Sample records for interim evaluation results

  1. Interim Results from Alternative Fuel Truck Evaluation Project

    SciTech Connect (OSTI)

    Kevin L. Chandler; Paul Norton; Nigel Clark

    1999-05-03T23:59:59.000Z

    The objective of this project, which is supported by the U.S. Department of Energy (DOE) through the National Renewable Energy Laboratory (NREL), is to provide a comprehensive comparison of heavy-duty trucks operating on alternative fuels and diesel fuel. Data collection from up to eight sites is planned. Currently, the project has four sites: Raley's in Sacramento, CA (Kenworth, Cummins LlO-300G, liquefied natural gas - LNG); Pima Gro Systems, Inc. in Fontana, CA (White/GMC, Caterpillar 31768 Dual-Fuel, compressed natural gas - CNG); Waste Management in Washington, PA (Mack, Mack E7G, LNG); and United Parcel Service in Hartford, CT (Freightliner Custom Chassis, Cummins B5.9G, CNG). This paper summarizes current data collection and evaluation results from this project.

  2. King County Metro Transit Hybrid Articulated Transit Buses: Interim Evaluation Results

    SciTech Connect (OSTI)

    Chandler, K.; Walkowicz, K.

    2006-04-01T23:59:59.000Z

    Interim technical report compares and evaluates new diesel and diesel hybrid-electric articulated buses operated as part of the King County Metro Transit (KC Metro) fleet in Seattle, Washington.

  3. New York City Transit Hybrid and CNG Transit Buses: Interim Evaluation Results

    SciTech Connect (OSTI)

    Chandler, K.; Eberts, E.; Eudy, L.

    2006-01-01T23:59:59.000Z

    This report focuses on the evaluation of compressed natural gas (CNG) and diesel hybrid electric bus propulsion systems in New York City Transit's transit buses.

  4. FedEx Gasoline Hybrid Electric Delivery Truck Evaluation: 6-Month Interim Report

    SciTech Connect (OSTI)

    Barnitt, R.

    2010-05-01T23:59:59.000Z

    This interim report presents partial (six months) results for a technology evaluation of gasoline hybrid electric parcel delivery trucks operated by FedEx in and around Los Angeles, CA. A 12 month in-use technology evaluation comparing in-use fuel economy and maintenance costs of GHEVs and comparative diesel parcel delivery trucks was started in April 2009. Comparison data was collected and analyzed for in-use fuel economy and fuel costs, maintenance costs, total operating costs, and vehicle uptime. In addition, this interim report presents results of parcel delivery drive cycle collection and analysis activities as well as emissions and fuel economy results of chassis dynamometer testing of a gHEV and a comparative diesel truck at the National Renewable Energy Laboratory's (NREL) ReFUEL laboratory. A final report will be issued when 12 months of in-use data have been collected and analyzed.

  5. ICPP radioactive liquid and calcine waste technologies evaluation. Interim report

    SciTech Connect (OSTI)

    Murphy, J.A.; Pincock, L.F.; Christiansen, I.N.

    1994-06-01T23:59:59.000Z

    The Department of Energy (DOE) has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage since 1951 and reprocessing since 1953. Until recently, the major activity of the ICPP has been the reprocessing of SNF to recover fissile uranium; however, changing world events have raised questions concerning the need to recover and recycle this material. In April 1992, DOE chose to discontinue reprocessing SNF for uranium recovery and shifted its focus toward the management and disposition of radioactive wastes accumulated through reprocessing activities. Currently, 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste) and 3,800 cubic meters (m{sup 3}) of calcine waste are in inventory at the ICPP. Legal drivers and agreements exist obligating the INEL to develop, demonstrate, and implement technologies for safe and environmentally sound treatment and interim storage of radioactive liquid and calcine waste. Candidate treatment processes and waste forms are being evaluated using the Technology Evaluation and Analysis Methodology (TEAM) Model. This process allows decision makers to (1) identify optimum radioactive waste treatment and disposal form alternatives; (2) assess tradeoffs between various optimization criteria; (3) identify uncertainties in performance parameters; and (4) focus development efforts on options that best satisfy stakeholder concerns. The Systems Analysis technology evaluation presented in this document supports the DOE in selecting the most effective radioactive liquid and calcine waste management plan to implement in compliance with established regulations, court orders, and agreements.

  6. Evaluation of 2004 Toyota Prius Hybrid Electric Drive System Interim Report

    SciTech Connect (OSTI)

    Ayers, C.W.

    2004-11-23T23:59:59.000Z

    Laboratory tests were conducted to evaluate the electrical and mechanical performance of the 2004 Toyota Prius and its hybrid electric drive system. As a hybrid vehicle, the 2004 Prius uses both a gasoline-powered internal combustion engine and a battery-powered electric motor as motive power sources. Innovative algorithms for combining these two power sources results in improved fuel efficiency and reduced emissions compared to traditional automobiles. Initial objectives of the laboratory tests were to measure motor and generator back-electromotive force (emf) voltages and determine gearbox-related power losses over a specified range of shaft speeds and lubricating oil temperatures. Follow-on work will involve additional performance testing of the motor, generator, and inverter. Information contained in this interim report summarizes the test results obtained to date, describes preliminary conclusions and findings, and identifies additional areas for further study.

  7. Sample Results From The Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-12-20T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  8. Sample Results from the Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-12-11T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  9. Accelerated alpha radiation damage in a ceramic waste form, interim results

    SciTech Connect (OSTI)

    Frank, S. M.; Johnson, S. G.; Moschetti, T. L.; O'Holleran, T. P.; Sinkler, W.; Esh, D.; Goff, K. M.

    1999-11-11T23:59:59.000Z

    Interim results are presented on the alpha-decay damage study of a {sup 238}Pu-loaded ceramic waste form (CWF). The waste form was developed to immobilize fission products and transuranic species accumulated from the electrometallurgical treatment of spent nuclear fuel. To evaluate the effects of {alpha}-decay damage on the waste form the {sup 238}Pu-loaded material was analyzed by (1) x-ray diffraction (XRD), (2) microstructure characterization by scanning electron microscopy (SEM) and transmission electron microscopy (TEM) with energy and wavelength dispersive spectroscopy (EDS/WDS) and electron diffraction, (3) bulk density measurements and (4) waste form durability, performed by the product consistency test (PCT). While the predominate phase of plutonium in the CWF, PuO{sub 2}, shows the expected unit cell expansion due to {alpha}-decay damage, currently no significant change has occurred to the macro- or microstructure of the material. The major phase of the waste form is sodalite and contains very little Pu, although the exact amount is unknown. Interestingly, measurement of the sodalite phase unit cell is also showing very slight expansion; again, presumably from {alpha}-decay damage.

  10. Results of benthic studies at Chalk Point. Interim report

    SciTech Connect (OSTI)

    Holland, A.F.; Hiegel, M.H.; Cargo, D.G.; Mountford, N.K.

    1980-01-01T23:59:59.000Z

    This report summarizes the results of annual cycle in the benthos of the Patuxent River and the effects of the Chalk Point Power Station on those benthos.

  11. RTD Biodiesel (B20) Transit Bus Evaluation: Interim Review Summary

    SciTech Connect (OSTI)

    Proc, K.; Barnitt, R.; McCormick, R. L.

    2005-08-01T23:59:59.000Z

    A summary of the data NREL collected from a project to evaluate the in-use performance of buses from the Regional Transportation District of Denver operating on B20.

  12. Environmental surveillance results for 1994 for the Hazelwood Interim Storage Site. FUSRAP technical memorandum Number 140-95-011

    SciTech Connect (OSTI)

    Szojka, S.

    1995-06-01T23:59:59.000Z

    This report presents analytical results and an interpretation of the results for samples collected as part of the 1994 environmental surveillance program for the Hazelwood Interim Storage Site (HISS) for the interim storage of radiologically contaminated soils. The discussion provides a comparative analysis of local background conditions and applicable regulatory criteria to results reported for external gamma radiation and for samples from the media investigated (air, surface water, sediment, groundwater, and stormwater). Results from the 1994 environmental surveillance program at HISS indicate that Department of Energy (DOE) guidelines were not exceeded for the calculated airborne particulate dose or for the monitored constituents.

  13. Evaluation of 2004 Toyota Prius Hybrid Electic Drive System Interim Report - Revised

    SciTech Connect (OSTI)

    Ayers, C.W.; Hsu, J.S.; Marlino, L.D.; Miller, C.W.; Ott, G.W., Jr.; Oland, C.B.; Burress, T.A.

    2007-07-31T23:59:59.000Z

    The 2004 Toyota Prius is a hybrid automobile equipped with a gasoline engine and a battery-powered electric motor. Both of these motive power sources are capable of providing mechanical drive power for the vehicle. The engine can deliver a peak power output of 57 kilowatts (kW) at 5000 revolutions per minute (rpm) while the motor can deliver a peak power output of 50 kW at 1300 rpm. Together, this engine-motor combination has a specified peak power output of 82 kW at a vehicle speed of 85 kilometers per hour (km/h). In operation, the 2004 Prius exhibits superior fuel economy compared to conventionally powered automobiles. Laboratory tests were conducted to evaluate the electrical and mechanical performance of the 2004 Toyota Prius and its hybrid electric drive system. As a hybrid vehicle, the 2004 Prius uses both a gasoline-powered internal combustion engine and a battery-powered electric motor as motive power sources. Innovative algorithms for combining these two power sources results in improved fuel efficiency and reduced emissions compared to traditional automobiles. Initial objectives of the laboratory tests were to measure motor and generator back-electromotive force (emf) voltages and determine gearbox-related power losses over a specified range of shaft speeds and lubricating oil temperatures. Follow-on work will involve additional performance testing of the motor, generator, and inverter. Information contained in this interim report summarizes the test results obtained to date, describes preliminary conclusions and findings, and identifies additional areas for further study.

  14. Deep Vadose Zone Treatability Test for the Hanford Central Plateau: Interim Post-Desiccation Monitoring Results

    SciTech Connect (OSTI)

    Truex, Michael J.; Oostrom, Martinus; Strickland, Christopher E.; Johnson, Timothy C.; Johnson, Christian D.; Clayton, Ray E.; Chronister, Glen B.

    2013-09-01T23:59:59.000Z

    A field test of desiccation is being conducted as an element of the deep vadose zone treatability test program. Desiccation technology relies on removal of water from a portion of the subsurface such that the resultant low moisture conditions inhibit downward movement of water and dissolved contaminants. Previously, a field test report (Truex et al. 2012a) was prepared describing the active desiccation portion of the test and initial post-desiccation monitoring data. Additional monitoring data have been collected at the field test site during the post-desiccation period and is reported herein along with interpretation with respect to desiccation performance. This is an interim report including about 2 years of post-desiccation monitoring data.

  15. King County Metro Transit Hybrid Articulated Buses: Interim Evaluation Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHigh SchoolIn12electron beamJoin2015JustKateKent5 B O N N EKim

  16. VTA Prototype Fuel Cell Bus Evaluation: Interim Results (Presentation) |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your DensityEnergy U.S.-China Electric Vehicle and03/02 TUE 08:59CapabilityVulnerabilities |2Participant

  17. INDEPENDENT TECHNICAL REVIEW OF THE C-400 INTERIM REMEDIAL PROJECT PHASE I RESULTS, PADUCAH, KENTUCKY

    SciTech Connect (OSTI)

    Looney, B.; Rossabi, J.; Stewart,L.; Richards, W.

    2010-10-29T23:59:59.000Z

    The groundwater and soil in the vicinity of the C-400 Building at the Paducah Gaseous Diffusion Plant (PGDP), is contaminated with substantial quantities of industrial solvents, primarily trichoroethene (TCE). This solvent 'source' is recognized as a significant challenge and an important remediation target in the overall environmental cleanup strategy for PGDP. Thus, the cleanup of the C-400 TCE Source is a principal focus for the Department of Energy (DOE) and its contractors, and for PGDP regulators and stakeholders. Using a formal investigation, feasibility study and decision process, Electrical Resistance Heating (ERH) was selected for the treatment of the soil and groundwater in the vicinity of C-400. ERH was selected as an interim action to remove 'a significant portion of the contaminant mass of TCE at the C-400 Cleaning Building area through treatment' with the longer term goal of reducing 'the period the TCE concentration in groundwater remains above its Maximum Contaminant Level (MCL).' ERH is a thermal treatment that enhances the removal of TCE and related solvents from soil and groundwater. The heterogeneous conditions at PGDP, particularly the high permeability regional gravel aquifer (RGA), are challenging to ERH. Thus, a phased approach is being followed to implement this relatively expensive and complex remediation technology. Conceptually, the phased approach encourages safety and efficiency by providing a 'lessons learned' process and allowing appropriate adjustments to be identified and implemented prior to follow-on phase(s) of treatment. More specifically, early deployment targeted portions of the challenging RGA treatment zone with relatively little contamination reducing the risk of adverse collateral impacts from underperformance in terms of heating and capture. Because of the importance and scope of the C-400 TCE source remediation activities, DOE chartered an Independent Technical Review (ITR) in 2007 to assess the C-400 ERH plans prior to deployment and a second ITR to evaluate Phase I performance in September 2010. In this report, these ITR efforts are referenced as the '2007 ITR' and the 'current ITR', respectively. The 2007 ITR document (Looney et al., 2007) provided a detailed technical evaluation that remains relevant and this report builds on that analysis. The primary objective of the current ITR is to provide an expedited assessment of the available Phase I data to assist the PGDP team as they develop the lessons learned from Phase I and prepare plans for Phase II.

  18. Safety evaluation of interim stabilization of non-stabilized single-shell watch list tanks

    SciTech Connect (OSTI)

    Stahl, S.M.

    1994-12-30T23:59:59.000Z

    The report provides a summation of the status of safety issues associated with interim stabilization of Watch List SSTs (organic, ferrocyanide, and flammable gas), as extracted from recent safety analyses, including the Tank Farms Accelerated Safety Analysis efforts.

  19. Evaluation of Dynamic Behavior of Pile Foundations for Interim Storage Facilities Through Geotechnical Centrifuge Tests

    SciTech Connect (OSTI)

    Shizuo Tsurumaki [Nuclear Power Engineering Corporation, Fujitakanko Toranomon Bldg. 7F, 3-17-1 Toranomon, Minato-ku, Tokyo 105-0001 (Japan); Hiroyuki Watanabe [Saitama University, 255 Shimo-Okubo, Sakura-ku, Saitama City, Saitama 338-8570 (Japan); Akira Tateishi; Kenichi Horikoshi; Shunichi Suzuki [Taisei Corporation, 1-25-1, Nishi-Shinjuku, Shinjuku-ku, Tokyo 163-0606 (Japan)

    2002-07-01T23:59:59.000Z

    In Japan, there is a possibility that interim storage facilities for recycled nuclear fuel resources may be constructed on quaternary layers, rather than on hard rock. In such a case, the storage facilities need to be supported by pile foundations or spread foundations to meet the required safety level. The authors have conducted a series of experimental studies on the dynamic behavior of storage facilities supported by pile foundations. A centrifuge modeling technique was used to satisfy the required similitude between the reduced size model and the prototype. The centrifuge allows a high confining stress level equivalent to prototype deep soils to be generated (which is considered necessary for examining complex pile-soil interactions) as the soil strength and the deformation are highly dependent on the confining stress. The soil conditions were set at as experimental variables, and the results are compared. Since 2000, the Nuclear Power Engineering Corporation (NUPEC) has been conducting these research tests under the auspices on the Ministry of Economy, Trade and Industry of Japan. (authors)

  20. PROJECT W-551 INTERIM PRETREATMENT SYSTEM TECHNOLOGY SELECTION SUMMARY DECISION REPORT AND RECOMMENDATION

    SciTech Connect (OSTI)

    CONRAD EA

    2008-08-12T23:59:59.000Z

    This report provides the conclusions of the tank farm interim pretreatment technology decision process. It documents the methodology, data, and results of the selection of cross-flow filtration and ion exchange technologies for implementation in project W-551, Interim Pretreatment System. This selection resulted from the evaluation of specific scope criteria using quantitative and qualitative analyses, group workshops, and technical expert personnel.

  1. Safety evaluation for the interim stabilization of Tank 241-C-103

    SciTech Connect (OSTI)

    Geschke, G.R.

    1995-03-01T23:59:59.000Z

    This document provides the basis for interim stabilization of tank 241-C-103. The document covers the removal of the organic liquid layer and the aqueous supernatant from tank 241-C-103. Hazards are identified, consequences are calculated and controls to mitigate or prevent potential accidents are developed.

  2. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification MST Solids Sample

    SciTech Connect (OSTI)

    Washington, A. L. II; Peters, T. B.

    2013-09-19T23:59:59.000Z

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 7 processing. The Marcrobatch 7 material was received with visible fine particulate solids, atypical for these samples. The as received material was allowed to settle for a period greater than 24 hours. The supernatant was then decanted and utilized as our clarified feed material. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test using the clarified feed material. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake after filtration from H-Tank Farm (HTF) feed salt solution. The results of these analyses are reported and are within historical precedent.

  3. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Washington, A. L. II

    2013-08-08T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 7 for the Interim Salt Disposition Program (ISDP). An ARP and several ESS tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP/MCU. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. A demonstration of the monosodium titanate (0.2 g/L) removal of strontium and actinides provided acceptable 4 hour average decontamination factors for Pu and Sr of 3.22 and 18.4, respectively. The Four ESS tests also showed acceptable behavior with distribution ratios (D(Cs)) values of 15.96, 57.1, 58.6, and 65.6 for the MCU, cold blend, hot blend, and Next Generation Solvent (NGS), respectively. The predicted value for the MCU solvent was 13.2. Currently, there are no models that would allow a prediction of extraction behavior for the other three solvents. SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed. While no outstanding issues were noted, the presence of solids in the samples should be investigated in future work. It is possible that the solids may represent a potential reservoir of material (such as potassium) that could have an impact on MCU performance if they were to dissolve back into the feed solution. This salt batch is intended to be the first batch to be processed through MCU entirely using the new NGS-MCU solvent.

  4. Interim Project Results: United Parcel Service's Second-Generation Hybrid-Electric Delivery Vans (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2012-01-01T23:59:59.000Z

    This fact sheet describes the performance evaluation of United Parcel Service's second-generation hybrid-electric delivery vans. The Fleet Test and Evaluation Team at the National Renewable Energy Laboratory (NREL) is evaluating the 18-month, in-service performance of 11 of these vans along with 11 comparable conventional diesel vans operating in Minneapolis, Minnesota. As a complement to the field study, the team recently completed fuel economy and emissions testing at NREL's Renewable Fuels and Lubricants (ReFUEL) laboratory.

  5. Immobilized High Level Waste (HLW) Interim Storage Alternative Generation and analysis and Decision Report 2nd Generation Implementing Architecture

    SciTech Connect (OSTI)

    CALMUS, R.B.

    2000-09-14T23:59:59.000Z

    Two alternative approaches were previously identified to provide second-generation interim storage of Immobilized High-Level Waste (IHLW). One approach was retrofit modification of the Fuel and Materials Examination Facility (FMEF) to accommodate IHLW. The results of the evaluation of the FMEF as the second-generation IHLW interim storage facility and subsequent decision process are provided in this document.

  6. Economic Impacts of Reduced Delta Exports Resulting from the Wanger Interim Order for Delta Smelt

    E-Print Network [OSTI]

    Sunding, David L.; Ajami, Newsha K; Hatchett, Steve; Mitchell, David; Zilberman, David

    2009-01-01T23:59:59.000Z

    Impacts of Reduced Delta Exports Resulting from the WangerImpacts of Reduced Delta Exports Resulting from the WangerOrder restricts water exports from the Delta to agricultural

  7. Plug-In Hybrid Electric Vehicle Value Proposition Study: Interim Report: Phase I Scenario Evaluation

    SciTech Connect (OSTI)

    Sikes, Karen R [ORNL; Markel, Lawrence C [ORNL; Hadley, Stanton W [ORNL; Hinds, Shaun [Sentech, Inc.; DeVault, Robert C [ORNL

    2009-01-01T23:59:59.000Z

    Plug-in hybrid electric vehicles (PHEVs) offer significant improvements in fuel economy, convenient low-cost recharging capabilities, potential environmental benefits, and decreased reliance on imported petroleum. However, the cost associated with new components (e.g., advanced batteries) to be introduced in these vehicles will likely result in a price premium to the consumer. This study aims to overcome this market barrier by identifying and evaluating value propositions that will increase the qualitative value and/or decrease the overall cost of ownership relative to the competing conventional vehicles and hybrid electric vehicles (HEVs) of 2030 During this initial phase of this study, business scenarios were developed based on economic advantages that either increase the consumer value or reduce the consumer cost of PHEVs to assure a sustainable market that can thrive without the aid of state and Federal incentives or subsidies. Once the characteristics of a thriving PHEV market have been defined for this timeframe, market introduction steps, such as supportive policies, regulations and temporary incentives, needed to reach this level of sustainability will be determined. PHEVs have gained interest over the past decade for several reasons, including their high fuel economy, convenient low-cost recharging capabilities, potential environmental benefits and reduced use of imported petroleum, potentially contributing to President Bush's goal of a 20% reduction in gasoline use in ten years, or 'Twenty in Ten'. PHEVs and energy storage from advanced batteries have also been suggested as enabling technologies to improve the reliability and efficiency of the electric power grid. However, PHEVs will likely cost significantly more to purchase than conventional or other hybrid electric vehicles (HEVs), in large part because of the cost of batteries. Despite the potential long-term savings to consumers and value to stakeholders, the initial cost of PHEVs presents a major market barrier to their widespread commercialization. The purpose of this project is to identify and evaluate value-added propositions for PHEVs that will help overcome this market barrier. Candidate value propositions for the initial case study were chosen to enhance consumer acceptance of PHEVs and/or compatibility with the grid. Potential benefits of such grid-connected vehicles include the ability to supply peak load or emergency power requirements of the grid, enabling utilities to size their generation capacity and contingency resources at levels below peak. Different models for vehicle/battery ownership, leasing, financing and operation, as well as the grid, communications, and vehicle infrastructure needed to support the proposed value-added functions were explored during Phase 1. Rigorous power system, vehicle, financial and emissions modeling were utilized to help identify the most promising value propositions and market niches to focus PHEV deployment initiatives.

  8. Interim Test Procedures for Evaluating Electrical Performance and Grid Integration of Vehicle-to-Grid Applications

    SciTech Connect (OSTI)

    Chakraborty, S.; Kramer, W.; Kroposki, B.; Martin, G.; McNutt, P.; Kuss, M.; Markel, T.; Hoke, A.

    2011-06-01T23:59:59.000Z

    The objective of this report is to provide a test plan for V2G testing. The test plan is designed to test and evaluate the vehicle's power electronics capability to provide power to the grid, and to evaluate the vehicle's ability to connect and disconnect from the utility according to a subset of the IEEE Std. 1547 tests.

  9. Evaluation of Shear Strength Threshold of Concern for Retrieval of Interim-Stored K-Basin Sludge in the Hanford Site

    SciTech Connect (OSTI)

    Onishi, Yasuo; Yokuda, Satoru T.; Schmidt, Andrew J.

    2010-11-01T23:59:59.000Z

    K-Basin sludge will be recovered into the Sludge Transport and Storage Containers (STSCs) and will be stored in the T Plant for interim storage (at least 10 years). Long-term sludge storage tests conducted by Pacific Northwest National Laboratory show that high uranium content K Basin sludge can self-cement and form a strong sludge with a bulk shear strength of up to 65 kPa. Some of this sludge has "paste" and "chunks" with shear strengths of approximately 3~5 kPa and 380 ~ 770 kPa, respectively. High uranium content sludge samples subjected to hydrothermal testing (e.g., 185°C, 10 h) have been observed to form agglomerates with a shear strength up to 170 kPa. After interim storage at T Plant, the sludge in the STSCs will be mobilized by water jets impinging the sludge. The objective of the evaluation was to determine the range of sludge shear strength for which there is high confidence that a water-jet retrieval system can mobilize stored K-Basin sludge from STSCs. The shear strength at which the sludge can be retrieved is defined as the "shear strength threshold of concern." If the sludge shear strength is greater than the value of the shear strength threshold of concern, a water-jet retrieval system will be unlikely to mobilize the sludge up to the container’s walls. The shear strength threshold of concern can be compared with the range of possible shear strengths of K-Basin stored sludge to determine if the current post interim-storage, water-jet retrieval method is adequate. Fourteen effective cleaning radius (ECR) models were reviewed, and their validity was examined by applying them to Hanford 241-SY-101 and 241-AZ-101 Tanks to reproduce the measured ECR produced by the mixer pumps. The validation test identified that the Powell-3 and Crowe-2 ECR models are more accurate than other ECR models reviewed. These ECR models were used to address a question as to whether the effective cleaning radius of a water jet is sufficient or if it can be readily expanded to cover the range of possible shear strengths. These results will assist CH2M HILL Plateau Remediation Company (CHPRC) to establish the technical basis of the feasibility of the sludge retrieval and storage plan and to develop an adequate water jet system to retrieve the stored K-Basin sludge in the STSCs. The STSCs are 2:1 elliptical-head vessels, 58 inches in diameter and 105 inches tall. Each STSC will contain 0.5 to 2.1 m3 of settled sludge with the specific loading dependent upon sludge type.

  10. Evaluation of Juvenile Fall Chinook Stranding on the Hanford Reach, 1997-1999 Interim Report.

    SciTech Connect (OSTI)

    Wagner, Paul; Nugent, John; Price, William (Washington Department of Fish and Wildlife, Olympia, WA)

    1999-02-15T23:59:59.000Z

    Pilot work conducted in 1997 to aid the development of the study for the 1998 Evaluation of Juvenile Fall Chinook Stranding on The Hanford Reach. The objectives of the 1997 work were to: (1) identify juvenile chinook production and rearing areas..., (2) identify sampling sites and develop the statistical parameters necessary to complete the study, (3) develop a study plan..., (4) conduct field sampling activities...

  11. A review of proposed Glen Canyon Dam interim operating criteria

    SciTech Connect (OSTI)

    LaGory, K.; Hlohowskyj, I.; Tomasko, D.; Hayse, J.; Durham, L.

    1992-04-01T23:59:59.000Z

    Three sets of interim operating criteria for Glen Canyon Dam on the Colorado River have been proposed for the period of November 1991, to the completion of the record of decision for the Glen Canyon Dam environmental impact statement (about 1993). These criteria set specific limits on dam releases, including maximum and minimum flows, up-ramp and down-ramp rates, and maximum daily fluctuation. Under the proposed interim criteria, all of these parameters would be reduced relative to historical operating criteria to protect downstream natural resources, including sediment deposits, threatened and endangered fishes, trout, the aquatic food base, and riparian plant communities. The scientific bases of the three sets of proposed operating criteria are evaluated in the present report:(1) criteria proposed by the Research/Scientific Group, associated with the Glen Canyon Environmental Studies (GCES); (2) criteria proposed state and federal officials charged with managing downstream resources; and (3) test criteria imposed from July 1991, to November 1991. Data from Phase 1 of the GCES and other sources established that the targeted natural resources are affected by dam operations, but the specific interim criteria chosen were not supported by any existing studies. It is unlikely that irreversible changes to any of the resources would occur over the interim period if historical operating criteria remained in place. It is likely that adoption of any of the sets of proposed interim operating criteria would reduce the levels of sediment transport and erosion below Glen Canyon Dam; however, these interim criteria could result in some adverse effects, including the accumulation of debris at tributary mouths, a shift of new high-water-zone vegetation into more flood-prone areas, and further declines in vegetation in the old high water zone.

  12. Deep Vadose Zone Treatability Test for the Hanford Central Plateau: Interim Post-Desiccation Monitoring Results, Fiscal Year 2014

    SciTech Connect (OSTI)

    Truex, Michael J.; Strickland, Christopher E.; Johnson, Christian D.; Johnson, Timothy C.; Clayton, Ray E.; Chronister, Glen B.

    2014-09-01T23:59:59.000Z

    Over decades of operation, the U.S. Department of Energy (DOE) and its predecessors have released nearly 2 trillion L (450 billion gal.) of liquid into the vadose zone at the Hanford Site. Much of this discharge of liquid waste into the vadose zone occurred in the Central Plateau, a 200 km2 (75 mi2) area that includes approximately 800 waste sites. Some of the inorganic and radionuclide contaminants in the deep vadose zone at the Hanford Site are at depths below the limit of direct exposure pathways, but may need to be remediated to protect groundwater. The Tri-Party Agencies (DOE, U.S. Environmental Protection Agency, and Washington State Department of Ecology) established Milestone M 015 50, which directed DOE to submit a treatability test plan for remediation of technetium-99 (Tc-99) and uranium in the deep vadose zone. These contaminants are mobile in the subsurface environment and have been detected at high concentrations deep in the vadose zone, and at some locations have reached groundwater. Testing technologies for remediating Tc-99 and uranium will also provide information relevant for remediating other contaminants in the vadose zone. A field test of desiccation is being conducted as an element of the DOE test plan published in March 2008 to meet Milestone M 015 50. The active desiccation portion of the test has been completed. Monitoring data have been collected at the field test site during the post-desiccation period and are reported herein. This is an interim data summary report that includes about 3 years of post-desiccation monitoring data. The DOE field test plan proscribes a total of 5 years of post-desiccation monitoring.

  13. New York City Transit Hybrid and CNG Transit Buses: Interim Evaluation Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible for Renewable Energy:Nanowire Solar541,9337, 2011RNew Visible to BroadbandNew YorkNew

  14. Plutonium Finishing Plant. Interim plutonium stabilization engineering study

    SciTech Connect (OSTI)

    Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J. [Pacific Northwest Lab., Richland, WA (United States); Nass, R. [Nuclear Fuel Services, Inc. (United States)

    1995-08-01T23:59:59.000Z

    This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage.

  15. Randomized Controlled Trial of Forward-Planned Intensity Modulated Radiotherapy for Early Breast Cancer: Interim Results at 2 Years

    SciTech Connect (OSTI)

    Barnett, Gillian C. [Department of Oncology, University of Cambridge, Cambridge University Hospitals, National Health Service Foundation Trust, Cambridge (United Kingdom); Wilkinson, Jennifer S.; Moody, Anne M.; Wilson, Charles B.; Twyman, Nicola [Oncology Centre, Cambridge University Hospitals, National Health Services Foundation Trust, Cambridge (United Kingdom); Wishart, Gordon C. [Cambridge Breast Unit, Addenbrooke's Hospital, Cambridge (United Kingdom); Burnet, Neil G. [Department of Oncology, University of Cambridge, Cambridge University Hospitals, National Health Service Foundation Trust, Cambridge (United Kingdom); Coles, Charlotte E., E-mail: charlotte.coles@addenbrookes.nhs.uk [Oncology Centre, Cambridge University Hospitals, National Health Services Foundation Trust, Cambridge (United Kingdom)

    2012-02-01T23:59:59.000Z

    Purpose: This single-center randomized trial was designed to investigate whether intensity-modulated radiotherapy (IMRT) reduces late toxicity in patients with early-stage breast cancer. Methods and Materials: The standard tangential plans of 1,145 nonselected patients were analyzed. The patients with inhomogeneous plans were randomized to a simple method of forward-planned IMRT or standard radiotherapy (RT). The primary endpoint was serial photographic assessment of breast shrinkage. Results: At 2 years, no significant difference was found in the development of any photographically assessed breast shrinkage between the patients randomized to the interventional or control group (odds ratio, 1.51; 95% confidence interval, 0.83-1.58; p = .41). The patients in the control group were more likely to develop telangiectasia than those in the IMRT group (odds ratio, 1.68; 95% confidence interval 1.13-2.40; p = .009). Poor baseline surgical cosmesis resulted in poor overall cosmesis at 2 years after RT. In patients who had good surgical cosmesis, those randomized to IMRT were less likely to deteriorate to a moderate or poor overall cosmesis than those in the control group (odds ratio, 0.63; 95% confidence interval, 0.39-1.03, p = .061). Conclusions: IMRT can lead to a significant reduction in telangiectasia at comparatively early follow-up of only 2 years after RT completion. An important component of breast induration and shrinkage will actually result from the surgery and not from the RT. Surgical cosmesis is an important determinant of overall cosmesis and could partially mask the longer term benefits of IMRT at this early stage.

  16. Interim Results from a Study of the Impacts of Tin (II) Based Mercury Treatment in a Small Stream Ecosystem: Tims Branch, Savannah River Site

    SciTech Connect (OSTI)

    Looney, Brian [Savannah River National Laboratory (SRNL); BryanJr., Larry [Savannah River Ecology Laboratory; Mathews, Teresa J [ORNL; Peterson, Mark J [ORNL; Roy, W Kelly [ORNL; Jett, Robert T [ORNL; Smith, John G [ORNL

    2012-03-01T23:59:59.000Z

    A research team is assessing the impacts of an innovative mercury treatment system in Tims Branch, a small southeastern stream. The treatment system, installed in 2007, reduces and removes inorganic mercury from water using tin(II) (stannous) chloride addition followed by air stripping. The system results in discharge of inorganic tin to the ecosystem. This screening study is based on historical information combined with measurements of contaminant concentrations in water, fish, sediment, biofilms and invertebrates. Initial mercury data indicate that first few years of mercury treatment resulted in a significant decrease in mercury concentration in an upper trophic level fish, redfin pickerel, at all sampling locations in the impacted reach. For example, the whole body mercury concentration in redfin pickerel collected from the most impacted pond decreased approximately 72% between 2006 (pre-treatment) and 2010 (post-treatment). Over this same period, mercury concentrations in the fillet of redfin pickerel in this pond were estimated to have decreased from approximately 1.45 {micro}g/g (wet weight basis) to 0.45 {micro}g/g - a decrease from 4.8x to 1.5x the current EPA guideline concentration for mercury in fillet (0.3 {micro}g/g). Thermodynamic modeling, scanning electron microscopy, and other sampling data for tin suggest that particulate tin (IV) oxides are a significant geochemical species entering the ecosystem with elevated levels of tin measured in surficial sediments and biofilms. Detectable increases in tin in sediments and biofilms extended approximately 3km from the discharge location. Tin oxides are recalcitrant solids that are relatively non-toxic and resistant to dissolution. Work continues to develop and validate methods to analyze total tin in the collected biota samples. In general, the interim results of this screening study suggest that the treatment process has performed as predicted and that the concentration of mercury in upper trophic level fish, as a surrogate for all of the underlying transport and transformation processes in a complex ecosystem, has declined as a direct result of the elimination of inorganic mercury inputs. Inorganic tin released to the ecosystem has been found in compartments where particles accumulate with notable levels measured in biofilms.

  17. Evaluation of interim and final waste forms for the newly generated liquid low-level waste flowsheet

    SciTech Connect (OSTI)

    Abotsi, G.M.K. [Clark Atlanta Univ., GA (United States); Bostick, D.T.; Beck, D.E. [Oak Ridge National Lab., TN (United States)] [and others

    1996-05-01T23:59:59.000Z

    The purpose of this review is to evaluate the final forms that have been proposed for radioactive-containing solid wastes and to determine their application to the solid wastes that will result from the treatment of newly generated liquid low-level waste (NGLLLW) and Melton Valley Storage Tank (MVST) supernate at the Oak Ridge National Laboratory (ORNL). Since cesium and strontium are the predominant radionuclides in NGLLLW and MVST supernate, this review is focused on the stabilization and solidification of solid wastes containing these radionuclides in cement, glass, and polymeric materials-the principal waste forms that have been tested with these types of wastes. Several studies have shown that both cesium and strontium are leached by distilled water from solidified cement, although the leachabilities of cesium are generally higher than those of strontium under similar conditions. The situation is exacerbated by the presence of sulfates in the solution, as manifested by cracking of the grout. Additives such as bentonite, blast-furnace slag, fly ash, montmorillonite, pottery clay, silica, and zeolites generally decrease the cesium and strontium release rates. Longer cement curing times (>28 d) and high ionic strengths of the leachates, such as those that occur in seawater, also decrease the leach rates of these radionuclides. Lower cesium leach rates are observed from vitrified wastes than from grout waste forms. However, significant quantities of cesium are volatilized due to the elevated temperatures required to vitrify the waste. Hence, vitrification will generally require the use of cleanup systems for the off-gases to prevent their release into the atmosphere.

  18. INTERIM POLICY JANUARY 9, 2004

    E-Print Network [OSTI]

    Chen, Tsuhan

    INTERIM POLICY JANUARY 9, 2004 CORNELL UNIVERSITY POLICY LIBRARY Health and Safety POLICY 2 _________________________________________________________________________________________________________________________________________________ POLICY STATEMENT. _________________________________________________________________________________________________________________________________________________ REASON FOR POLICY

  19. Evaluation of higher distribution and/or utilization voltages. First interim report (December 1978): literature search and problem definition

    SciTech Connect (OSTI)

    Not Available

    1981-04-01T23:59:59.000Z

    A literature search has been conducted on the economics and technical problems associated with the use of higher voltages in both the primary distribution and secondary utilization systems. After a literature review and evaluation, an assessment of the state-of-the-art with regard to high voltage has been made and is presented for the primary and secondary distribution systems, end use elements, and economics and system analysis or optimization. An annotated bibliography is provided for each of the three categories. A comprehensive list of potential advantages and disadvantages of higher primary distribution and utilization voltages has also been prepared and is presented.

  20. Policy Statement and Interim

    E-Print Network [OSTI]

    Hemami, Sheila S.

    1 Policy Statement and Interim Procedures CORNELL UNIVERSITY POLICY LIBRARY POLICY 8.3 Volume: 8 Emergency Planning POLICY STATEMENT Cornell University organizes, coordinates, and directs available of this effort is dependent on the development of periodic review of comprehensive plans. This policy includes

  1. LOUISE LENNIHAN Interim Provost

    E-Print Network [OSTI]

    Dennehy, John

    is Interim Provost and Senior Vice President for Academic Affairs at the Graduate Center. In her role, she and Effectiveness, the Mina Rees Library, Student Affairs, and Research and Sponsored Programs, as well from the Social Science Research Council, the National Science Foundation, NIMH, and Fulbright

  2. Standard guide for evaluation of materials used in extended service of interim spent nuclear fuel dry storage systems

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 Part of the total inventory of commercial spent nuclear fuel (SNF) is stored in dry cask storage systems (DCSS) under licenses granted by the U.S. Nuclear Regulatory Commission (NRC). The purpose of this guide is to provide information to assist in supporting the renewal of these licenses, safely and without removal of the SNF from its licensed confinement, for periods beyond those governed by the term of the original license. This guide provides information on materials behavior under conditions that may be important to safety evaluations for the extended service of the renewal period. This guide is written for DCSS containing light water reactor (LWR) fuel that is clad in zirconium alloy material and stored in accordance with the Code of Federal Regulations (CFR), at an independent spent-fuel storage installation (ISFSI). The components of an ISFSI, addressed in this document, include the commercial SNF, canister, cask, and all parts of the storage installation including the ISFSI pad. The language of t...

  3. Immobilized high-level waste interim storage alternatives generation and analysis and decision report

    SciTech Connect (OSTI)

    CALMUS, R.B.

    1999-05-18T23:59:59.000Z

    This report presents a study of alternative system architectures to provide onsite interim storage for the immobilized high-level waste produced by the Tank Waste Remediation System (TWRS) privatization vendor. It examines the contract and program changes that have occurred and evaluates their impacts on the baseline immobilized high-level waste (IHLW) interim storage strategy. In addition, this report documents the recommended initial interim storage architecture and implementation path forward.

  4. Stability of Biodiesel and Biodiesel Blends: Interim Report

    SciTech Connect (OSTI)

    McCormick, R. L.; Alleman, T. L.; Waynick, J. A.; Westbrook, S. R.; Porter, S.

    2006-04-01T23:59:59.000Z

    This is an interim report for a study of biodiesel oxidative stability. It describes characterization and accelerated stability test results for 19 B100 samples and six diesel fuels.

  5. Kathleen Carlson Appointed Interim Acting Deputy Administrator...

    National Nuclear Security Administration (NNSA)

    Interim Acting Deputy Administrator for Defense Programs Press Release Aug 16, 2001 Kathleen Carlson Appointed Interim Acting Deputy Administrator for Defense Programs...

  6. Yosemite Waters Vehicle Evaluation Report: Final Results

    SciTech Connect (OSTI)

    Eudy, L.; Barnitt, R.; Alleman, T. L.

    2005-08-01T23:59:59.000Z

    Document details the evaluation of Fischer-Tropsch diesel, a gas-to-liquid fuel, in medium-duty delivery vehicles at Yosemite Waters. The study was conducted by NREL at the company's Fullerton, California, bottling headquarters.

  7. Interim storage study report

    SciTech Connect (OSTI)

    Rawlins, J.K.

    1998-02-01T23:59:59.000Z

    High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration.

  8. Interim Action Determination

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment of EnergyIndustry15Among States in theWAPA1 DOEAnalysisInterim

  9. 1998 interim 242-A Evaporator tank system integrity assessment report

    SciTech Connect (OSTI)

    Jensen, C.E.

    1998-07-02T23:59:59.000Z

    This Integrity Assessment Report (IAR) is prepared by Fluor Daniel Northwest (FDNW) under contract to Lockheed-Martin Hanford Company (LMHC) for Waste Management Hanford (WMH), the 242-A Evaporator (facility) operations contractor for Fluor Daniel Hanford, and the US Department of Energy, the system owner. The contract specifies that FDNW perform an interim (5 year) integrity assessment of the facility and prepare a written IAR in accordance with Washington Administrative Code (WAC) 173-303-640. The WAC 173-303 defines a treatment, storage, or disposal (TSD) facility tank system as the ``dangerous waste storage or treatment tank and its ancillary equipment and containment.`` This integrity assessment evaluates the two tank systems at the facility: the evaporator vessel, C-A-1 (also called the vapor-liquid separator), and the condensate collection tank, TK-C-100. This IAR evaluates the 242-A facility tank systems up to, but not including, the last valve or flanged connection inside the facility perimeter. The initial integrity assessment performed on the facility evaluated certain subsystems not directly in contact with dangerous waste, such as the steam condensate and used raw water subsystems, to provide technical information. These subsystems were not evaluated in this IAR. The last major upgrade to the facility was project B-534. The facility modifications, as a result of project B-534, were evaluated in the 1993 facility interim integrity assessment. Since that time, the following upgrades have occurred in the facility: installation of a process condensate recycle system, and installation of a package steam boiler to provide steam for the facility. The package boiler is not within the scope of the facility TSD.

  10. Summary of Test Results for the Interagency Field Test &Evaluation...

    Broader source: Energy.gov (indexed) [DOE]

    Summary of Test Results for the Interagency Field Test &Evaluation of Wind Turbine - Radar Interference Mitigation Technologies Summary of Test Results for the Interagency Field...

  11. Ground-water hydrologic effects resulting from underground coal gasification experiments at the Hoe Creek Site near Gillette, Wyoming. Interim report, October 1979-March 1980

    SciTech Connect (OSTI)

    Raber, E.; Stone, R.

    1980-05-01T23:59:59.000Z

    This technical note summarizes our activities, to date, on the research project: Ground-Water Hydrologic Effects Resulting from Underground Coal Gasification Experiments (EPA-IAG-79-D-X0795). The gasified coal seam (Felix No. 2 coal) and two overlying aquifers (Felix No. 1 coal and overlying sand) appear to have become interconnected as a result of roof collapse and subsidence at both Hoe Creek Sites II and III near Gillette, Wyoming. To evaluate changes in the ground-water flow regime at the two sites, completion of supplementary wells was necessary to define the distance versus head drawdown relationships in each of the three aquifers. Hydraulic head potentials have been measured at Site III since gasification ended on October 10, 1979. These data are presented in graphic format. Although hydraulic head measurements at Site II seemed to be approaching a steady-state condition 1.5 years after gasification, the subsequent gasification at Site III temporarily altered the ground-water flow patterns. These changes will have a definite effect on contaminant dispersal and will need to be taken into consideration.

  12. Global Positioning System receiver evaluation results

    SciTech Connect (OSTI)

    Byrne, R.H.

    1993-09-01T23:59:59.000Z

    A Sandia project currently uses an outdated Magnavox 6400 Global Positioning System (GPS) receiver as the core of its navigation system. The goal of this study was to analyze the performance of the current GPS receiver compared to newer, less expensive models and to make recommendations on how to improve the performance of the overall navigation system. This paper discusses the test methodology used to experimentally analyze the performance of different GPS receivers, the test results, and recommendations on how an upgrade should proceed. Appendices contain detailed information regarding the raw data, test hardware, and test software.

  13. Interim Design Report

    E-Print Network [OSTI]

    R. J. Abrams; S. K. Agarwalla; A. Alekou; C. Andreopoulos; C. M. Ankenbrandt; S. Antusch; M. Apollonio; M. Aslaninejad; J. Back; P. Ballett; G. Barker; K. B. Beard; E. Benedetto; J. R. J. Bennett; J. S. Berg; S. Bhattacharya; V. Blackmore; M. Blennow; A. Blondel; A. Bogacz; M. Bonesini; C. Bontoiu; C. Booth; C. Bromberg; S. Brooks; A. Bross; O. Caretta; A. Cervera-Villanueva; S. Choubey; D. Cline; J. Cobb; P. Coloma; L. Coney; M. A. C. Cummings; T. Davenne; A. de Gouvea; C. Densham; X. Ding; A. Donini; P. Dornan; M. Dracos; F. Dufour; R. Eccleston; R. Edgecock; I. Efthymiopoulos; M. Ellis; E. Fernandez-Martinez; R. Fernow; G. Flanagan; J. C. Gallardo; R. Gandhi; R. Garoby; B. Gavela; S. Geer; S. Gilardoni; J. J. Gomez-Cadenas; S. Goswami; V. B. Graves; R. Gupta; G. Hanson; P. Harrison; T. Hart; P. Hernandez; P. Huber; D. Indumathi; R. P. Johnson; C. Johnstone; Y. Karadzhov; D. Kelliher; H. Kirk; J. Kopp; Y. Kudenko; Y. Kuno; A. Kurup; P. Kyberd; A. Laing; T. Li; M. Lindner; K. Long; J. Lopez Pavon; P. Loveridge; S. Machida; D. Majumdar; M. Maltoni; J. Martin-Albo; M. Martini; R. Matev; K. T. McDonald; A. McFarland; D. Meloni; M. Mezzetto; P. Migliozzi; S. R. Mishra; N. Mokhov; N. Mondal; J. Morfin; Y. Mori; V. Morozov; D. Neuffer; T. Ota; V. Palladino; S. Parke; S. Pascoli; J. Pasternak; J. Peltoniemi; R. Petti; T. Planche; M. Popovic; J. Pozimski; G. Prior; C. Prior; G. Rees; S. Rigolin; T. J. Roberts; Y. Roblin; C. Rogers; R. Samulyak; T. Schwetz; N. Simos; N. Sinha; G. Skoro; P. Snopok; F. J. P. Soler; N. Souchlas; J. Strait; D. Stratakis; S. Striganov; J. Tang; J. W. G. Thomason; L. Tortora; R. Tsenov; W. Winter; H. Witte; O. Yasuda; C. Y. Yoshikawa; M. Zisman

    2011-12-13T23:59:59.000Z

    The International Design Study for the Neutrino Factory (the IDS-NF) was established by the community at the ninth "International Workshop on Neutrino Factories, super-beams, and beta- beams" which was held in Okayama in August 2007. The IDS-NF mandate is to deliver the Reference Design Report (RDR) for the facility on the timescale of 2012/13. In addition, the mandate for the study [3] requires an Interim Design Report to be delivered midway through the project as a step on the way to the RDR. This document, the IDR, has two functions: it marks the point in the IDS-NF at which the emphasis turns to the engineering studies required to deliver the RDR and it documents baseline concepts for the accelerator complex, the neutrino detectors, and the instrumentation systems. The IDS-NF is, in essence, a site-independent study. Example sites, CERN, FNAL, and RAL, have been identified to allow site-specific issues to be addressed in the cost analysis that will be presented in the RDR. The choice of example sites should not be interpreted as implying a preferred choice of site for the facility.

  14. Stump Harvesting: Interim Guidance on

    E-Print Network [OSTI]

    , including biomass for fossil fuel substitution. Forest harvesting residues are increasingly being used to supply biomass for heat and power generation in the UK and attention is now turning to the potentialStump Harvesting: Interim Guidance on Site Selection and Good Practice Forest Research, April 2009

  15. Evaluation of Smart Irrigation Controllers: Initial Bench Testing Results

    E-Print Network [OSTI]

    Swanson, Charles; Fipps, Guy

    COLLEGE OF AGRICULTURE AND LIFE SCIENCES TR-354 2009 Evaluation of Smart Irrigation Controllers: Initial Bench Testing Results July 2009 By Charles Swanson, Extension Associate Guy Fipps, Professor and Extension... Agricultural Engineer Rio Grande Basin Initiative Irrigation Technology Center Texas AgriLife Extension Service Texas Water Resources Institute Technical Report July 2009 TR 354 EVALUATION OF SMART IRRIGATION CONTROLLERS...

  16. Performance and evaluation of gas engine driven rooftop air conditioning equipment at the Willow Grove (PA) Naval Air Station. Interim report, 1992 cooling season

    SciTech Connect (OSTI)

    Armstrong, P.R.; Conover, D.R.

    1993-05-01T23:59:59.000Z

    In a field evaluation conducted for the US Department of Energy (DOE) Office of Federal Energy Management Program (FEMP), the Pacific Northwest Laboratory (PNL) examined the performance of a new US energy-related technology under the FEMP Test Bed Demonstration Program. The technology was a 15-ton natural gas engine driven roof top air conditioning unit. Two such units were installed on a naval retail building to provide space conditioning to the building. Under the Test Bed Demonstration Program, private and public sector interests are focused to support the installation and evaluation of new US technologies in the federal sector. Participating in this effort under a Cooperative Research and Development Agreement (CRADA) with DOE were the American Gas Cooling Center, Philadelphia Electric Company, Thermo King Corporation, and the US Naval Air Station at Willow Grove, Pennsylvania. Equipment operating and service data as well as building interior and exterior conditions were secured for the 1992 cooling season. Based on a computer assessment of the building using standard weather data, a comparison was made with the energy and operating costs associated with the previous space conditioning system. Based on performance during the 1992 cooling season and adjusted to a normal weather year, the technology will save the site $6,000/yr in purchased energy costs. An additional $9,000 in savings due to electricity demand ratchet charge reductions will also be realized. Detailed information on the technology, the installation, and the results of the technology test are provided to illustrate the advantages to the federal sector of using this technology. A history of the CRADA development process is also reported.

  17. INTERIM RESULTS FROM A STUDY OF THE IMPACTS OF TIN(II) BASED MERCURY TREATMENT IN A SMALL STREAM ECOSYSTEM: TIMS BRANCH, SAVANNAH RIVER SITE

    SciTech Connect (OSTI)

    Looney, B.; Bryan, L.; Mathews, T.

    2012-03-30T23:59:59.000Z

    Mercury (Hg) has been identified as a 'persistent, bioaccumulative and toxic' pollutant with widespread impacts throughout North America and the world (EPA. 1997a, 1997b, 1998a, 1998b, 2000). Although most of the mercury in the environment is inorganic Hg, a small proportion of total Hg is transformed through the actions of aquatic microbes into methylmercury (MeHg). In contrast to virtually all other metals, MeHg biomagnifies or becomes increasingly concentrated as it is transferred through aquatic food chains so that the consumption of mercury contaminated fish is the primary route of this toxin to humans. For this reason, the ambient water quality criterion (AWQC) for mercury is based on a fish tissue endpoint rather than an aqueous Hg concentration, as the tissue concentration (e.g., < 0.3 {mu}g/g fillet) is considered to be a more consistent indicator of exposure and risk (EPA, 2001). Effective mercury remediation at point-source contaminated sites requires an understanding of the nature and magnitude of mercury inputs, and also knowledge of how these inputs must be controlled in order to achieve the desired reduction of mercury contamination in biota necessary for compliance with AWQC targets. One of the challenges to remediation is that mercury body burdens in fish are more closely linked to aqueous MeHg than to inorganic Hg concentrations (Sveinsdottir and Mason 2005), but MeHg production is not easily predicted or controlled. At point-source contaminated sites, mercury methylation is not only affected by the absolute mercury load, but also by the form of mercury loaded. In addition, once MeHg is formed, the hydrology, trophic structure, and water chemistry of a given system affect how it is transformed and transferred through the food chain to fish. Decreasing inorganic Hg concentrations and loading may often therefore be a more achievable remediation goal, but has led to mixed results in terms of responses in fish bioaccumulation. A number of source control measures have resulted in rapid responses in lake or reservoir fisheries (Joslin 1994, Turner and Southworth 1999; Orihel et al., 2007), but examples of similar responses in Hg-contaminated stream ecosystems are less common. Recent work suggests that stream systems may actually be more susceptible to mercury bioaccumulation than lakes, highlighting the need to better understand the ecological drivers of mercury bioaccumulation in stream-dwelling fish (Chasar et al. 2009, Ward et al. 2010). In the present study we examine the response of fish to remedial actions in Tims Branch, a point-source contaminated stream on the Department of Energy's (DOE) Savannah River Site in Aiken, South Carolina. This second order stream received inorganic mercury inputs at its headwaters from the 1950s-2000s which contaminated the water, sediments, and biota downstream. In 2007, an innovative mercury removal system using tin (II) chloride (stannous chloride, SnCl{sub 2}) was implemented at a pre-existing air stripper. Tin(II) reduces dissolved Hg (II) to Hg (0), which is removed by the air stripper. During this process, tin(II) is oxidized to tin (IV) which is expected to precipitate as colloidal tin(IV) oxides and hydroxides, particulate materials with relatively low toxicity (Hallas and Cooney, 1981, EPA 2002, ATSDR, 2005). The objectives of the present research are to provide an initial assessment of the net impacts of the tin(II) based mercury treatment on key biota and to document the distribution and fate of inorganic tin in this small stream ecosystem after the first several years of operating a full scale system. To support these objectives, we collected fish, sediment, water, invertebrates, and biofilm samples from Tims Branch to quantify the general behavior and accumulation patterns for mercury and tin in the ecosystem and to determine if the treatment process has resulted in: (1) a measurable beneficial impact on (i.e., decrease of) mercury concentration in upper trophic level fish and other biota; this is a key environmental endpoint since reducing mercury concen

  18. Connecticut Transit (CTTRANSIT) Fuel Cell Transit Bus: Preliminary Evaluation Results

    SciTech Connect (OSTI)

    Chandler, K.; Eudy, L.

    2008-10-01T23:59:59.000Z

    This report provides preliminary results from a National Renewable Energy Laboratory evaluation of a protoptye fuel cell transit bus operating at Connecticut Transit in Hartford. Included are descriptions of the planned fuel cell bus demonstration and equipment; early results and agency experience are also provided.

  19. Burn site groundwater interim measures work plan.

    SciTech Connect (OSTI)

    Witt, Jonathan L. (North Wind, Inc., Idaho Falls, ID); Hall, Kevin A. (North Wind, Inc., Idaho Falls, ID)

    2005-05-01T23:59:59.000Z

    This Work Plan identifies and outlines interim measures to address nitrate contamination in groundwater at the Burn Site, Sandia National Laboratories/New Mexico. The New Mexico Environment Department has required implementation of interim measures for nitrate-contaminated groundwater at the Burn Site. The purpose of interim measures is to prevent human or environmental exposure to nitrate-contaminated groundwater originating from the Burn Site. This Work Plan details a summary of current information about the Burn Site, interim measures activities for stabilization, and project management responsibilities to accomplish this purpose.

  20. associations interim guidelines: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    the MacAdam, Keith 20 RESEARCH REPORT 1405-5 INTERIM CONCLUSIONS, RECOMMENDATIONS, Energy Storage, Conversion and Utilization Websites Summary: RESEARCH REPORT 1405-5 INTERIM...

  1. Initial Evaluation of Smart Irrigation Controllers: Year Two (2009) Results

    E-Print Network [OSTI]

    Swanson, Charles; Fipps, Guy

    COLLEGE OF AGRICULTURE AND LIFE SCIENCES TR-364 2010 Initial Evaluation of Smart Irrigation Controllers: Year Two (2009) Results By: Charles Swanson and Guy Fipps, P.E. Department of Biological... OF SMART IRRIGATION CONTROLLERS: YEAR TWO (2009) RESULTS 1 By Charles Swanson and Guy Fipps, P.E 2 April 27, 2010 A Report Prepared for Task 2 of the Rio Grande Basin Initiative Irrigation Technology Center Texas AgriLIFE Extension Service...

  2. Realization of the German Concept for Interim Storage of Spent Nuclear Fuel - Current Situation and Prospects

    SciTech Connect (OSTI)

    Thomauske, B. R.

    2003-02-25T23:59:59.000Z

    The German government has determined a phase out of nuclear power. With respect to the management of spent fuel it was decided to terminate transports to reprocessing plants by 2005 and to set up interim storage facilities on power plant sites. This paper gives an overview of the German concept for spent fuel management focused on the new on-site interim storage concept and the applied interim storage facilities. Since the end of the year 1998, the utilities have applied for permission of on-site interim storage in 13 storage facilities and 5 storage areas; one application for the interim storage facility Stade was withdrawn due to the planned final shut down of Stade nuclear power plant in autumn 2003. In 2001 and 2002, 3 on-site storage areas and 2 on-site storage facilities for spent fuel were licensed by the Federal Office for Radiation Protection (BfS). A main task in 2002 and 2003 has been the examination of the safety and security of the planned interim storage facilities and the verification of the licensing prerequisites. In the aftermath of September 11, 2001, BfS has also examined the attack with a big passenger airplane. Up to now, these aircraft crash analyses have been performed for three on-site interim storage facilities; the fundamental results will be presented. It is the objective of BfS to conclude the licensing procedures for the applied on-site interim storage facilities in 2003. With an assumed construction period for the storage buildings of about two years, the on-site interim storage facilities could then be available in the year 2005.

  3. Results of NDE Technique Evaluation of Clad Hydrides

    SciTech Connect (OSTI)

    Dennis C. Kunerth

    2014-09-01T23:59:59.000Z

    This report fulfills the M4 milestone, M4FT-14IN0805023, Results of NDE Technique Evaluation of Clad Hydrides, under Work Package Number FT-14IN080502. During service, zirconium alloy fuel cladding will degrade via corrosion/oxidation. Hydrogen, a byproduct of the oxidation process, will be absorbed into the cladding and eventually form hydrides due to low hydrogen solubility limits. The hydride phase is detrimental to the mechanical properties of the cladding and therefore it is important to be able to detect and characterize the presence of this constituent within the cladding. Presently, hydrides are evaluated using destructive examination. If nondestructive evaluation techniques can be used to detect and characterize the hydrides, the potential exists to significantly increase test sample coverage while reducing evaluation time and cost. To demonstrate the viability this approach, an initial evaluation of eddy current and ultrasonic techniques were performed to demonstrate the basic ability to these techniques to detect hydrides or their effects on the microstructure. Conventional continuous wave eddy current techniques were applied to zirconium based cladding test samples thermally processed with hydrogen gas to promote the absorption of hydrogen and subsequent formation of hydrides. The results of the evaluation demonstrate that eddy current inspection approaches have the potential to detect both the physical damage induced by hydrides, e.g. blisters and cracking, as well as the combined effects of absorbed hydrogen and hydride precipitates on the electrical properties of the zirconium alloy. Similarly, measurements of ultrasonic wave velocities indicate changes in the elastic properties resulting from the combined effects of absorbed hydrogen and hydride precipitates as well as changes in geometry in regions of severe degradation. However, for both approaches, the signal responses intended to make the desired measurement incorporate a number of contributing parameters. These contributing factors need to be recognized and a means to control them or separate their contributions will be required to obtain the desired information.

  4. NEXT GENERATION MELTER OPTIONEERING STUDY - INTERIM REPORT

    SciTech Connect (OSTI)

    GRAY MF; CALMUS RB; RAMSEY G; LOMAX J; ALLEN H

    2010-10-19T23:59:59.000Z

    The next generation melter (NOM) development program includes a down selection process to aid in determining the recommended vitrification technology to implement into the WTP at the first melter change-out which is scheduled for 2025. This optioneering study presents a structured value engineering process to establish and assess evaluation criteria that will be incorporated into the down selection process. This process establishes an evaluation framework that will be used progressively throughout the NGM program, and as such this interim report will be updated on a regular basis. The workshop objectives were achieved. In particular: (1) Consensus was reached with stakeholders and technology providers represented at the workshop regarding the need for a decision making process and the application of the D{sub 2}0 process to NGM option evaluation. (2) A framework was established for applying the decision making process to technology development and evaluation between 2010 and 2013. (3) The criteria for the initial evaluation in 2011 were refined and agreed with stakeholders and technology providers. (4) The technology providers have the guidance required to produce data/information to support the next phase of the evaluation process. In some cases it may be necessary to reflect the data/information requirements and overall approach to the evaluation of technology options against specific criteria within updated Statements of Work for 2010-2011. Access to the WTP engineering data has been identified as being very important for option development and evaluation due to the interface issues for the NGM and surrounding plant. WRPS efforts are ongoing to establish precisely data that is required and how to resolve this Issue. It is intended to apply a similarly structured decision making process to the development and evaluation of LAW NGM options.

  5. Tritium APEX Interim Report November, 1999

    E-Print Network [OSTI]

    California at Los Angeles, University of

    Tritium APEX Interim Report November, 1999 16-1 CHAPTER 16: TRITIUM Contributors Lead Author: Dai Kai Sze #12;Tritium APEX Interim Report November, 1999 16-2 16. TRITIUM 16.1 Design constraints Tritium recovery and containment are some of the key issues associated with breeding blanket design

  6. Interim activities report

    SciTech Connect (OSTI)

    Majzlik, E.H. Jr.

    1992-05-01T23:59:59.000Z

    Several developments have occurred since the 32nd WANTO Meeting that effect the status of the Savannah River Site. A request to restart K-Reactor was issued after nearly three years of intensive engineering analysis, procedure revisions and enhanced operator training to upgrade all aspects of reactor operation. In early December 1991, the Westinghouse Savannah River Company requested permission from DOE to start the K-Reactor. In mid-December the DOE and the Defense Nuclear Facility Safety Board concurred with readiness to operate and a Federal Circuit Court of Appeals ruled against a lawsuit to delay restart until a cooling tower is completed. The K-Reactor was restarted and has been in an evaluation and testing mode. Full power operation at thirty percent of maximum capacity is projected for March 1992 after which actual tritium generation will begin. Operation will continue until October when the cooling tower will be tied into the reactor cooling system. In conjunction with the restart of K-Reactor, the P-Reactor has been placed in permanent shutdown status and the L-Reactor has been placed in warm stand-by. In another reactor related situation, the DOE will delay the decision on construction of the New Production Reactor (NPR) until 1993. The choice of reactor type and location of the NPR will be integrated into the overall programmatic decision on Reconfiguration of the Weapons Complex. Finally, construction of the Replacement Tritium Facility (RTF) was resumed in December 1991 after several months stoppage for evaluation and revision of project funding procedures.

  7. AGR-1 Data Qualification Interim Report

    SciTech Connect (OSTI)

    Machael Abbott

    2009-08-01T23:59:59.000Z

    Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR Program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor (AGR-1) experiment, the processing of these data within NDMAS, and reports the interim FY09 qualification status of the AGR-1 data to date. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category, which is assigned by the data generator, and include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent QA program. The interim qualification status of the following four data streams is reported in this document: (1) fuel fabrication data, (2) fuel irradiation data, (3) fission product monitoring system (FPMS) data, and (4) Advanced Test Reactor (ATR) operating conditions data. A final report giving the NDMAS qualification status of all AGR-1 data (including cycle 145A) is planned for February 2010.

  8. King County Metro Transit Hybrid Articulated Buses: Final Evaluation Results

    SciTech Connect (OSTI)

    Chandler, K.; Walkowicz, K.

    2006-12-01T23:59:59.000Z

    Final technical report compares and evaluates new diesel and diesel hybrid-electric articulated buses operated as part of the King County Metro Transit (KC Metro) fleet in Seattle, Washington. The evaluation lasted 12 months.

  9. BC Transit Fuel Cell Bus Project: Evaluation Results Report

    SciTech Connect (OSTI)

    Eudy, L.; Post, M.

    2014-02-01T23:59:59.000Z

    This report evaluates a fuel cell electric bus demonstration led by British Columbia Transit (BC Transit) in Whistler, Canada. BC Transit is collaborating with the California Air Resources Board and the U.S. Department of Energy's National Renewable Energy Laboratory to evaluate the buses in revenue service. This evaluation report covers two years of revenue service data on the buses from April 2011 through March 2013.

  10. Engineering report single-shell tank farms interim measures to limit infiltration through the vadose zone

    SciTech Connect (OSTI)

    HAASS, C.C.

    1999-10-14T23:59:59.000Z

    Identifies, evaluates and recommends interim measures for reducing or eliminating water sources and preferential pathways within the vadose zone of the single-shell tank farms. Features studied: surface water infiltration and leaking water lines that provide recharge moisture, and wells that could provide pathways for contaminant migration. An extensive data base, maps, recommended mitigations, and rough order of magnitude costs are included.

  11. 90-day Interim Report on Shale Gas Production - Secretary of...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    90-day Interim Report on Shale Gas Production - Secretary of Energy Advisory Board 90-day Interim Report on Shale Gas Production - Secretary of Energy Advisory Board The Shale Gas...

  12. Interim Update: Global Automotive Power Electronics R&D Relevant...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Interim Update: Global Automotive Power Electronics R&D Relevant To DOE 2015 and 2020 Cost Targets Interim Update: Global Automotive Power Electronics R&D Relevant To DOE 2015 and...

  13. Design review report FFTF interim storage cask

    SciTech Connect (OSTI)

    Scott, P.L.

    1995-01-03T23:59:59.000Z

    Final Design Review Report for the FFTF Interim Storage Cask. The Interim Storage Cask (ISC) will be used for long term above ground dry storage of FFTF irradiated fuel in Core Component Containers (CCC)s. The CCC has been designed and will house assemblies that have been sodium washed in the IEM Cell. The Solid Waste Cask (SWC) will transfer a full CCC from the IEM Cell to the RSB Cask Loading Station where the ISC will be located to receive it. Once the loaded ISC has been sealed at the RSB Cask Loading Station, it will be transferred by facility crane to the DSWC Transporter. After the ISC has been transferred to the Interim Storage Area (ISA), which is yet to be designed, a mobile crane will be used to place the ISC in its final storage location.

  14. CSUF A.S. Bylaws Interim UPS 100.001 Interim UPS 100.001 Cover Page

    E-Print Network [OSTI]

    de Lijser, Peter

    CSUF A.S. Bylaws ­ Interim UPS 100.001 Interim UPS 100.001 Cover Page Effective Date: 1-2-13 UPS 100.001 ACADEMIC SENATE BYLAWS Interim UPS 100.001 includes sections moved from UPS 100 faculty in a special election held spring 2011 (ASD 11-64). UPS 100.001 (BYLAWS) to be edited

  15. Systematic Method for Evaluating Extraction and Injection Flow Rates for 100-KR-4 and 100-HR-3 Groundwater Operable Unit Pump-and-Treat Interim Actions for Hydraulic Containment

    SciTech Connect (OSTI)

    Spiliotopoulos, Alexandros A.

    2013-03-20T23:59:59.000Z

    This document describes a systematic method to develop flow rate recommendations for Pump-and-Treat (P&T) extraction and injection wells in 100-KR-4 and 100-HR-3 Groundwater Operable Units (OU) of the Hanford Site. Flow rate recommendations are developed as part of ongoing performance monitoring and remedy optimization of the P&T interim actions to develop hydraulic contairnnent of the dissolved chromium plume in groundwater and protect the Columbia River from further discharges of groundwater from inland. This document details the methodology and data required to infer the influence of individual wells near the shoreline on hydraulic containment and river protection and develop flow rate recommendations to improve system performance and mitigate potential shortcomings of the system configuration in place.

  16. SULFURIC ACID REMOVAL PROCESS EVALUATION: LONG-TERM RESULTS

    SciTech Connect (OSTI)

    Gary M. Blythe; Richard McMillan

    2002-07-03T23:59:59.000Z

    The objective of this project is to demonstrate the use of alkaline reagents injected into the furnace of coal-fired boilers as a means of controlling sulfuric acid emissions. The project is being co-funded by the U.S. DOE National Energy Technology Laboratory, under Cooperative Agreement DE-FC26-99FT40718, along with EPRI, the American Electric Power Company (AEP), FirstEnergy Corp., the Tennessee Valley Authority, and Dravo Lime, Inc. Sulfuric acid controls are becoming of increasing interest to power generators with coal-fired units for a number of reasons. Sulfuric acid is a Toxic Release Inventory species and can cause a variety of plant operation problems such as air heater plugging and fouling, back-end corrosion, and plume opacity. These issues will likely be exacerbated with the retrofit of selective catalytic reduction (SCR) for NO{sub x} control on many coal-fired plants, as SCR catalysts are known to further oxidize a portion of the flue gas SO{sub 2} to SO{sub 3}. The project previously tested the effectiveness of furnace injection of four different calcium-and/or magnesium-based alkaline sorbents on full-scale utility boilers. These reagents were tested during four one- to two-week tests conducted on two FirstEnergy Bruce Mansfield Plant (BMP) units. One of the sorbents tested was a magnesium hydroxide byproduct slurry produced from a modified Thiosorbic{reg_sign} Lime wet flue gas desulfurization system. The other three sorbents are available commercially and include dolomite, pressure-hydrated dolomitic lime, and commercial magnesium hydroxide. The dolomite reagent was injected as a dry powder through out-of-service burners, while the other three reagents were injected as slurries through air-atomizing nozzles inserted through the front wall of the upper furnace, either across from the nose of the furnace or across from the pendant superheater tubes. After completing the four one- to two-week tests, the most promising sorbents were selected for longer-term (approximately 25-day) full-scale tests on two different units. The longer-term tests were conducted to confirm the effectiveness of the sorbents tested over extended operation on two different boilers, and to determine balance-of-plant impacts. The first long-term test was conducted on FirstEnergy's BMP, Unit 3, and the second test was conducted on AEP's Gavin Plant, Unit 1. The Gavin Plant testing provided an opportunity to evaluate the effects of sorbent injected into the furnace on SO{sub 3} formed across an operating SCR reactor. This report presents the results from those long-term tests. The tests determined the effectiveness of injecting commercially available magnesium hydroxide slurry (Gavin Plant) and byproduct magnesium hydroxide slurry (both Gavin Plant and BMP) for sulfuric acid control. The results show that injecting either slurry could achieve up to 70 to 75% overall sulfuric acid removal. At BMP, this overall removal was limited by the need to maintain acceptable electrostatic precipitator (ESP) particulate control performance. At Gavin Plant, the overall sulfuric acid removal was limited because the furnace injected sorbent was less effective at removing SO{sub 3} formed across the SCR system installed on the unit for NOX control than at removing SO{sub 3} formed in the furnace. The long-term tests also determined balance-of-plant impacts from slurry injection during the two tests. These include impacts on boiler back-end temperatures and pressure drops, SCR catalyst properties, ESP performance, removal of other flue gas species, and flue gas opacity. For the most part the balance-of-plant impacts were neutral to positive, although adverse effects on ESP performance became an issue during the BMP test.

  17. BC Transit Fuel Cell Bus Project Evaluation Results: Second Report

    SciTech Connect (OSTI)

    Eudy, L.; Post, M.

    2014-09-01T23:59:59.000Z

    Second report evaluating a fuel cell electric bus (FCEB) demonstration led by British Columbia Transit (BC Transit) in Whistler, Canada. BC Transit is collaborating with the California Air Resources Board and the U.S. Department of Energy's National Renewable Energy Laboratory to evaluate the buses in revenue service. NREL published its first report on the demonstration in February 2014. This report is an update to the previous report; it covers 3 full years of revenue service data on the buses from April 2011 through March 2014 and focuses on the final experiences and lessons learned.

  18. Evaluation of Smart Irrigation Controllers: Year 2010 Results

    E-Print Network [OSTI]

    Swanson, Charles; Fipps, Guy

    2011-12-19T23:59:59.000Z

    A smart controller testing facility was established by the Irrigation Technology Center at Texas A&M University in College Station in 2008 in order to evaluate their performance from an “enduser” point of view. The “end-user” is considered...

  19. Interim Process Agreement Proposal June 3, 2003

    E-Print Network [OSTI]

    Interim Process Agreement Proposal June 3, 2003 Overview For the near term, the Columbia Basin Fish) return to the planning and budget management process patterned after the 1996-2001 Bonneville Power implementation of the Fish and Wildlife Program (Program) through a quarterly review process, 3) establishing

  20. New York City Transit Hybrid and CNG Transit Buses: Final Evaluation Results

    SciTech Connect (OSTI)

    Barnitt, R.; Chandler, K.

    2006-11-01T23:59:59.000Z

    This report describes the evaluation results for new Orion VII buses at NYCT with CNG propulsion and new hybrid propulsion.

  1. High Temperature Materials Interim Data Qualification Report

    SciTech Connect (OSTI)

    Nancy Lybeck

    2010-08-01T23:59:59.000Z

    ABSTRACT Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim FY2010 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under NQA-1 guidelines, and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from two test series within the High Temperature Materials data stream have been entered into the NDMAS vault: 1. Tensile Tests for Sm (i.e., Allowable Stress) Confirmatory Testing – 1,403,994 records have been inserted into the NDMAS database. Capture testing is in process. 2. Creep-Fatigue Testing to Support Determination of Creep-Fatigue Interaction Diagram – 918,854 records have been processed and inserted into the NDMAS database. Capture testing is in process.

  2. Yosemite Waters Vehicle Evaluation Report: Final Results (Brochure)

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuels Data Center Home PageStation LocationsGeneseeValleyPerformance of® ®Results

  3. SULFURIC ACID REMOVAL PROCESS EVALUATION: SHORT-TERM RESULTS

    SciTech Connect (OSTI)

    Gary M. Blythe; Richard McMillan

    2002-03-04T23:59:59.000Z

    The objective of this project is to demonstrate the use of alkaline reagents injected into the furnace of coal-fired boilers as a means of controlling sulfuric acid emissions. Sulfuric acid controls are becoming of increasing interest to utilities with coal-fired units for a number of reasons. Sulfuric acid is a Toxic Release Inventory species, a precursor to acid aerosol/condensable emissions, and can cause a variety of plant operation problems such as air heater plugging and fouling, back-end corrosion, and plume opacity. These issues will likely be exacerbated with the retrofit of SCR for NOX control on some coal-fired plants, as SCR catalysts are known to further oxidize a portion of the flue gas SO{sub 2} to SO{sub 3}. The project is testing the effectiveness of furnace injection of four different calcium- and/or magnesium-based alkaline sorbents on full-scale utility boilers. These reagents have been tested during four one- to two-week tests conducted on two FirstEnergy Bruce Mansfield Plant units. One of the sorbents tested was a magnesium hydroxide slurry produced from a wet flue gas desulfurization system waste stream, from a system that employs a Thiosorbic{reg_sign} Lime scrubbing process. The other three sorbents are available commercially and include dolomite, pressure-hydrated dolomitic lime, and commercial magnesium hydroxide. The dolomite reagent was injected as a dry powder through out-of-service burners, while the other three reagents were injected as slurries through air-atomizing nozzles into the front wall of upper furnace, either across from the nose of the furnace or across from the pendant superheater tubes. After completing the four one- to two-week tests, the most promising sorbents were selected for longer-term (approximately 25-day) full-scale tests. The longer-term tests are being conducted to confirm the effectiveness of the sorbents tested over extended operation and to determine balance-of-plant impacts. This reports presents the results of the short-term tests; the long-term test results will be reported in a later document. The short-term test results showed that three of the four reagents tested, dolomite powder, commercial magnesium hydroxide slurry, and byproduct magnesium hydroxide slurry, were able to achieve 90% or greater removal of sulfuric acid compared to baseline levels. The molar ratio of alkali to flue gas sulfuric acid content (under baseline conditions) required to achieve 90% sulfuric acid removal was lowest for the byproduct magnesium hydroxide slurry. However, this result may be confounded because this was the only one of the three slurries tested with injection near the top of the furnace across from the pendant superheater platens. Injection at the higher level was demonstrated to be advantageous for this reagent over injection lower in the furnace, where the other slurries were tested.

  4. SULFURIC ACID REMOVAL PROCESS EVALUATION: SHORT-TERM RESULTS

    SciTech Connect (OSTI)

    Gary M. Blythe; Richard McMillan

    2002-02-04T23:59:59.000Z

    The objective of this project is to demonstrate the use of alkaline reagents injected into the furnace of coal-fired boilers as a means of controlling sulfuric acid emissions. Sulfuric acid controls are becoming of increasing interest to utilities with coal-fired units for a number of reasons. Sulfuric acid is a Toxic Release Inventory species, a precursor to acid aerosol/condensable emissions, and can cause a variety of plant operation problems such as air heater plugging and fouling, back-end corrosion, and plume opacity. These issues will likely be exacerbated with the retrofit of SCR for NO{sub x} control on some coal-fired plants, as SCR catalysts are known to further oxidize a portion of the flue gas SO{sub 2} to SO{sub 3}. The project is testing the effectiveness of furnace injection of four different calcium- and/or magnesium-based alkaline sorbents on full-scale utility boilers. These reagents have been tested during four one- to two-week tests conducted on two First Energy Bruce Mansfield Plant units. One of the sorbents tested was a magnesium hydroxide slurry produced from a wet flue gas desulfurization system waste stream, from a system that employs a Thiosorbic{reg_sign} Lime scrubbing process. The other three sorbents are available commercially and include dolomite, pressure-hydrated dolomitic lime, and commercial magnesium hydroxide. The dolomite reagent was injected as a dry powder through out-of-service burners, while the other three reagents were injected as slurries through air-atomizing nozzles into the front wall of upper furnace, either across from the nose of the furnace or across from the pendant superheater tubes. After completing the four one- to two-week tests, the most promising sorbents were selected for longer-term (approximately 25-day) full-scale tests. The longer-term tests are being conducted to confirm the effectiveness of the sorbents tested over extended operation and to determine balance-of-plant impacts. This reports presents the results of the short-term tests; the long-term test results will be reported in a later document. The short-term test results showed that three of the four reagents tested, dolomite powder, commercial magnesium hydroxide slurry, and byproduct magnesium hydroxide slurry, were able to achieve 90% or greater removal of sulfuric acid compared to baseline levels. The molar ratio of alkali to flue gas sulfuric acid content (under baseline conditions) required to achieve 90% sulfuric acid removal was lowest for the byproduct magnesium hydroxide slurry. However, this result may be confounded because this was the only one of the three slurries tested with injection near the top of the furnace across from the pendant superheater platens. Injection at the higher level was demonstrated to be advantageous for this reagent over injection lower in the furnace, where the other slurries were tested.

  5. 222-S Laboratory interim safety basis

    SciTech Connect (OSTI)

    WEAVER, L.L.

    2001-09-10T23:59:59.000Z

    The purpose of this document is to establish the Interim Safety Basis (ISB) for the 222-S Laboratory. An ISB is a documented safety basis that provides the justification for the continued operation of the facility until an upgraded documented safety analysis (DSA) is prepared in compliance with 10CFR 830, Subpart B. The 222-S Laboratory ISB is based on revised facility and process descriptions and revised accident analyses that reflect current conditions.

  6. Interim Vice President/CFO Administration and Finance

    E-Print Network [OSTI]

    de Lijser, Peter

    Interim Vice President/CFO Administration and Finance Stephen G. Garcia Associate Vice President Project Management Tinnah Medina Director Facilities Operations Willem van der Pol Manager Finance & Admin

  7. Comments of NRDC on Department of Energy Interim Final Rule:...

    Broader source: Energy.gov (indexed) [DOE]

    NRDC's comments on Interim Final Rule: Energy Conservation for New Federal Commercial and Multi-Family High-Rise Residential Buildings and New Federal Low-Rise Residential...

  8. SunLine Transit Agency, Hydrogen Powered Transit Buses: Preliminary Evaluation Results

    SciTech Connect (OSTI)

    Chandler, K.; Eudy, L.

    2007-02-01T23:59:59.000Z

    This paper provides preliminary results from an evaluation by DOE's National Renewable Energy Laboratory of hydrogen-powered transit buses at SunLine Transit Agency.

  9. Database and Interim Glass Property Models for Hanford HLW and LAW Glasses

    SciTech Connect (OSTI)

    Vienna, John D. (BATTELLE (PACIFIC NW LAB)); Kim, Dong-Sang (BATTELLE (PACIFIC NW LAB)); Hrma, Pavel R. (BATTELLE (PACIFIC NW LAB))

    2002-09-27T23:59:59.000Z

    This report discusses a methodology for increasing the efficiency and decreasing the cost of vitrifying nuclear waste by optimizing waste-glass formulation. This methodology involves collecting and generating a property-composition database (for glass properties that determine waste-glass processability and acceptability) and relating these properties to glass composition via property-composition models. The report explains how the property-composition models are developed, fitted to data and evaluated, validated using additional data, used for glass-formulation optimization, and continuously updated in response to changes in waste-composition estimates and processing technologies. Further, the report describes a waste-glass property-composition database compiled from literature sources and presents the results from a critical evaluation and screening of the data for applicability to Hanford waste glasses. Finally, the report provides interim property-composition models for melt viscosity, liquidus temperature (with spinel and zircon primary crystalline phases), and Product Consistency Test normalized releases of B, Na, and Li. Models were fitted to a subset of the database deemed most relevant for the anticipated Hanford waste-glass composition region.

  10. Materials Considerations and Data Base APEX Interim Report November, 1999

    E-Print Network [OSTI]

    California at Los Angeles, University of

    Materials Considerations and Data Base APEX Interim Report November, 1999 13-1 CHAPTER 13: MATERIALS CONSIDERATIONS AND DATA BASE Contributors Lead Author: S.J. Zinkle S. Majumdar N.M. Ghoniem S. Sharafat. #12;Materials Considerations and Data Base APEX Interim Report November, 1999 13-2 13. MATERIALS

  11. North American Carbon Program (NACP) Regional Interim Synthesis: Terrestrial Biospheric Model Intercomparision

    SciTech Connect (OSTI)

    Huntzinger, Deborah [University of Michigan; Post, Wilfred M [ORNL; Michalak, Anna [University of Michigan; West, Tristram O. [Joint Global Change Research Institute, PNNL; Jacobson, Andrew [NOAA ESRL and CIRES; Baker, Ian [Colorado State University, Fort Collins; Chen, Jing M. [University of Toronto; Davis, Kenneth [Pennsylvania State University; Hayes, Daniel J [ORNL; Hoffman, Forrest M [ORNL; Jain, Atul [University of Illinois, Urbana-Champaign; Liu, Shuguang [United States Geological Survey, Center for Earth Resources Observation and Science (USGS EROS); Mcguire, David [University of Alaska; Neilson, Ronald [Oregon State University, Corvallis; Poulter, Ben [Potsdam Institute for Climate Impact Research, Potsdam, Germany; Tian, Hanqin [Auburn University, Auburn, Alabama; Thornton, Peter E [ORNL; Tomelleri, Enrico [Max Planck Institute for Biogeochemistry; Viovy, Nicolas [National Center for Scientific Research, Gif-sur-Yvette, France; Xiao, Jingfeng [Purdue University; Cook, Robert B [ORNL

    2012-01-01T23:59:59.000Z

    Understanding of carbon exchange between terrestrial ecosystems and the atmosphere can be improved through direct observations and experiments, as well as through modeling activities. Terrestrial biosphere models (TBMs) have become an integral tool for extrapolating local observations and understanding to much larger terrestrial regions. Although models vary in their specific goals and approaches, their central role within carbon cycle science is to provide a better understanding of the mechanisms currently controlling carbon exchange. Recently, the North American Carbon Program (NACP) organized several interim-synthesis activities to evaluate and inter-compare models and observations at local to continental scales for the years 2000-2005. Here, we compare the results from the TBMs collected as part of the regional and continental interim-synthesis (RCIS) activities. The primary objective of this work is to synthesize and compare the 19 participating TBMs to assess current understanding of the terrestrial carbon cycle in North America. Thus, the RCIS focuses on model simulations available from analyses that have been completed by ongoing NACP projects and other recently published studies. The TBM flux estimates are compared and evaluated over different spatial (1{sup o} x 1{sup o} and spatially aggregated to different regions) and temporal (monthly and annually) scales. The range in model estimates of net ecosystem productivity (NEP) for North America is much narrower than estimates of productivity or respiration, with estimates of NEP varying between -0.7 and 2.2 PgC yr{sup -1}, while gross primary productivity and heterotrophic respiration vary between 12.2 and 32.9 PgC yr{sup -1} and 5.6 and 13.2 PgC yr{sup -1}, respectively. The range in estimates from the models appears to be driven by a combination of factors, including the representation of photosynthesis, the source and of environmental driver data and the temporal variability of those data, as well as whether nutrient limitation is considered in soil carbon decomposition. The disagreement in current estimates of carbon flux across North America, including whether North America is a net biospheric carbon source or sink, highlights the need for further analysis through the use of model runs following a common simulation protocol, in order to isolate the influences of model formulation, structure, and assumptions on flux estimates.

  12. Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components

    SciTech Connect (OSTI)

    Ware, A.G.; Morton, D.K.; Nitzel, M.E. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

    1995-03-01T23:59:59.000Z

    Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the components in the reactor coolant pressure boundary of LWRs were performed. The sample consists of components from facilities designed by each of the four U.S. nuclear steam supply system vendors. For each facility, six locations were studied, including two locations on the reactor pressure vessel. In addition, there are older vintage plants where components of the reactor coolant pressure boundary were designed to codes that did not require an explicit fatigue analysis of the components. In order to assess the fatigue resistance of the older vintage plants, an evaluation was also conducted on selected components of three of these plants. This report discusses the insights gained from the application of the interim fatigue curves to components of seven operating nuclear power plants.

  13. Flatiron AGC Interim Controller. Volume 4

    SciTech Connect (OSTI)

    Gish, W.B.; Whittemore, T.R.; Lennon, C.A. Jr.; Stitt, S.C.

    1984-03-01T23:59:59.000Z

    The Flatiron Interim Automatic Generation Controller has been placed in service for the Lower Missouri Western Area Power Administration Control Area. This controller meets the requirements of the National Electric Reliability Council and controls the energy generation and transfers in northern Colorado, Wyoming, western Nebraska, western South Dakota, and southern Montana. The master controller is based on five interacting microprocessors with unique communication structures and data storage methods. The design, construction, maintenance, and operation details for the master station and the remote stations, including flow charts, schematics, and wiring diagrams, are in this four-volume series.

  14. Interim Solution 2.0 Files

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes | National Nuclear SecurityIntellectualInterconnectingInterim

  15. ST. LOUIS AIRPORT/ HAZELWOOD INTERIM

    E-Print Network [OSTI]

    and remote disposal of contaminated soils on various private properties, under removal action authority the Airport resulted in the contamination of numerous private and municipally owned properties. The St. Louis radioactively-contaminated sites are part of the Formerly Utilized Sites Remedial Action Program (FUSRAP

  16. Performance testing of aged hydrogen getters against criteria for interim safe storage of plutonium bearing materials.

    SciTech Connect (OSTI)

    Shepodd, Timothy J.; Nissen, April; Buffleben, George M.

    2006-01-01T23:59:59.000Z

    Hydrogen getters were tested for use in storage of plutonium-bearing materials in accordance with DOE's Criteria for Interim Safe Storage of Plutonium Bearing Materials. The hydrogen getter HITOP was aged for 3 months at 70 C and tested under both recombination and hydrogenation conditions at 20 and 70 C; partially saturated and irradiated aged getter samples were also tested. The recombination reaction was found to be very fast and well above the required rate of 45 std. cc H2h. The gettering reaction, which is planned as the backup reaction in this deployment, is slower and may not meet the requirements alone. Pressure drop measurements and {sup 1}H NMR analyses support these conclusions. Although the experimental conditions do not exactly replicate the deployment conditions, the results of our conservative experiments are clear: the aged getter shows sufficient reactivity to maintain hydrogen concentrations below the flammability limit, between the minimum and maximum deployment temperatures, for three months. The flammability risk is further reduced by the removal of oxygen through the recombination reaction. Neither radiation exposure nor thermal aging sufficiently degrades the getter to be a concern. Future testing to evaluate performance for longer aging periods is in progress.

  17. An Experimental Evaluation of Duct-Mounted Relative Humidity Sensors: Part 2 – Accuracy Results 

    E-Print Network [OSTI]

    Joshi, S.N.; Pate, M.B.; Nelson, R.M; House, J.H.; Klaasen, C.J.

    2005-01-01T23:59:59.000Z

    Reproduced with permission of the copyright owner. Further reproduction prohibited without permission. An Experimental Evaluation of Duct-Mounted Relative Humidity Sensors: Part 2-Accuracy Results Joshi, Shailesh N;House, John M;Pate, Michael B...

  18. Operable Unit 3: Proposed Plan/Environmental Assessment for interim remedial action

    SciTech Connect (OSTI)

    Not Available

    1993-12-01T23:59:59.000Z

    This document presents a Proposed Plan and an Environmental Assessment for an interim remedial action to be undertaken by the US Department of Energy (DOE) within Operable Unit 3 (OU3) at the Fernald Environmental Management Project (FEMP). This proposed plan provides site background information, describes the remedial alternatives being considered, presents a comparative evaluation of the alternatives and a rationnale for the identification of DOE`s preferred alternative, evaluates the potential environmental and public health effects associated with the alternatives, and outlines the public`s role in helping DOE and the EPA to make the final decision on a remedy.

  19. System design study to reduce capital and operating costs and bench-scale testing of a circulating-bed AFB advanced concept. Phase 1, Task 2: interim report on Task 1 results

    SciTech Connect (OSTI)

    Fraley, L.D.; Hsiao, K.H.; Lee, M.M.; Lin, Y.Y.; Sadhukhan, P.; Schlossman, M.; Schreiner, W.C.; Solbakken, A.

    1985-08-01T23:59:59.000Z

    The M.W. Kellogg Company has had under consideration for many years a combustor design involving a circulating fluid bed of ash, coal, lime/limestone sorbent, and calcium sulfate. In a previous study for the Department of Energy, M.W. Kellogg performed a design analysis for an atmospheric fluidized-bed combustor whose performance should significantly exceed conventional FBC operation performance, i.e., the Kellogg CFBC. The analysis conclusively showed that the Kellogg CFBC met or exceeded performance criteria for advanced atmospheric FBC's. This is superior to those FBC's currently in the market place. The objective of the study presented here was to reduce capital and operating costs of the Kellogg CFBC, configured into an industrial boiler system of 150,000 pounds per hour steaming capacity. This report presents the design optimization, detailed designs, and cost estimates required to compare CFBC with conventional AFB. The results show the Kellogg CFBC to be a very economical concept. Technically, the Kellogg CFBC can meet or exceed all of the design criteria established for an advanced AFBC. Its compact design resembles an FCC unit in structure and operation. By staged combustion, NO/sub x/ emissions are controlled by the reducing atmosphere and sulfur absorption enhanced in the improved kinetics of the H/sub 2/S-CaO reaction. The unique combustor/riser design keeps the boiler tubes from exposure to corrosive combustion gases, solving the erosion and corrosion problems existing in conventional bubbling-bed AFB. 7 refs., 28 figs., 17 tabs.

  20. PROJECT W-551 INTERIM PRETREATMENT SYSTEM PRECONCEPTUAL CANDIDATE TECHNOLOGY DESCRIPTIONS

    SciTech Connect (OSTI)

    MAY TH

    2008-08-12T23:59:59.000Z

    The Office of River Protection (ORP) has authorized a study to recommend and select options for interim pretreatment of tank waste and support Waste Treatment Plant (WTP) low activity waste (LAW) operations prior to startup of all the WTP facilities. The Interim Pretreatment System (IPS) is to be a moderately sized system which separates entrained solids and 137Cs from tank waste for an interim time period while WTP high level waste vitrification and pretreatment facilities are completed. This study's objective is to prepare pre-conceptual technology descriptions that expand the technical detail for selected solid and cesium separation technologies. This revision includes information on additional feed tanks.

  1. TANK FARM INTERIM SURFACE BARRIER MATERIALS AND RUNOFF ALTERNATIVES STUDY

    SciTech Connect (OSTI)

    HOLM MJ

    2009-06-25T23:59:59.000Z

    This report identifies candidate materials and concepts for interim surface barriers in the single-shell tank farms. An analysis of these materials for application to the TY tank farm is also provided.

  2. Public Interest Energy Research (PIER) Program INTERIM REPORT

    E-Print Network [OSTI]

    Public Interest Energy Research (PIER) Program INTERIM REPORT SOLAR REFLECTANCES OF ROOFS: · Buildings EndUse Energy Efficiency · Energy Innovations Small Grants · EnergyRelated Environmental/Agricultural/Water EndUse Energy Efficiency · Renewable Energy Technologies · Transportation Solar Reflectances

  3. Fire Hazards Analysis for the 200 Area Interim Storage Area

    SciTech Connect (OSTI)

    JOHNSON, D.M.

    2000-01-06T23:59:59.000Z

    This documents the Fire Hazards Analysis (FHA) for the 200 Area Interim Storage Area. The Interim Storage Cask, Rad-Vault, and NAC-1 Cask are analyzed for fire hazards and the 200 Area Interim Storage Area is assessed according to HNF-PRO-350 and the objectives of DOE Order 5480 7A. This FHA addresses the potential fire hazards associated with the Interim Storage Area (ISA) facility in accordance with the requirements of DOE Order 5480 7A. It is intended to assess the risk from fire to ensure there are no undue fire hazards to site personnel and the public and to ensure property damage potential from fire is within acceptable limits. This FHA will be in the form of a graded approach commensurate with the complexity of the structure or area and the associated fire hazards.

  4. Electromagnetically Restrained Lithium Blanket APEX Interim Report November, 1999

    E-Print Network [OSTI]

    California at Los Angeles, University of

    to avoid corrosion or fire. Lithium's high electrical conductivity may possibly permit efficient, compactElectromagnetically Restrained Lithium Blanket APEX Interim Report November, 1999 6-1 CHAPTER 6: ELECTROMAGNETICALLY RESTRAINED LITHIUM BLANKET Contributors Robert Woolley #12;Electromagnetically Restrained Lithium

  5. area interim storage: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Spot Height Northern British Columbia, University of 3 In Situ Bioremediation Interim Remedial Action Report, Test Area North, Operable Unit 1-07B CiteSeer Summary: This...

  6. K basins interim remedial action health and safety plan

    SciTech Connect (OSTI)

    DAY, P.T.

    1999-09-14T23:59:59.000Z

    The K Basins Interim Remedial Action Health and Safety Plan addresses the requirements of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as they apply to the CERCLA work that will take place at the K East and K West Basins. The provisions of this plan become effective on the date the US Environmental Protection Agency issues the Record of Decision for the K Basins Interim Remedial Action, currently planned in late August 1999.

  7. SAHP Faculty Assembly Resolution 04-01 Commendation of Performance of Jimmy Cairo, Ph.D. as Interim Dean

    E-Print Network [OSTI]

    SAHP Faculty Assembly Resolution 04-01 Commendation of Performance of Jimmy Cairo, Ph.D. as Interim the performance of Jimmy Cairo, Ph.D. while he has served as Interim Dean for the SAHP. While serving as Interim

  8. Interim measure work plan/design for Agra, Kansas.

    SciTech Connect (OSTI)

    LaFreniere, L. M.; Environmental Science Division

    2008-11-18T23:59:59.000Z

    This Interim Measure Work Plan/Design (IMWP/D) is supplemental to the Argonne document Interim Measure Conceptual Design for Remediation of Source Area Contamination at Agra, Kansas. The IMWP/D includes information required by Kansas Department of Health and Environment (KDHE) Policy BER-RS-029, Policy and Scope of Work for Interim Measures. Specific to Policy BER-RS-029 is the requirement for several documents that will ensure that an adequate amount and type of data are collected for implementation of the IMWP/D and that data quality and safe conditions are prevailed. Such information is included in the IMWP/D as follows: Appendix A: Data Acquisition Plan--Design Testing Requirements; Appendix B: Basis of Design; Appendix C: Permits; Appendix D: Quality Assurance Project Plan; Appendix E: Health and Safety Plan; and Appendix F: Operations, Maintenance, and Monitoring Schedule. The proposed remedial technology for this project is the installation of five large-diameter boreholes (LDBs) in a source area that has been identified on the property formerly used for grain storage by the Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA). The goal of the LDB technology is the remediation of the source area by removal of mass quantities of contaminated soil from the vadose zone and treatment of any remaining contaminated soils that are adjacent to the source area to achieve a carbon tetrachloride concentration below 200 {micro}g/kg. Secondary to the soil remediation is the remediation of groundwater at and adjacent to the source areas. The LDB technology serves the following purposes: (1) The physical removal of contaminated soil from the identified source area. (2) Replacement of less permeable native materials (silty clay, clayey silt, and silty sand) with more permeable materials to facilitate the capture of volatilized contaminants in the vertical borehole. (3) Removal of contaminants volatilized by air sparging (AS) and extracted from the vadose zone by soil vapor extraction (SVE). (4) Volatilization of contaminants from portions of the affected aquifer that can be accessed from the former CCC/USDA property. The primary objective of the proposed removal action is removal of mass quantities of carbon tetrachloride from the vadose zone and treatment of any remaining contaminated soils that are adjacent to the source area, to achieve a carbon tetrachloride concentration below 200 {micro}g/kg. This objective will be the basis for evaluating system performance. The scope of action outlined in the IMWP/D is limited to the five treatment zones defined by the LDB/SVE/AS locations. Surrounding soils and groundwater will benefit; however, remedial benefits to groundwater will be limited to the area of influence associated with the five treatment zones. While treatment should be aggressive in the vicinity of the LDB locations, the heterogeneity, clay content, and low permeability of the soils will place inherent limits on the area of influence.

  9. Database and Interim Glass Property Models for Hanford HLW Glasses

    SciTech Connect (OSTI)

    Hrma, Pavel R.; Piepel, Gregory F.; Vienna, John D.; Cooley, Scott K.; Kim, Dong-Sang; Russell, Renee L.

    2001-07-24T23:59:59.000Z

    The purpose of this report is to provide a methodology for an increase in the efficiency and a decrease in the cost of vitrifying high-level waste (HLW) by optimizing HLW glass formulation. This methodology consists in collecting and generating a database of glass properties that determine HLW glass processability and acceptability and relating these properties to glass composition. The report explains how the property-composition models are developed, fitted to data, used for glass formulation optimization, and continuously updated in response to changes in HLW composition estimates and changes in glass processing technology. Further, the report reviews the glass property-composition literature data and presents their preliminary critical evaluation and screening. Finally the report provides interim property-composition models for melt viscosity, for liquidus temperature (with spinel and zircon primary crystalline phases), and for the product consistency test normalized releases of B, Na, and Li. Models were fitted to a subset of the screened database deemed most relevant for the current HLW composition region.

  10. Interim performance criteria for photovoltaic energy systems. [Glossary included

    SciTech Connect (OSTI)

    DeBlasio, R.; Forman, S.; Hogan, S.; Nuss, G.; Post, H.; Ross, R.; Schafft, H.

    1980-12-01T23:59:59.000Z

    This document is a response to the Photovoltaic Research, Development, and Demonstration Act of 1978 (P.L. 95-590) which required the generation of performance criteria for photovoltaic energy systems. Since the document is evolutionary and will be updated, the term interim is used. More than 50 experts in the photovoltaic field have contributed in the writing and review of the 179 performance criteria listed in this document. The performance criteria address characteristics of present-day photovoltaic systems that are of interest to manufacturers, government agencies, purchasers, and all others interested in various aspects of photovoltaic system performance and safety. The performance criteria apply to the system as a whole and to its possible subsystems: array, power conditioning, monitor and control, storage, cabling, and power distribution. They are further categorized according to the following performance attributes: electrical, thermal, mechanical/structural, safety, durability/reliability, installation/operation/maintenance, and building/site. Each criterion contains a statement of expected performance (nonprescriptive), a method of evaluation, and a commentary with further information or justification. Over 50 references for background information are also given. A glossary with definitions relevant to photovoltaic systems and a section on test methods are presented in the appendices. Twenty test methods are included to measure performance characteristics of the subsystem elements. These test methods and other parts of the document will be expanded or revised as future experience and needs dictate.

  11. Evaluation of Advanced Wind Power Forecasting Models Results of the Anemos Project

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 Evaluation of Advanced Wind Power Forecasting Models ­ Results of the Anemos Project I. Martí1.kariniotakis@ensmp.fr Abstract An outstanding question posed today by end-users like power system operators, wind power producers or traders is what performance can be expected by state-of-the-art wind power prediction models. This paper

  12. Lamar Low-Level Jet Program Interim Report

    SciTech Connect (OSTI)

    Kelley, N.; Shirazi, M.; Jager, D.; Wilde, S.; Adams, J.; Buhl, M.; Sullivan, P.; Patton, E.

    2004-01-01T23:59:59.000Z

    This interim report presents the results to date from the Lamar Low-Level Jet Program (LLLJP) that has been established as joint effort among the U.S. Department of Energy (DOE), the National Wind Technology Center (NWTC) of the National Renewable Energy Laboratory (NREL), and General Electric Wind Energy (GE Wind). The purpose of this project is to develop an understanding of the influence of nocturnal low-level jet streams on the inflow turbulence environment and the documenting of any potential operating impacts on current large wind turbines and the Low Wind Speed Turbine (LWST) designs of the future. A year's record of detailed nocturnal turbulence measurements has been collected from NREL instrumentation installed on the GE Wind 120-m tower in southeastern Colorado and supplemented with mean wind profile data collected using an acoustic wind profiler or SODAR (Sound Detection and Ranging). The analyses of measurements taken as part of a previous program conducted at the NWTC have been used to aid in the interpretation of the results of representative case studies of data collected from the GE Wind tower.

  13. Interim Draft for Internal NASA Use Only NASA SPACE FLIGHT PROGRAM AND

    E-Print Network [OSTI]

    Christian, Eric

    ............................................................................40 2.6 Use of Earned Value ManagementInterim Draft for Internal NASA Use Only INTERIM NASA SPACE FLIGHT PROGRAM AND PROJECT MANAGEMENT............................................................................................................................2 1.4 Overview of Management Process

  14. Innovative nuclear thermal propulsion technology evaluation: Results of the NASA/DOE Task Team study

    SciTech Connect (OSTI)

    Howe, S. (Los Alamos National Lab., NM (United States)); Borowski, S. (National Aeronautics and Space Administration, Cleveland, OH (United States). Lewis Research Center); Motloch, C. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Helms, I. (Nuclear Utility Services, Damascus, MD (United States)); Diaz, N.; Anghaie, S. (Florida Univ., Gainesville, FL (United States)); Latham, T. (United

    1991-01-01T23:59:59.000Z

    In response to findings from two NASA/DOE nuclear propulsion workshops held in the summer of 1990, six task teams were formed to continue evaluation of various nuclear propulsion concepts. The Task Team on Nuclear Thermal Propulsion (NTP) created the Innovative Concepts Subpanel to evaluate thermal propulsion concepts which did not utilize solid fuel. The Subpanel endeavored to evaluate each of the concepts on a level technological playing field,'' and to identify critical technologies, issues, and early proof-of-concept experiments. The concepts included the liquid core fission, the gas core fission, the fission foil reactors, explosively driven systems, fusion, and antimatter. The results of the studies by the panel will be provided. 13 refs., 6 figs., 2 tabs.

  15. Usefulness of Interim FDG-PET After Induction Chemotherapy in Patients With Locally Advanced Squamous Cell Carcinoma of the Head and Neck Receiving Sequential Induction Chemotherapy Followed by Concurrent Chemoradiotherapy

    SciTech Connect (OSTI)

    Yoon, Dok Hyun; Cho, Yoojin [Department of Oncology, Asan Medical Center, University of Ulsan College of Medicine, Seoul (Korea, Republic of); Kim, Sang Yoon; Nam, Soon Yuhl; Choi, Seung-Ho; Roh, Jong-Lyel [Department of Otolaryngology, Asan Medical Center, University of Ulsan College of Medicine, Seoul (Korea, Republic of); Lee, Sang-wook; Song, Si Yeol [Department of Radiation Oncology, Asan Medical Center, University of Ulsan College of Medicine, Seoul (Korea, Republic of); Lee, Jeong Hyun [Department of Radiology, Asan Medical Center, University of Ulsan College of Medicine, Seoul (Korea, Republic of); Kim, Jae Seung [Department of Nuclear Medicine, Asan Medical Center, University of Ulsan College of Medicine, Seoul (Korea, Republic of); Cho, Kyung-Ja [Department of Pathology, Asan Medical Center, University of Ulsan College of Medicine, Seoul (Korea, Republic of); Kim, Sung-Bae, E-mail: sbkim3@amc.seoul.kr [Department of Oncology, Asan Medical Center, University of Ulsan College of Medicine, Seoul (Korea, Republic of)

    2011-09-01T23:59:59.000Z

    Purpose: Induction chemotherapy (ICT) has been used to select patients for organ preservation and determine subsequent treatments in patients with locally advanced squamous cell carcinoma of the head and neck (LASCCHN). Still, the clinical outcomes of LASCCHN patients who showed response to ICT are heterogeneous. We evaluated the efficacy of interim 18-fluoro-2-deoxy-glucose positron emission tomography (FDG-PET) after ICT in this specific subgroup of LASCCHN patients who achieved partial response (PR) after ICT to predict clinical outcomes after concurrent chemoradiotherapy (CCRT). Methods and Materials: Twenty-one patients with LASCCHN who showed PR to ICT by Response Evaluation Criteria In Solid Tumors before definitive CCRT were chosen in this retrospective analysis. FDG-PET was performed before and 2-4 weeks after ICT to assess the extent of disease at baseline and the metabolic response to ICT, respectively. We examined the correlation of the metabolic response by the percentage decrease of maximum standardized uptake value (SUVmax) on the primary tumor or lymph node after ICT or a specific threshold of SUVmax on interim FDG-PET with clinical outcomes including complete response (CR) rate to CCRT, progression-free survival (PFS), and overall survival (OS). Results: A SUVmax of 4.8 on interim FDG-PET could predict clinical CR after CCRT (100% vs. 20%, p = 0.001), PFS (median, not reached vs. 8.5 mo, p < 0.001), and OS (median, not reached vs. 12.0 months, p = 0.001) with a median follow-up of 20.3 months in surviving patients. A 65% decrease in SUVmax after ICT from baseline also could predict clinical CR after CCRT (100% vs. 33.3%, p = 0.003), PFS (median, not reached vs. 8.9 months, p < 0.001) and OS (median, not reached vs. 24.4 months, p = 0.001) of the patients. Conclusion: These data suggest that interim FDG-PET after ICT might be a useful determinant to predict clinical outcomes in patients with LASCCHN receiving sequential ICT followed by CCRT.

  16. Results of the Evaluation Study DeAL Decentralized Facade Integrated Ventilation Systems

    E-Print Network [OSTI]

    Mahler, B.; Himmler, R.

    Evaluation Results from 12 Buildings in Operation ESL-IC-08-10-38a Proceedings of the Eighth International Conference for Enhanced Building Operations, Berlin, Germany, October 20-22, 2008 2... ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? ? What are Facade Integrated Ventilation Systems? ESL-IC-08-10-38a Proceedings of the Eighth International Conference for Enhanced Building Operations, Berlin, Germany, October 20-22, 2008 3...

  17. Plutonium uranium extraction (PUREX) end state basis for interim operation (BIO) for surveillance and maintenance

    SciTech Connect (OSTI)

    DODD, E.N.

    1999-05-12T23:59:59.000Z

    This Basis for Interim Operation (BIO) was developed for the PUREX end state condition following completion of the deactivation project. The deactivation project has removed or stabilized the hazardous materials within the facility structure and equipment to reduce the hazards posed by the facility during the surveillance and maintenance (S and M) period, and to reduce the costs associated with the S and M. This document serves as the authorization basis for the PUREX facility, excluding the storage tunnels, railroad cut, and associated tracks, for the deactivated end state condition during the S and M period. The storage tunnels, and associated systems and areas, are addressed in WHC-SD-HS-SAR-001, Rev. 1, PUREX Final Safety Analysis Report. During S and M, the mission of the facility is to maintain the conditions and equipment in a manner that ensures the safety of the workers, environment, and the public. The S and M phase will continue until the final decontamination and decommissioning (D and D) project and activities are begun. Based on the methodology of DOE-STD-1027-92, Hazards Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports, the final facility hazards category is identified as hazards category This considers the remaining material inventories, form and distribution of the material, and the energies present to initiate events of concern. Given the current facility configuration, conditions, and authorized S and M activities, there are no operational events identified resulting in significant hazard to any of the target receptor groups (e.g., workers, public, environment). The only accident scenarios identified with consequences to the onsite co-located workers were based on external natural phenomena, specifically an earthquake. The dose consequences of these events are within the current risk evaluation guidelines and are consistent with the expectations for a hazards category 2 facility.

  18. Extended-burnup LWR (light-water reactor) fuel: The amount, characteristics, and potential effects on interim storage

    SciTech Connect (OSTI)

    Bailey, W.J.

    1989-03-01T23:59:59.000Z

    The results of a study on extended-burnup, light-water reactor (LWR) spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory for the US Department of Energy (DOE). The purpose of the study was to collect and evaluate information on the status of in-reactor performance and integrity of extended-burnup LWR fuel and initiate the investigation of the effects of extending fuel burnup on the subsequent handling, interim storage, and other operations (e.g., rod consolidation and shipping) associated with the back end of the fuel cycle. The results of this study will aid DOE and the nuclear industry in assessing the effects on waste management of extending the useful in-reactor life of nuclear fuel. The experience base with extended-burnup fuel is now substantial and projections for future use of extended-burnup fuel in domestic LWRs are positive. The basic performance and integrity of the fuel in the reactor has not been compromised by extending the burnup, and the potential limitations for further extending the burnup are not severe. 104 refs., 15 tabs.

  19. REVIEW OF FAST FLUX TEST FACILITY (FFTF) FUEL EXPERIMENTS FOR STORAGE IN INTERIM STORAGE CASKS (ISC)

    SciTech Connect (OSTI)

    CHASTAIN, S.A.

    2005-10-24T23:59:59.000Z

    Appendix H, Section H.3.3.10.11 of the Final Safety Analysis Report (FSAR), provides the limits to be observed for fueled components authorized for storage in the Fast Flux Test Facility (FFTF) spent fuel storage system. Currently, the authorization basis allows standard driver fuel assemblies (DFA), as described in the FSAR Chapter 17, Section 17.5.3.1, to be stored provided decay power per assembly is {le} 250 watts, post-irradiation time is four years minimum, average assembly burn-up is 150,000 MWD/MTHM maximum and the pre-irradiation enrichment is 29.3% maximum (per H.3.3.10.11). In addition, driver evaluation (DE), core characterizer assemblies (CCA), and run-to-cladding-breach (RTCB) assemblies are included based on their similarities to a standard DFA. Ident-69 pin containers with fuel pins from these DFAs can also be stored. Section H.3.3.10.11 states that fuel types outside the specification criteria above will be addressed on a case-by-case basis. There are many different types of fuel and blanket experiments that were irradiated in the FFTF which now require offload to the spent fuel storage system. Two reviews were completed for a portion of these special type fuel components to determine if placement into the Core Component Container (CCC)/Interim Storage Cask (ISC) would require any special considerations or changes to the authorization basis. Project mission priorities coupled with availability of resources and analysts prevented these evaluations from being completed as a single effort. Areas of review have included radiological accident release consequences, radiological shielding adequacy, criticality safety, thermal limits, confinement, and stress. The results of these reviews are available in WHC-SD-FF-RPT-005, Rev. 0 and 1, ''Review of FFTF Fuel Experiments for Storage at ISA'', (Reference I), which subsequently allowed a large portion of these components to be included in the authorization basis (Table H.3.3-21). The report also identified additional components and actions in Section 3.0 and Table 3 that require further evaluation. The purpose of this report is to evaluate another portion of the remaining inventory (i.e., delayed neutron signal fuel, blanket assemblies, highly enriched assemblies, newly loaded Ident-69 pin containers, and returned fuel) to ensure it can be safely off loaded to the FFTF spent fuel storage system.

  20. Single-shell tank interim stabilization project plan

    SciTech Connect (OSTI)

    Ross, W.E.

    1998-03-27T23:59:59.000Z

    Solid and liquid radioactive waste continues to be stored in 149 single-shell tanks at the Hanford Site. To date, 119 tanks have had most of the pumpable liquid removed by interim stabilization. Thirty tanks remain to be stabilized. One of these tanks (C-106) will be stabilized by retrieval of the tank contents. The remaining 29 tanks will be interim stabilized by saltwell pumping. In the summer of 1997, the US Department of Energy (DOE) placed a moratorium on the startup of additional saltwell pumping systems because of funding constraints and proposed modifications to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestones to the Washington State Department of Ecology (Ecology). In a letter dated February 10, 1998, Final Determination Pursuant to Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) in the Matter of the Disapproval of the DOE`s Change Control Form M-41-97-01 (Fitzsimmons 1998), Ecology disapproved the DOE Change Control Form M-41-97-01. In response, Fluor Daniel Hanford, Inc. (FDH) directed Lockheed Martin Hanford Corporation (LNMC) to initiate development of a project plan in a letter dated February 25, 1998, Direction for Development of an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan in Support of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In a letter dated March 2, 1998, Request for an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan, the DOE reaffirmed the need for an aggressive SST interim stabilization completion project plan to support a finalized Tri-Party Agreement Milestone M-41 recovery plan. This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities, and interfaces; and operational methods. The plan is based on realistic assumptions and addresses three separate funding scenarios.

  1. Verification and validation interim report for portable 1,000 CFM exhauster skids POR-007/Skid E and POR-008/Skid F

    SciTech Connect (OSTI)

    Nelson, O.D.

    1998-07-25T23:59:59.000Z

    This Verification and Validation (V/V) interim report summarizes to date the results of the V/V tasks performed in each of the following life cycle phases: concept, requirements, design, implementation, test, installation and checkout, and operation and maintenance. At the end of the installation and checkout phase, the V/V final report will be issued. This interim report contains or references the following for each phase: Description of V/V tasks performed; Summary of task results; Summary of anomalies and resolution; Assessment of system quality; Recommendations.

  2. Lakeland Electric SGIG Consumer Behavior Study Interim (Year 1) Evaluation

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment ofLetter Report:40PM toLEDControl Concept | DepartmentLake

  3. Lakeland Electric SGIG Consumer Behavior Study Interim (Year 1) Evaluation

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the.pdfBreaking ofOil & Gas » MethaneJohnsonKristina PflanzLMLaboratory

  4. RTD Biodiesel (B20) Transit Bus Evaluation: Interim Review Summary

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible forPortsmouth/Paducah47,193.70COMMUNITYResponses:December562 RevisionI: EnergyFeedsRTD

  5. Conduct and results of the Interagency Nuclear Safety Review Panel's evaluation of the Ulysses space mission

    SciTech Connect (OSTI)

    Sholtis, J.A. Jr. (Directorate of Nuclear Surety, Air Force Inspection Safety Center, Kirtland AFB, New Mexico 87117-5000 (USA)); Gray, L.B. (Office of Safety Mission Quality, National Aeronautics Space Administration, Washington, DC 20546 (USA)); Huff, D.A. (Office of Environment, Safety, Health, U.S. Department of Energy, Washington, DC 20545 (USA)); Klug, N.P. (Office of Light Water Reactor Safety Technology, U.S. Department of Energy, Washington, DC 20545 (USA)); Winchester, R.O. (Directorate of Nuclear Surety, Air Force Inspection Safety Center, Kirtland, AFB, New Mexico 87111-5000 (USA))

    1991-01-01T23:59:59.000Z

    The recent 6 October 1990 launch and deployment of the nuclear-powered Ulysses spacecraft from the Space Shuttle {ital Discovery} culminated an extensive safety review and evaluation effort by the Interagency Nuclear Safety Review Panel (INSRP). After more than a year of detailed independent review, study, and analysis, the INSRP prepared a Safety Evaluation Report (SER) on the Ulysses mission, in accordance with Presidential Directive-National Security Council memorandum 25. The SER, which included a review of the Ulysses Final Safety Analysis Report (FSAR) and an independent characterization of the mission risks, was used by the National Aeronautics and Space Administration (NASA) in its decision to request launch approval as well as by the Executive Office of the President in arriving at a launch decision based on risk-benefit considerations. This paper provides an overview of the Ulysses mission and the conduct as well as the results of the INSRP evaluation. While the mission risk determined by the INSRP in the SER was higher than that characterized by the Ulysses project in the FSAR, both reports indicated that the radiological risks were relatively small. In the final analysis, the SER proved to be supportive of a positive launch decision. The INSRP evaluation process has demonstrated its effectiveness numerous times since the 1960s. In every case, it has provided the essential ingredients and perspective to permit an informed launch decision at the highest level of our Government.

  6. Interim safety basis for fuel supply shutdown facility

    SciTech Connect (OSTI)

    Brehm, J.R.; Deobald, T.L.; Benecke, M.W.; Remaize, J.A.

    1995-05-23T23:59:59.000Z

    This ISB in conjunction with the new TSRs, will provide the required basis for interim operation or restrictions on interim operations and administrative controls for the Facility until a SAR is prepared in accordance with the new requirements. It is concluded that the risk associated with the current operational mode of the Facility, uranium closure, clean up, and transition activities required for permanent closure, are within Risk Acceptance Guidelines. The Facility is classified as a Moderate Hazard Facility because of the potential for an unmitigated fire associated with the uranium storage buildings.

  7. SunLine Transit Agency Advanced Technology Fuel Cell Bus Evaluation: Second Results Report and Appendices

    SciTech Connect (OSTI)

    Eudy, L.; Chandler, K.

    2011-10-01T23:59:59.000Z

    This report describes operations at SunLine Transit Agency for their newest prototype fuel cell bus and five compressed natural gas (CNG) buses. In May 2010, SunLine began operating its sixth-generation hydrogen fueled bus, an Advanced Technology (AT) fuel cell bus that incorporates the latest design improvements to reduce weight and increase reliability and performance. The agency is collaborating with the U.S. Department of Energy's (DOE) National Renewable Energy Laboratory (NREL) to evaluate the bus in revenue service. This is the second results report for the AT fuel cell bus since it was placed in service, and it focuses on the newest data analysis and lessons learned since the previous report. The appendices, referenced in the main report, provide the full background for the evaluation. They will be updated as new information is collected but will contain the original background material from the first report.

  8. Computer–Based Procedures for Nuclear Power Plant Field Workers: Preliminary Results from Two Evaluation Studies

    SciTech Connect (OSTI)

    Katya L Le Blanc; Johanna H Oxstrand

    2013-10-01T23:59:59.000Z

    The Idaho National Laboratory and participants from the U.S. nuclear industry are collaborating on a research effort aimed to augment the existing guidance on computer-based procedure (CBP) design with specific guidance on how to design CBP user interfaces such that they support procedure execution in ways that exceed the capabilities of paper-based procedures (PBPs) without introducing new errors. Researchers are employing an iterative process where the human factors issues and interface design principles related to CBP usage are systematically addressed and evaluated in realistic settings. This paper describes the process of developing a CBP prototype and the two studies conducted to evaluate the prototype. The results indicate that CBPs may improve performance by reducing errors, but may increase the time it takes to complete procedural tasks.

  9. Santa Clara Valley Transportation Authority and San Mateo County Transit District; Fuel Cell Transit Buses: Preliminary Evaluation Results

    SciTech Connect (OSTI)

    Eudy, L.; Chandler, K.

    2006-03-01T23:59:59.000Z

    Report provides preliminary results from an evaluation of prototype fuel cell transit buses operating at Santa Clara Valley Transportation Authority (VTA) in San Jose, California.

  10. Santa Clara Valley Transportation Authority and San Mateo County Transit District -- Fuel Cell Transit Buses: Evaluation Results

    SciTech Connect (OSTI)

    Chandler, K.; Eudy, L.

    2006-11-01T23:59:59.000Z

    This report provides evaluation results for prototype fuel cell transit buses operating at Santa Clara Valley Transportation Authority in San Jose, California.

  11. SunLine Transit Agency Advanced Technology Fuel Cell Bus Evaluation: First Results Report

    SciTech Connect (OSTI)

    Eudy, L.; Chandler, K.

    2011-03-01T23:59:59.000Z

    This report describes operations at SunLine Transit Agency for their newest prototype fuel cell bus and five compressed natural gas (CNG) buses. In May 2010, SunLine began operating its sixth-generation hydrogen fueled bus, an Advanced Technology (AT) fuel cell bus that incorporates the latest design improvements to reduce weight and increase reliability and performance. The agency is collaborating with the U.S. Department of Energy's (DOE) National Renewable Energy Laboratory (NREL) to evaluate the bus in revenue service. This report provides the early data results and implementation experience of the AT fuel cell bus since it was placed in service.

  12. Single-shell tank interim stabilization project plan

    SciTech Connect (OSTI)

    Ross, W.E.

    1998-05-11T23:59:59.000Z

    This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline.

  13. Single Shell Tank (SST) Interim Stabilization Project Plan

    SciTech Connect (OSTI)

    VLADIMIROFF, D.T.; BOYLES, V.C.

    2000-05-22T23:59:59.000Z

    This project plan establishes the management framework for the conduct of the CHG Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organization structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline.

  14. Division of Residential and Campus Communities Review Interim Report

    E-Print Network [OSTI]

    Botea, Adi

    Division of Residential and Campus Communities Review Interim Report December 2013 As stressed in the University's strategic plan ANU by 2020, the residential experience is a key aspect of the holistic ANU experience of all students by providing a richer residential experience for on-campus students and more

  15. SunLine Transit Agency Advanced Technology Fuel Cell Bus Evaluation: Fourth Results Report

    SciTech Connect (OSTI)

    Eudy, L.; Chandler, K.

    2013-01-01T23:59:59.000Z

    SunLine Transit Agency, which provides public transit services to the Coachella Valley area of California, has demonstrated hydrogen and fuel cell bus technologies for more than 10 years. In May 2010, SunLine began demonstrating the advanced technology (AT) fuel cell bus with a hybrid electric propulsion system, fuel cell power system, and lithium-based hybrid batteries. This report describes operations at SunLine for the AT fuel cell bus and five compressed natural gas buses. The U.S. Department of Energy's National Renewable Energy Laboratory (NREL) is working with SunLine to evaluate the bus in real-world service to document the results and help determine the progress toward technology readiness. NREL has previously published three reports documenting the operation of the fuel cell bus in service. This report provides a summary of the results with a focus on the bus operation from February 2012 through November 2012.

  16. High Temperature Materials Interim Data Qualification Report FY 2011

    SciTech Connect (OSTI)

    Nancy Lybeck

    2011-08-01T23:59:59.000Z

    Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim fiscal year (FY) 2011 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under the Nuclear Quality Assurance (NQA)-1 guidelines and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from seven test series within the High Temperature Materials data stream have been entered into the NDMAS vault, including tensile tests, creep tests, and cyclic tests. Of the 5,603,682 records currently in the vault, 4,480,444 have been capture passed, and capture testing is in process for the remaining 1,123,238.

  17. SLIGHTLY IRRADIATED FUEL (SIF) INTERIM DISPOSITION PROJECT

    SciTech Connect (OSTI)

    NORTON SH

    2010-02-23T23:59:59.000Z

    CH2M HILL Plateau Remediation Company (CH2M HILL PRC) is proud to submit the Slightly Irradiated Fuel (SIF) Interim Disposition Project for consideration by the Project Management Institute as Project of the Year for 2010. The SIF Project was a set of six interrelated sub-projects that delivered unique stand-alone outcomes, which, when integrated, provided a comprehensive and compliant system for storing high risk special nuclear materials. The scope of the six sub-projects included the design, construction, testing, and turnover of the facilities and equipment, which would provide safe, secure, and compliant Special Nuclear Material (SNM) storage capabilities for the SIF material. The project encompassed a broad range of activities, including the following: Five buildings/structures removed, relocated, or built; Two buildings renovated; Structural barriers, fencing, and heavy gates installed; New roadways and parking lots built; Multiple detection and assessment systems installed; New and expanded communication systems developed; Multimedia recording devices added; and A new control room to monitor all materials and systems built. Project challenges were numerous and included the following: An aggressive 17-month schedule to support the high-profile Plutonium Finishing Plant (PFP) decommissioning; Company/contractor changeovers that affected each and every project team member; Project requirements that continually evolved during design and construction due to the performance- and outcome-based nature ofthe security objectives; and Restrictions imposed on all communications due to the sensitive nature of the projects In spite of the significant challenges, the project was delivered on schedule and $2 million under budget, which became a special source of pride that bonded the team. For years, the SIF had been stored at the central Hanford PFP. Because of the weapons-grade piutonium produced and stored there, the PFP had some of the tightest security on the Hanford nuclear reservation. Workers had to pass through metal detectors when they arrived at the plant and materials leaving the plant had to be scanned for security reasons. Whereas other high-security nuclear materials were shipped from the PFP to Savannah River, S.C. as part ofa Department of Energy (DOE) program to consolidate weapons-grade plutonium, it was determined that the SIF should remain onsite pending disposition to a national repository. Nevertheless, the SIF still requires a high level of security that the PFP complex has always provided. With the 60-year PFP mission of producing and storing plutonium concluded, the environmental cleanup plans for Hanford call for the demolition of the 63-building PFP complex. Consequently, if the SIF remained at PFP it not only would have interfered with the environmental cleanup plans, but would have required $100 million in facility upgrades to meet increased national security requirements imposed after the 9/11 terrorist attacks. A new smaller and more cost-effective area was needed to store this material, which led to the SIF Project. Once the SIF project was successfully completed and the SIF was safely removed from PFP, the existing Protected Area at PFP could be removed, and demolition could proceed more quickly without being encumbered by restrictive security requirements that an active Protected Area requires. The lightened PFP security level brought by safely removing and storing the SIF would also yield lowered costs for deactivation and demolition, as well as reduce overall life-cycle costs.

  18. SunLine Transit Agency Advanced Technology Fuel Cell Bus Evaluation: Third Results Reports

    SciTech Connect (OSTI)

    Eudy, L.; Chandler, K.

    2012-05-01T23:59:59.000Z

    This report describes operations at SunLine Transit Agency for their newest prototype fuel cell bus and five compressed natural gas (CNG) buses. In May 2010, SunLine began operating its sixth-generation hydrogen fueled bus, an Advanced Technology (AT) fuel cell bus that incorporates the latest design improvements to reduce weight and increase reliability and performance. The agency is collaborating with the U.S. Department of Energy's (DOE) National Renewable Energy Laboratory (NREL) to evaluate the bus in revenue service. NREL has previously published two reports documenting the operation of the fuel cell bus in service. This report provides a summary of the results with a focus on the bus operation from July 2011 through January 2012.

  19. RESULTS FOR THE INTERMEDIATE-SPECTRUM ZEUS BENCHMARK OBTAINED WITH NEW 63,65Cu CROSS-SECTION EVALUATIONS

    SciTech Connect (OSTI)

    Sobes, Vladimir [ORNL] [ORNL; Leal, Luiz C [ORNL] [ORNL

    2014-01-01T23:59:59.000Z

    The four HEU, intermediate-spectrum, copper-reflected Zeus experiments have shown discrepant results between measurement and calculation for the last several major releases of the ENDF library. The four benchmarks show a trend in reported C/E values with increasing energy of average lethargy causing fission. Recently, ORNL has made improvements to the evaluations of three key isotopes involved in the benchmark cases in question. Namely, an updated evaluation for 235U and evaluations of 63,65Cu. This paper presents the benchmarking results of the four intermediate-spectrum Zeus cases using the three updated evaluations.

  20. Evaluation of operational safety at Babcock and Wilcox Plants: Volume 2, Thermal-hydraulic results

    SciTech Connect (OSTI)

    Wheatley, P.D.; Davis, C.B.; Callow, R.A.; Fletcher, C.D.; Dobbe, C.A.; Beelman, R.J.

    1987-11-01T23:59:59.000Z

    The Nuclear Regulatory Commission has initiated a research program to develop a methodology to assess the operational performance of Babcock and Wilcox plants and to apply this methodology on a trial basis. The methodology developed for analyzing Babcock and Wilcox plants integrated methods used in both thermal-hydraulics and human factors and compared results with information used in the assessment of risk. The integrated methodology involved an evaluation of a selected plant for each pressurized water reactor vendor during a limited number of transients. A plant was selected to represent each vendor, and three transients were identified for analysis. The plants were Oconee Unit 1 for Babcock and Wilcox, H.B. Robinson Unit 2 for Westinghouse, and Calvert Cliffs Unit 1 for Combustion Engineering. The three transients were a complete loss of all feedwater, a small-break loss-of-coolant accident, and a steam-generator overfill with auxiliary feedwater. Included in the integrated methodology was an assessment of the thermal-hydraulic behavior, including event timing, of the plants during the three transients. Thermal-hydraulic results are presented in this volume (Volume 2) of the report. 26 refs., 30 figs., 7 tabs.

  1. 105-H Reactor Interim Safe Storage Project Final Report

    SciTech Connect (OSTI)

    E.G. Ison

    2008-11-08T23:59:59.000Z

    The following information documents the decontamination and decommissioning of the 105-H Reactor facility, and placement of the reactor core into interim safe storage. The D&D of the facility included characterization, engineering, removal of hazardous and radiologically contaminated materials, equipment removal, decontamination, demolition of the structure, and restoration of the site. The ISS work also included construction of the safe storage enclosure, which required the installation of a new roofing system, power and lighting, a remote monitoring system, and ventilation components.

  2. Method of preparing nuclear wastes for tansportation and interim storage

    DOE Patents [OSTI]

    Bandyopadhyay, Gautam (Naperville, IL); Galvin, Thomas M. (Darien, IL)

    1984-01-01T23:59:59.000Z

    Nuclear waste is formed into a substantially water-insoluble solid for temporary storage and transportation by mixing the calcined waste with at least 10 weight percent powdered anhydrous sodium silicate to form a mixture and subjecting the mixture to a high humidity environment for a period of time sufficient to form cementitious bonds by chemical reaction. The method is suitable for preparing an interim waste form from dried high level radioactive wastes.

  3. Report to Congress on Plan for Interim Storage of Spent Nuclear...

    Broader source: Energy.gov (indexed) [DOE]

    Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from Decommissioned Reactors More Documents & Publications Information Request, "THE REPORT TO THE PRESIDENT...

  4. Evaluation of oil palm research and the dissemination of its results in Nigeria

    SciTech Connect (OSTI)

    Agiobenebo, T.J.

    1986-01-01T23:59:59.000Z

    This dissertation evaluates public investment in oil palm research and the dissemination of research results in Nigeria using the economic surplus technique adapted to suit the specific setting in which these activities are carried out. The issues raised include: (1) development of appropriate test of investment effectiveness suitable for appraising public investment in hybrid palm research and extension; (2) specification and econometric estimation of supply and demand functions for oil and kernels; (3) computation of the social returns to research; (4) sensitivity of returns to variations in extraction rates for both oil and kernels; (5) sensitivity of returns to research to types of supply shift; and (6) isolation of qualitative implications for public policy with respect to maximum exploitation of the economic opportunities offered by the knowledge generated by oil palm research. The author found that investments in hybrid palm research and extension are socially profitable under a wide range of conditions. The returns to research and related activities were computed and reported by periods according to the data situation and accrued, expected and total benefits over the investment.

  5. Evaluating impacts of CO2 gas intrusion into a confined sandstone aquifer: Experimental results

    SciTech Connect (OSTI)

    Qafoku, Nikolla; Lawter, Amanda R.; Shao, Hongbo; Wang, Guohui; Brown, Christopher F.

    2014-12-31T23:59:59.000Z

    Deep subsurface storage and sequestration of CO2 has been identified as a potential mitigation technique for rising atmospheric CO2 concentrations. Sequestered CO2 represents a potential risk to overlying aquifers if the CO2 leaks from the deep storage reservoir. Experimental and modeling work is required to evaluate potential risks to groundwater quality and develop a systematic understanding of how CO2 leakage may cause important changes in aquifer chemistry and mineralogy by promoting dissolution/precipitation, adsorption/desorption, and redox reactions. Sediments from the High Plains aquifer in Kansas, United States, were used in this investigation, which is part of the National Risk Assessment Partnership Program sponsored by the US Department of Energy. This aquifer was selected to be representative of consolidated sand and gravel/sandstone aquifers overlying potential CO2 sequestration repositories within the continental US. In this paper, we present results from batch experiments conducted at room temperature and atmospheric pressure with four High Plains aquifer sediments. Batch experiments simulate sudden, fast, and short-lived releases of the CO2 gas as would occur in the case of well failure during injection. Time-dependent release of major, minor, and trace elements were determined by analyzing the contacting solutions. Characterization studies demonstrated that the High Plains aquifer sediments were abundant in quartz and feldspars, and contained about 15 to 20 wt% montmorillonite and up to 5 wt% micas. Some of the High Plains aquifer sediments contained no calcite, while others had up to about 7 wt% calcite. The strong acid extraction tests confirmed that in addition to the usual elements present in most soils, rocks, and sediments, the High Plains aquifer sediments had appreciable amounts of As, Cd, Pb, Cu, and occasionally Zn, which potentially may be mobilized from the solid to the aqueous phase during or after exposure to CO2. However, the results from the batch experiments showed that the High Plains sediments mobilized only low concentrations of trace elements (potential contaminants), which were detected occasionally in the aqueous phase during these experiments. Importantly, these occurrences were more frequent in the calcite-free sediment. Results from these investigations provide useful information to support site selection, risk assessment, and public education efforts associated with geological CO2 storage and sequestration.

  6. Plutonium Surveillance Destructive Examination Requirements at Savannah River National Laboratory for K-Area Interim Surveillance

    SciTech Connect (OSTI)

    Stefek, T. M.

    2005-09-29T23:59:59.000Z

    The DOE 3013 storage standard requires nested, welded 300 series stainless steel containers to store plutonium-bearing materials for up to 50 years. Packaged contents include stabilized plutonium-bearing residues that contain chloride salts and a low (< 0.5 weight %) water content. The DOE 3013 STD requires surveillance of the packages over the 50 year lifetime. These surveillance requirements have been further defined by the Integrated Surveillance Program to include both non-destructive examination (NDE) and destructive examination (DE) of the 3013 container. The DE portion of surveillance involves examining the 3013 nested containers, analyzing the head space gas, and evaluating the plutonium oxide chemistry. At SRS, the stored 3013 containers will undergo preparation for the DE surveillance activities in facilities located in K-Area. The actual DE surveillance will be performed in SRNL. This report provides preliminary functional requirements for the destructive examination (DE) of plutonium-bearing oxide materials and containers in support of K-Area Interim Surveillance (KIS). The KIS project will install interim facilities to prepare the samples for analysis in SRNL. This document covers the requirements for the interim period beginning in 2007, and lasting until the Container Storage and Surveillance Capability (CSSC) project provides the permanent facilities in K-Area to perform sampling and repackaging operations associated with the 3013 container storage and surveillance program. Initial requirements for the CSSC project have been previously defined in WSRC-TR-2004-00584 ''Plutonium Surveillance Destructive Examination Requirements at Savannah River National Laboratory''. As part of the Plutonium Surveillance Program of 3013 Containers at the Savannah River Site (SRS), the Savannah River National Laboratory (SRNL) will receive the emptied 3013 container components, plutonium oxide samples and headspace gas samples from K-Area. The DE program scope includes chemical and metallurgical analyses for a maximum of 25 DE sets a year to provide essential data in support of the SRS Plutonium Surveillance Program. The normal operation is expected to be approximately 15 DE sets a year.

  7. Alameda-Contra Costa Transit District (AC Transit) Fuel Cell Transit Buses: Preliminary Evaluation Results

    SciTech Connect (OSTI)

    Chandler, K.; Eudy, L.

    2007-03-01T23:59:59.000Z

    This report provides an evaluation of three prototype fuel cell-powered transit buses operating at AC Transit in Oakland, California, and six baseline diesel buses similar in design to the fuel cell buses.

  8. EA-2005: Chromium Plume Control Interim Measure And Plume-Center Characterization, Los Alamos National Laboratory, Los Alamos, NM

    Broader source: Energy.gov [DOE]

    EA-2005: Chromium Plume Control Interim Measure And Plume-Center Characterization, Los Alamos National Laboratory, Los Alamos, NM

  9. RCRA Corrective Action Plan. Interim report (Final)

    SciTech Connect (OSTI)

    Not Available

    1988-06-01T23:59:59.000Z

    The RCRA Corrective Action Plan (CAP) will assist in the development of Corrective Action Orders (Section 3008(h)) and corrective action requirements in permit applications and permits (Section 3004(u) (v)). The purpose of the CAP is to aid Regions and States in determining and directing the specific work the owner/operator or respondent must perform, as part of a complete corrective action program. The CAP should be used as a technical framework during the development of Corrective Action Orders and corrective action permit regulations. The CAP provides a framework for the development of a site-specific schedule of compliance to be included in a permit or a compliance schedule in a Corrective Action Order. It does so by laying out scopes of work for the three essential phases of a complete corrective action program. These three phases and their objectives are as follows: (1) RCRA Facility Investigation (RFI) - to evaluate thoroughly the nature and extent of the release of hazardous waste and hazardous constituents and to gather necessary data to support the Corrective Measure Study; (2) Corrective Measures Study (CMS) - to develop and evaluate a corrective measure alternative or alternatives and to recommend the final corrective measure or measures; and (3) Corrective Measures Implementation (CMI) - to design, construct, operate, maintain and monitor the performance of the corrective measure or measures selected.

  10. Synergy between Liquid Walls and Tokamak Physics Performance APEX Interim Report November, 1999

    E-Print Network [OSTI]

    California at Los Angeles, University of

    Synergy between Liquid Walls and Tokamak Physics Performance APEX Interim Report November, 1999 15-1 CHAPTER 15: SYNERGISM BETWEEN LIQUID METAL WALLS, TOKAMAK PHYSICS PERFORMANCE, AND REACTOR ATTRACTIVENESS and Tokamak Physics Performance APEX Interim Report November, 1999 15-2 15. SYNERGISM BETWEEN LIQUID METAL

  11. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    SciTech Connect (OSTI)

    Burgard, K.C.

    1998-04-09T23:59:59.000Z

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

  12. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    SciTech Connect (OSTI)

    Burgard, K.C.

    1998-06-02T23:59:59.000Z

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

  13. Green River Lake and Dam interim plan benefits ecosystem By John Hickey

    E-Print Network [OSTI]

    US Army Corps of Engineers

    11 Green River Lake and Dam interim plan benefits ecosystem By John Hickey Hydrologic Engineering that water is released from Green River Dam in Kentucky. In May 2006, the interim plan was approved shown that operation of Green River Dam can be changed in ways that improve ecosystems while continuing

  14. Interim activities report. [Westinghouse Savannah River Company

    SciTech Connect (OSTI)

    Majzlik, E.H. Jr.

    1992-01-01T23:59:59.000Z

    Several developments have occurred since the 32nd WANTO Meeting that effect the status of the Savannah River Site. A request to restart K-Reactor was issued after nearly three years of intensive engineering analysis, procedure revisions and enhanced operator training to upgrade all aspects of reactor operation. In early December 1991, the Westinghouse Savannah River Company requested permission from DOE to start the K-Reactor. In mid-December the DOE and the Defense Nuclear Facility Safety Board concurred with readiness to operate and a Federal Circuit Court of Appeals ruled against a lawsuit to delay restart until a cooling tower is completed. The K-Reactor was restarted and has been in an evaluation and testing mode. Full power operation at thirty percent of maximum capacity is projected for March 1992 after which actual tritium generation will begin. Operation will continue until October when the cooling tower will be tied into the reactor cooling system. In conjunction with the restart of K-Reactor, the P-Reactor has been placed in permanent shutdown status and the L-Reactor has been placed in warm stand-by. In another reactor related situation, the DOE will delay the decision on construction of the New Production Reactor (NPR) until 1993. The choice of reactor type and location of the NPR will be integrated into the overall programmatic decision on Reconfiguration of the Weapons Complex. Finally, construction of the Replacement Tritium Facility (RTF) was resumed in December 1991 after several months stoppage for evaluation and revision of project funding procedures.

  15. Fast Flux Test Facility interim examination and maintenance cell: Past, present, and future

    SciTech Connect (OSTI)

    Vincent, J.R.

    1990-09-01T23:59:59.000Z

    The Fast Flux Test Facility Interim Examination and Maintenance Cell was designed to perform interim examination and/or disassembly of experimental core components for final analysis elsewhere, as well as maintenance of sodium-wetted or neutron-activated internal reactor parts and plant support hardware. The Interim Examination and Maintenance Cell equipment developed and used for the first ten years of operation has been primarily devoted to the disassembly and examination of core component test assemblies. While no major reactor equipment has required remote repair or maintenance, the Interim Examina Examination and Maintenance Cell has served as the remote repair facility for its own in-cell equipment, and several innovative remote repairs have been accomplished. The Interim Examination and Maintenance Cell's demonstrated versatility has shown its capability to support a challenging future. 12 refs., 9 figs.

  16. Hanford low-level tank waste interim performance assessment

    SciTech Connect (OSTI)

    Mann, F.M.

    1997-09-12T23:59:59.000Z

    The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and performance early in the disposal system project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives.

  17. Hanford low-level tank waste interim performance assessment

    SciTech Connect (OSTI)

    Mann, F.M.

    1996-09-16T23:59:59.000Z

    The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single- and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and its performance as early as possible in the project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives.

  18. US PRACTICE FOR INTERIM WET STORAGE OF RRSNF

    SciTech Connect (OSTI)

    Vinson, D.

    2010-08-05T23:59:59.000Z

    Aluminum research reactor spent nuclear fuel is currently being stored or is anticipated to be returned to the United States and stored at Department of Energy storage facilities at the Savannah River Site and the Idaho Nuclear Technology and Engineering Center. This paper summarizes the current practices to provide for continued safe interim wet storage in the U.S. Aluminum fuel stored in poor quality water is subject to aggressive corrosion attack and therefore water chemistry control systems are essential to maintain water quality. Fuel with minor breaches are safely stored directly in the basin. Fuel pieces and heavily damaged fuel is safely stored in isolation canisters.

  19. Interim Final Rule and Proposed Rule | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment of EnergyIndustry15Among States in theWAPA1Interim Final Rule

  20. Interim Report on Customer Acceptance, Retention, and Response to

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment of EnergyIndustry15Among States in theWAPA1Interim

  1. Interim report on updated microarray probes for the LLNL Burkholderia pseudomallei SNP array

    SciTech Connect (OSTI)

    Gardner, S; Jaing, C

    2012-03-27T23:59:59.000Z

    The overall goal of this project is to forensically characterize 100 unknown Burkholderia isolates in the US-Australia collaboration. We will identify genome-wide single nucleotide polymorphisms (SNPs) from B. pseudomallei and near neighbor species including B. mallei, B. thailandensis and B. oklahomensis. We will design microarray probes to detect these SNP markers and analyze 100 Burkholderia genomic DNAs extracted from environmental, clinical and near neighbor isolates from Australian collaborators on the Burkholderia SNP microarray. We will analyze the microarray genotyping results to characterize the genetic diversity of these new isolates and triage the samples for whole genome sequencing. In this interim report, we described the SNP analysis and the microarray probe design for the Burkholderia SNP microarray.

  2. Corona and Motor Voltage Interim Report

    SciTech Connect (OSTI)

    Hsu, J.S.

    2005-05-06T23:59:59.000Z

    It has been suggested that to meet the FreedomCAR objectives for cost, size, weight, efficiency, and reliability higher buss voltages be utilized in HEV and FC automotive applications. The reasoning is that since electric power is equal to the product of voltage and current for a given power a higher voltage and lower current would result in smaller cable and inverter switching components. Consequently, the system can be lighter and smaller. On the other hand, higher voltages are known to require better and thicker electrical insulation that reduce the available slot area for motor windings. One cause of slow insulation breakdown is corona that gradually erodes the insulation and shortens the life expectancy of the motor. This study reports on the results of a study on corona initiating voltages for mush-wound and bobbin-wound stators. A unique testing method is illustrated.

  3. Evaluating state markets for residential wind systems: Results from an economic and policy analysis tool

    E-Print Network [OSTI]

    Edwards, Jennifer L.; Wiser, Ryan; Bolinger, Mark; Forsyth, Trudy

    2004-01-01T23:59:59.000Z

    xii Figure ES-4. Incremental LCOE Without State16 Figure 5. LCOE Results from SWAT Base-Case60 Table A-5. Base Case Results for LCOE for Wind Classes 2-

  4. Learning Demonstration Interim Progress Report -- July 2010

    SciTech Connect (OSTI)

    Wipke, K.; Spirk, S.; Kurtz, J.; Ramsden, T.

    2010-09-01T23:59:59.000Z

    This report discusses key results based on data through December 2009 from the U.S. Department of Energy's (DOE) Controlled Hydrogen Fleet and Infrastructure Validation and Demonstration Project, also referred to as the National Fuel Cell Electric Vehicle (FCEV) Learning Demonstration. The report serves to help transfer knowledge and lessons learned within various parts of DOE's hydrogen program, as well as externally to other stakeholders. It is the fourth such report in a series, with previous reports being published in July 2007, November 2007, and April 2008.

  5. Residential energy demand modeling and the NIECS data base : an evaluation

    E-Print Network [OSTI]

    Cowing, Thomas G.

    1982-01-01T23:59:59.000Z

    The purpose of this report is to evaluate the 1978-79 National Interim Energy Consumption Survey (NIECS) data base in terms of its usefulness for estimating residential energy demand models based on household appliance ...

  6. ZINC MITIGATION INTERIM REPORT - THERMODYNAMIC STUDY

    SciTech Connect (OSTI)

    Korinko, P.

    2010-12-17T23:59:59.000Z

    An experimental program was initiated in order to develop and validate conditions that will effectively trap Zn vapors that are released during extraction. The proposed work is broken down into three tasks. The first task is to determine the effectiveness of various pore sizes of filter elements. The second task is to determine the effect of filter temperature on zinc vapor deposition. The final task is to determine whether the zinc vapors can be chemically bound. The approach for chemically binding the zinc vapors has two subtasks, the first is a review of literature and thermodynamic calculations and the second is an experimental approach using the best candidates. This report details the results of the thermodynamic calculations to determine feasibility of chemically binding the zinc vapors within the furnace module, specifically the lithium trap (1). A review of phase diagrams, literature, and thermodynamic calculations was conducted to determine if there are suitable materials to capture zinc vapor within the lithium trap of the extraction basket. While numerous elements exist that form compounds with zinc, many of these also form compounds with hydrogen or the water that is present in the TPBARs. This relatively comprehensive review of available data indicates that elemental cobalt and copper and molybdenum trioxide (MoO3) may have the requisite properties to capture zinc and yet not be adversely affected by the extraction gases and should be considered for testing.

  7. HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT BUCKLING EVALUATION METHODS & RESULTS FOR THE PRIMARY TANKS

    SciTech Connect (OSTI)

    MACKEY TC; JOHNSON KI; DEIBLER JE; PILLI SP; RINKER MW; KARRI NK

    2007-02-14T23:59:59.000Z

    This report documents a detailed buckling evaluation of the primary tanks in the Hanford double-shell waste tanks (DSTs), which is part of a comprehensive structural review for the Double-Shell Tank Integrity Project. This work also provides information on tank integrity that specifically responds to concerns raised by the Office of Environment, Safety, and Health (ES&H) Oversight (EH-22) during a review of work performed on the double-shell tank farms and the operation of the aging waste facility (AWF) primary tank ventilation system. The current buckling review focuses on the following tasks: (1) Evaluate the potential for progressive I-bolt failure and the appropriateness of the safety factors that were used for evaluating local and global buckling. The analysis will specifically answer the following questions: (a) Can the EH-22 scenario develop if the vacuum is limited to -6.6-inch water gage (w.g.) by a relief valve? (b) What is the appropriate factor of safety required to protect against buckling if the EH-22 scenario can develop? (c) What is the appropriate factor of safety required to protect against buckling if the EH-22 scenario cannot develop? (2) Develop influence functions to estimate the axial stresses in the primary tanks for all reasonable combinations of tank loads, based on detailed finite element analysis. The analysis must account for the variation in design details and operating conditions between the different DSTs. The analysis must also address the imperfection sensitivity of the primary tank to buckling. (3) Perform a detailed buckling analysis to determine the maximum allowable differential pressure for each of the DST primary tanks at the current specified limits on waste temperature, height, and specific gravity. Based on the I-bolt loads analysis and the small deformations that are predicted at the unfactored limits on vacuum and axial loads, it is very unlikely that the EH-22 scenario (i.e., progressive I-bolt failure leading to global buckling of the tank under increased vacuum) could occur.

  8. Novel Scanning Lens Instrument for Evaluating Fresnel Lens Performance: Equipment Development and Initial Results (Presentation)

    SciTech Connect (OSTI)

    Herrero, R.; Miller, D. C.; Kurtz, S. R.; Anton, I.; Sala, G.

    2013-07-01T23:59:59.000Z

    A system dedicated to the optical transmittance characterization of Fresnel lenses has been developed at NREL, in collaboration with the UPM. The system quantifies the optical efficiency of the lens by generating a performance map. The shape of the focused spot may also be analyzed to understand change in the lens performance. The primary instrument components (lasers and CCD detector) have been characterized to confirm their capability for performing optical transmittance measurements. Measurements performed on SoG and PMMA lenses subject to a variety of indoor conditions (e.g., UV and damp heat) identified differences in the optical efficiency of the evaluated lenses, demonstrating the ability of the Scanning Lens Instrument (SLI) to distinguish between the aged lenses.

  9. EERC pilot-scale CFBC evaluation facility Project CFB test results

    SciTech Connect (OSTI)

    Mann, M.D.; Hajicek, D.R.; Henderson, A.K.; Moe, T.A.

    1992-09-01T23:59:59.000Z

    Project CFB was initiated at the University of North Dakota Energy and Environmental Research Center (EERC) in May 1988. Specific goals of the project were to (1) construct a circulating fluidized-bed combustor (CFBC) facility representative of the major boiler vendors' designs with the capability of producing scalable data, (2) develop a database for use in making future evaluations of CFBC technology, and (3) provide a facility for evaluating fuels, free of vendor bias for use in the - energy industry. Five coals were test-burned in the 1-MWth unit: North Dakota and Asian lignites, a Wyoming subbituminous, and Colorado and Pennsylvania bituminous coats. A total of 54 steady-state test periods were conducted, with the key test parameters being the average combustor temperature, excess air, superficial gas velocity, calcium-to-sulfur molar ratio, and the primary air-to-secondary air split. The capture for a coal fired in a CFBC is primarily dependent upon the total alkali-to-sulfur ratio. The required alkali-to ratio for 90% sulfur retention ranged from 1.4 to 4.9, depending upon coal type. While an alkali-to-ratio of 4.9 was required to meet 90% sulfur retention for the Salt Creek coal versus 1.4 for the Asian lignite, the total amount of sorbent addition required is much less for the Salt Creek coal, 4.2 pound sorbent per million Btu coal input, versus 62 pound/million Btu for the Asian lignite. The bituminous coals tested show optimal capture at combustor temperatures of approximately 1550[degree]F, with low-rank coals having optimal sulfur capture approximately 100[degree]F lower.

  10. Ultrasonic Characterization of Cast Austenitic Stainless Steel Microstructure: Discrimination between Equiaxed- and Columnar-Grain Material – An Interim Study

    SciTech Connect (OSTI)

    Ramuhalli, Pradeep; Good, Morris S.; Diaz, Aaron A.; Anderson, Michael T.; Watson, Bruce E.; Peters, Timothy J.; Dixit, Mukul; Bond, Leonard J.

    2009-10-27T23:59:59.000Z

    Ultrasonic nondestructive evaluation (NDE) and inspection of cast austenitic stainless steel (CASS) components used in the nuclear power industry is neither as effective nor reliable as is needed due to detrimental effects upon the interrogating ultrasonic beam and interference from ultrasonic backscatter. The root cause is the coarse-grain microstructure inherent to this class of materials. Some ultrasonic techniques perform better for particular microstructural classifications and this has led to the hypothesis that an ultrasonic inspection can be optimized for a particular microstructural class, if a technique exists to reliably classify the microstructure for feedback to the inspection. This document summarizes scoping experiments of in-situ ultrasonic methods for classification and/or characterization of the material microstructures in CASS components from the outside surface of a pipe. The focus of this study was to evaluate ultrasonic methods and provide an interim report that documents results and technical progress. An initial set of experiments were performed to test the hypothesis that in-service characterization of cast austenitic stainless steel (CASS) is feasible, and that, if reliably performed, such data would provide real-time feedback to optimize in-service inspections in the field. With this objective in mind, measurements for the experiment were restricted to techniques that should be robust if carried forward to eventual field implementation. Two parameters were investigated for their ability to discriminate between different microstructures in CASS components. The first parameter was a time-of-flight ratio of a normal incidence shear wave to that of a normal incidence longitudinal wave (TOFRSL). The ratio removed dependency on component thickness which may not be accurately reported in the field. The second parameter was longitudinal wave attenuation. The selected CASS specimens provided five equiaxed-grain material samples and five columnar-grain material samples for a two-class discrimination problem. Qualitative TOFRSL estimates and a threshold algorithm classified all 10 material samples correctly and indicated a reliable and robust technique. Qualitative longitudinal wave attenuation estimates and a threshold algorithm also classified all 10 materials samples correctly; however, the technique was not as robust as TOFRSL. The experiments provided promising results and demonstrated that good potential exists for future development of techniques to implement real-time classification of CASS material. However, the reported measurements need to be substantiated with measurements on additional specimens.

  11. Economic evaluation of the Annual Cycle Energy System (ACES). Volume II. Detailed results. Final report

    SciTech Connect (OSTI)

    Not Available

    1980-05-01T23:59:59.000Z

    The energy effectiveness and the economic viability of the ACES concept are examined. ACES is studied in a variety of different applications and compared to a number of conventional systems. The different applications are studied in two groups: the class of building into which the ACES is incorporated and the climatic region in which the ACES is located. Buildings investigated include single-family and multi-family residences and a commercial office building. The application of ACES to each of these building types is studied in Minneapolis, Atlanta, and Philadelphia. The economic evaluation of the ACES is based on a comparison of the present worth of the ACES to the present worth of conventional systems; namely, electric resistance heating, electric air conditioning, and electric domestic water heating; air-to-air heat pump and electric domestic water heating; oil-fired furnace, electric air conditioning, and electric domestic water heating; and gas-fired furnace, electric air conditioning, and gas domestic water heating.

  12. Economic Evaluation of Short-Term Wind Power Forecasts in ERCOT: Preliminary Results; Preprint

    SciTech Connect (OSTI)

    Orwig, K.; Hodge, B. M.; Brinkman, G.; Ela, E.; Milligan, M.; Banunarayanan, V.; Nasir, S.; Freedman, J.

    2012-09-01T23:59:59.000Z

    Historically, a number of wind energy integration studies have investigated the value of using day-ahead wind power forecasts for grid operational decisions. These studies have shown that there could be large cost savings gained by grid operators implementing the forecasts in their system operations. To date, none of these studies have investigated the value of shorter-term (0 to 6-hour-ahead) wind power forecasts. In 2010, the Department of Energy and National Oceanic and Atmospheric Administration partnered to fund improvements in short-term wind forecasts and to determine the economic value of these improvements to grid operators, hereafter referred to as the Wind Forecasting Improvement Project (WFIP). In this work, we discuss the preliminary results of the economic benefit analysis portion of the WFIP for the Electric Reliability Council of Texas. The improvements seen in the wind forecasts are examined, then the economic results of a production cost model simulation are analyzed.

  13. Radiation site cleanup regulation: An interim progress report

    SciTech Connect (OSTI)

    Not Available

    1994-02-01T23:59:59.000Z

    On October 18 and 19, 1993, the 13 members of the National Advisory Council on Environmental Policy and Technology (NACEPT) Subcommittee on Radiation Site Cleanup Regulations met in Washington D.C. at the invitation of EPA. The Subcommittee discussed a variety of topics relevant to the cleanup of sites contaminated with radiation, and to the regulations which EPA will promulgate to establish cleanup levels for radioactive sites. This Interim Progress Report: condenses and summarizes the major themes, issues, and concerns brought up during the NACEPT Subcommittee meeting in October; Provides a brief description of current Agency thinking regarding each of the major topic areas discussed by the NACEPT Subcommittee; and Serves as a discussion guide for NACEPT Subcommittee members. Four major topics were discussed by the NACEPT Subcommittee members during their first meeting in October 1993: Common Themes; Risk (or Cleanup Levels and Risk Levels); Future Land Use and Local Statutes; and Site-Specific Public Involvement.

  14. Waste Encapsulation and Storage Facility (WESF) Interim Status Closure Plan

    SciTech Connect (OSTI)

    SIMMONS, F.M.

    2000-12-01T23:59:59.000Z

    This document describes the planned activities and performance standards for closing the Waste Encapsulation and Storage Facility (WESF). WESF is located within the 225B Facility in the 200 East Area on the Hanford Facility. Although this document is prepared based on Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the storage unit will comply with Washington Administrative Code (WAC) 173-303-610 regulations pursuant to Section 5.3 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Action Plan (Ecology et al. 1996). Because the intention is to clean close WESF, postclosure activities are not applicable to this interim status closure plan. To clean close the storage unit, it will be demonstrated that dangerous waste has not been left onsite at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or environmentally is impracticable, the interim status closure plan will be modified to address required postclosure activities. WESF stores cesium and strontium encapsulated salts. The encapsulated salts are stored in the pool cells or process cells located within 225B Facility. The dangerous waste is contained within a double containment system to preclude spills to the environment. In the unlikely event that a waste spill does occur outside the capsules, operating methods and administrative controls require that waste spills be cleaned up promptly and completely, and a notation made in the operating record. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

  15. H.A.R. 11-265 - Hazardous Management: Interim Status Standard...

    Open Energy Info (EERE)

    Reference LibraryAdd to library Legal Document- RegulationRegulation: H.A.R. 11-265 - Hazardous Management: Interim Status Standard for Owners and OperatorsLegal Abstract The...

  16. TO: Deans, Directors and Department Heads FROM: Charles Eaton, Interim Controller and Director of Accounting

    E-Print Network [OSTI]

    Holsinger, Kent

    TO: Deans, Directors and Department Heads FROM: Charles Eaton, Interim Controller and Director in the current fiscal year. Purchase Requisitions: Purchases under $10,000 (Includes Corporate Express) June 11

  17. Basis for Interim Operation for the K-Reactor in Cold Standby

    SciTech Connect (OSTI)

    Shedrow, B.

    1998-10-19T23:59:59.000Z

    The Basis for Interim Operation (BIO) document for K Reactor in Cold Standby and the L- and P-Reactor Disassembly Basins was prepared in accordance with the draft DOE standard for BIO preparation (dated October 26, 1993).

  18. Conceptual design statement of work for the immobilized low-activity waste interim storage facility project

    SciTech Connect (OSTI)

    Carlson, T.A., Fluor Daniel Hanford

    1997-02-06T23:59:59.000Z

    The Immobilized Low-Activity Waste Interim Storage subproject will provide storage capacity for immobilized low-activity waste product sold to the U.S. Department of Energy by the privatization contractor. This statement of work describes the work scope (encompassing definition of new installations and retrofit modifications to four existing grout vaults), to be performed by the Architect-Engineer, in preparation of a conceptual design for the Immobilized Low-Activity Waste Interim Storage Facility.

  19. Calculating Energy and Demand Retrofit Savings for Victoria High School: Interim Report

    E-Print Network [OSTI]

    Liu, Y.; Reddy, T. A.; Katipamula, S.; Claridge, D. E.

    1992-01-01T23:59:59.000Z

    ESL-TR-92/12-03 Calculating Energy and Demand Retrofit Savings For Victoria High School Yue Liu, T. Agami Reddy, S. Katipamula and David E. Claridge. Interim Report Energy Systems Laboratory Texas A&M University College Station, TX 77843 December... 1992 Calculating Energy and Demand Retrofit Savings For Victoria High School Yue Liu, T. Agami Reddy, S. Katipamula and David E. Claridge. Interim Report Energy Systems Laboratory Texas A&M University College Station, TX 77843 December 1992 Abstract...

  20. Evaluating state markets for residential wind systems: Results from an economic and policy analysis tool

    SciTech Connect (OSTI)

    Edwards, Jennifer L.; Wiser, Ryan; Bolinger, Mark; Forsyth, Trudy

    2004-12-01T23:59:59.000Z

    The market for small wind systems in the United States, often defined as systems less than or equal to 100 kW that produce power on the customer side of the meter, is small but growing steadily. The installed capacity of domestic small wind systems in 2002 was reportedly 15-18 MW, though the market is estimated to be growing by as much as 40 percent annually (AWEA, 2002). This growth is driven in part by recent technology advancements and cost improvements and, perhaps more importantly, by favorable policy incentives targeted at small wind systems that are offered in several states. Currently, over half of all states have incentive policies for which residential small wind installations are eligible. These incentives range from low-interest loan programs and various forms of tax advantages to cash rebates that cover as much as 60 percent of the total system cost for turbines 10 kW or smaller installed in residential applications. Most of these incentives were developed to support a ran ge of emerging renewable technologies (most notably photovoltaic systems), and were therefore not specifically designed with small wind systems in mind. As such, the question remains as to which incentive types provide the greatest benefit to small wind systems, and how states might appropriately set the level and type of incentives in the future. Furthermore, given differences in incentive types and levels across states, as well as variations in retail electricity rates and other relevant factors, it is not immediately obvious which states offer the most promising markets for small wind turbine manufacturers and installers, as well as potential residential system owners. This paper presents results from a Berkeley Lab analysis of the impact of existing and proposed state and federal incentives on the economics of grid-connected, residential small wind systems. Berkeley Lab has designed the Small Wind Analysis Tool (SWAT) to compare system economics under current incentive structures a cross all 50 states. SWAT reports three metrics to characterize residential wind economics in each state and wind resource class: (1) Break-Even Turnkey Cost (BTC): The BTC is defined as the aggregate installed system cost that would balance total customer payments and revenue over the life of the system, allowing the customer to ''break-even'' while earning a specified rate of return on the small wind ''investment.'' (2) Simple Payback (SP): The SP is the number of years it takes a customer to recoup a cash payment for a wind system and all associated costs, assuming zero discount on future revenue and payments (i.e., ignoring the time value of money). (3) Levelized Cost of Energy (LCOE): The LCOE is the levelized cost of generating a kWh of electricity over the lifetime of the system, and is calculated assuming a cash purchase for the small wind system and a 5.5 percent real discount rate. This paper presents SWAT results for a 10 kW wind turbine and turbine power production is based on a Bergey Excel system. These results are not directly applicable to turbines with different power curves and rated outputs, especially given the fact that many state incentives are set as a fixed dollar amount, and the dollar per Watt amount will vary based on the total rated turbine capacity.

  1. Cast Stone Oxidation Front Evaluation: Preliminary Results For Samples Exposed To Moist Air

    SciTech Connect (OSTI)

    Langton, C. A.; Almond, P. M.

    2013-11-26T23:59:59.000Z

    The rate of oxidation is important to the long-term performance of reducing salt waste forms because the solubility of some contaminants, e.g., technetium, is a function of oxidation state. TcO{sub 4}{sup ?} in the salt solution is reduced to Tc(IV) and has been shown to react with ingredients in the waste form to precipitate low solubility sulfide and/or oxide phases. Upon exposure to oxygen, the compounds containing Tc(IV) oxidize to the pertechnetate ion, Tc(VII)O{sub 4}{sup ?}, which is very soluble. Consequently the rate of technetium oxidation front advancement into a monolith and the technetium leaching profile as a function of depth from an exposed surface are important to waste form performance and ground water concentration predictions. An approach for measuring contaminant oxidation rate (effective contaminant specific oxidation rate) based on leaching of select contaminants of concern is described in this report. In addition, the relationship between reduction capacity and contaminant oxidation is addressed. Chromate (Cr(VI) was used as a non-radioactive surrogate for pertechnetate, Tc(VII), in Cast Stone samples prepared with 5 M Simulant. Cast Stone spiked with pertechnetate was also prepared and tested. Depth discrete subsamples spiked with Cr were cut from Cast Stone exposed to Savannah River Site (SRS) outdoor ambient temperature fluctuations and moist air. Depth discrete subsamples spiked with Tc-99 were cut from Cast Stone exposed to laboratory ambient temperature fluctuations and moist air. Similar conditions are expected to be encountered in the Cast Stone curing container. The leachability of Cr and Tc-99 and the reduction capacities, measured by the Angus-Glasser method, were determined for each subsample as a function of depth from the exposed surface. The results obtained to date were focused on continued method development and are preliminary and apply to the sample composition and curing / exposure conditions described in this report. The Cr oxidation front (depth to which soluble Cr was detected) for the Cast Stone sample exposed for 68 days to ambient outdoor temperatures and humid air (total age of sample was 131 days) was determined to be about 35 mm below the top sample surface exposed. The Tc oxidation front, depth at which Tc was insoluble, was not determined. Interpretation of the results indicates that the oxidation front is at least 38 mm below the exposed surface. The sample used for this measurement was exposed to ambient laboratory conditions and humid air for 50 days. The total age of the sample was 98 days. Technetium appears to be more easily oxidized than Cr in the Cast Stone matrix. The oxidized forms of Tc and Cr are soluble and therefore leachable. Longer exposure times are required for both the Cr and Tc spiked samples to better interpret the rate of oxidation. Tc spiked subsamples need to be taken further from the exposed surface to better define and interpret the leachable Tc profile. Finally Tc(VII) reduction to Tc(IV) appears to occur relatively fast. Results demonstrated that about 95 percent of the Tc(VII) was reduced to Tc(IV) during the setting and very early stage setting for a Cast Stone sample cured 10 days. Additional testing at longer curing times is required to determine whether additional time is required to reduce 100 % of the Tc(VII) in Cast Stone or whether the Tc loading exceeded the ability of the waste form to reduce 100 % of the Tc(VII). Additional testing is required for samples cured for longer times. Depth discrete subsampling in a nitrogen glove box is also required to determine whether the 5 percent Tc extracted from the subsamples was the result of the sampling process which took place in air. Reduction capacity measurements (per the Angus-Glasser method) performed on depth discrete samples could not be correlated with the amount of chromium or technetium leached from the depth discrete subsamples or with the oxidation front inferred from soluble chromium and technetium (i.e., effective Cr and Tc oxidation fronts). Residual reduction capacity

  2. Interim test methods and procedures for determining the performance of small photovoltaic systems

    SciTech Connect (OSTI)

    McNutt, P.; Kroposki, B.; Hansen, R.; DeBlasio, R.

    1998-07-01T23:59:59.000Z

    This document provides test methods and procedures for determining the performance of small stand-alone and utility-grid connected PV systems. The procedures in this document provide a common approach for evaluating whether a given PV system is suitable to perform the function it was designed and manufactured to accomplish and meet the application load. This test document fills a testing void and provides the catalyst and focus for establishing the technical foundation and bridging the institutional barriers needed to reduce uncertainty that a system`s performance will be what its designers and builders claim. The need for this document was recently made more apparent with the initiation of a PV Global Approval Program (PVGAP) at the international level and is in response to concerns that PV systems being fielded must meet performance standards and that these standards include system-level performance type tests. The title of these test procedures is prefaced with the word interim because experience in using the procedures is needed before a consensus standard is developed and accepted by the PV community through its activities with the IEEE Standards Coordinating Committee 21 (SCC21) and International Electrotechnical Commission Technical Committee 82 (IEC TC82) national and international standards-making bodies. Both entities have initiated projects to develop test standards and will need the technical basis and validation of test procedures such as those presented in this document before a consensus is achieved by the PV community.

  3. RH-TRU Waste Shipments from Battelle Columbus Laboratories to the Hanford Nuclear Facility for Interim Storage

    SciTech Connect (OSTI)

    Eide, J.; Baillieul, T. A.; Biedscheid, J.; Forrester, T,; McMillan, B.; Shrader, T.; Richterich, L.

    2003-02-26T23:59:59.000Z

    Battelle Columbus Laboratories (BCL), located in Columbus, Ohio, must complete decontamination and decommissioning (D&D) activities for nuclear research buildings and grounds by 2006, as directed by Congress. Most of the resulting waste (approximately 27 cubic meters [m3]) is remote-handled (RH) transuranic (TRU) waste destined for disposal at the Waste Isolation Pilot Plant (WIPP). The BCL, under a contract to the U.S. Department of Energy (DOE) Ohio Field Office, has initiated a plan to ship the TRU waste to the DOE Hanford Nuclear Facility (Hanford) for interim storage pending the authorization of WIPP for the permanent disposal of RH-TRU waste. The first of the BCL RH-TRU waste shipments was successfully completed on December 18, 2002. This BCL shipment of one fully loaded 10-160B Cask was the first shipment of RH-TRU waste in several years. Its successful completion required a complex effort entailing coordination between different contractors and federal agencies to establish necessary supporting agreements. This paper discusses the agreements and funding mechanisms used in support of the BCL shipments of TRU waste to Hanford for interim storage. In addition, this paper presents a summary of the efforts completed to demonstrate the effectiveness of the 10-160B Cask system. Lessons learned during this process are discussed and may be applicable to other TRU waste site shipment plans.

  4. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

  5. Surveillance program for WWER-440/Type 213 reactor pressure vessels -- Standard program, re-evaluation of results, supplementary program

    SciTech Connect (OSTI)

    Brumovsky, M.; Novosad, P.; Zdarek, J. [Nuclear Research Inst. Rez plc (Czech Republic)

    1996-12-31T23:59:59.000Z

    Irradiation embrittlement of the reactor pressure vessel beltline materials of WWER-440/Type 213 reactors is monitored by a material irradiation surveillance program. Due to the high lead factor, the duration of the standard surveillance program is only five years, after which no further surveillance samples remain in the reactor. The large variation and uncertainty in neutron flux over the irradiated materials produce significant scatter in mechanical properties and necessitate a re-evaluation of results using gamma scanning, specimen reconstitution and recalculation. In order to provide information on the impact of changes in plant operation during later years a supplementary surveillance program has been devised.

  6. National Ignition Facility Cryogenic Target Systems Interim Management Plan

    SciTech Connect (OSTI)

    Warner, B

    2002-04-25T23:59:59.000Z

    Restricted availability of funding has had an adverse impact, unforeseen at the time of the original decision to projectize the National Ignition Facility (NIF) Cryogenic Target Handling Systems (NCTS) Program, on the planning and initiation of these efforts. The purpose of this document is to provide an interim project management plan describing the organizational structure and management processes currently in place for NCTS. Preparation of a Program Execution Plan (PEP) for NCTS has been initiated, and a current draft is provided as Attachment 1 to this document. The National Ignition Facility is a multi-megajoule laser facility being constructed at Lawrence Livermore National Laboratory (LLNL) by the National Nuclear Security Administration (NNSA) in the Department of Energy (DOE). Its primary mission is to support the Stockpile Stewardship Program (SSP) by performing experiments studying weapons physics, including fusion ignition. NIF also supports the missions of weapons effects, inertial fusion energy, and basic science in high-energy-density physics. NIF will be operated by LLNL under contract to the University of California (UC) as a national user facility. NIF is a low-hazard, radiological facility, and its operation will meet all applicable federal, state, and local Environmental Safety & Health (ES&H) requirements. The NCTS Interim Management Plan provides a summary of primary design criteria and functional requirements, current organizational structure, tracking and reporting procedures, and current planning estimates of project scope, cost, and schedule. The NIF Director controls the NIF Cryogenic Target Systems Interim Management Plan. Overall scope content and execution schedules for the High Energy Density Physics Campaign (SSP Campaign 10) are currently undergoing rebaselining and will be brought into alignment with resources expected to be available throughout the NNSA Future Years National Security Plan (FYNSP). The revised schedule for delivering this system will be decided at the national level, based on experiment campaign requirement dates that will be derived through this process. The current milestone date for achieving indirect-drive ignition on the NIF is December 2010. Maintaining this milestone requires that the cryogenic systems be complete and available for fielding experiments early enough that the planned experimental campaigns leading up to ignition can be carried out. The capability of performing non-ignition cryogenic experiments is currently required by March 2006, when the NIF's first cluster of beams is operational. Plans for cryogenic and non-cryogenic experiments on the NIF are contained in NNSA's Campaign 10 Program Plans for Ignition (MTE 10.1) and High Energy Density Sciences (MTE 10.2). As described in this document, the NCTS Program Manager is responsible for managing NIF Cryogenic Target Systems development, engineering, and deployment. Through the NIF Director, the NCTS Program Manager will put in place an appropriate Program Execution Plan (draft attached) at a later time consistent with the maturing and funding these efforts. The PEP will describe management methods for carrying out these activities.

  7. Hazard Ranking System evaluation of CERCLA (Comprehensive Environmental Response, Compensation, and Liability Act) inactive waste sites at Hanford: Volume 1, Evaluation methods and results

    SciTech Connect (OSTI)

    Stenner, R.D.; Cramer, K.H.; Higley, K.A.; Jette, S.J.; Lamar, D.A.; McLaughlin, T.J.; Sherwood, D.R.; Van Houten, N.C.

    1988-10-01T23:59:59.000Z

    The purpose of this report is to formally document the individual site Hazard Ranking System (HRS) evaluations conducted as part of the preliminary assessment/site inspection (PA/SI) activities at the US Department of Energy (DOE) Hanford Site. These activities were carried out pursuant to the DOE orders that describe the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Program addressing the cleanup of inactive waste sites. These orders incorporate the US Environmental Protection Agency methodology, which is based on the Superfund Amendments and Reauthorization Act of 1986 (SARA). The methodology includes six parts: PA/SI, remedial investigation/feasibility study, record of decision, design and implementation of remedial action, operation and monitoring, and verification monitoring. Volume 1 of this report discusses the CERCLA inactive waste-site evaluation process, assumptions, and results of the HRS methodology employed. Volume 2 presents the data on the individual CERCLA engineered-facility sites at Hanford, as contained in the Hanford Inactive Site Surveillance (HISS) Data Base. Volume 3 presents the data on the individual CERCLA unplanned-release sites at Hanford, as contained in the HISS Data Base. 34 refs., 43 figs., 47 tabs.

  8. Large Scale Duty Cycle (LSDC) Project: Tractive Energy Analysis Methodology and Results from Long-Haul Truck Drive Cycle Evaluations

    SciTech Connect (OSTI)

    LaClair, Tim J [ORNL

    2011-05-01T23:59:59.000Z

    This report addresses the approach that will be used in the Large Scale Duty Cycle (LSDC) project to evaluate the fuel savings potential of various truck efficiency technologies. The methods and equations used for performing the tractive energy evaluations are presented and the calculation approach is described. Several representative results for individual duty cycle segments are presented to demonstrate the approach and the significance of this analysis for the project. The report is divided into four sections, including an initial brief overview of the LSDC project and its current status. In the second section of the report, the concepts that form the basis of the analysis are presented through a discussion of basic principles pertaining to tractive energy and the role of tractive energy in relation to other losses on the vehicle. In the third section, the approach used for the analysis is formalized and the equations used in the analysis are presented. In the fourth section, results from the analysis for a set of individual duty cycle measurements are presented and different types of drive cycles are discussed relative to the fuel savings potential that specific technologies could bring if these drive cycles were representative of the use of a given vehicle or trucking application. Additionally, the calculation of vehicle mass from measured torque and speed data is presented and the accuracy of the approach is demonstrated.

  9. Hazelwood Interim Storage Site environmental report for calendar year 1992, 9200 Latty Avenue, Hazelwood, Missouri

    SciTech Connect (OSTI)

    Not Available

    1993-05-01T23:59:59.000Z

    This report describes the environmental surveillance program at the Hazelwood Interim storage Site (HISS) and surrounding area, provides the results for 1992, and discusses applicable environmental standards and requirements with which the results were compared. HISS is located in eastern Missouri in the City of Hazelwood (St. Louis County) and occupies approximately 2.2 ha (5.5 acres). Environmental monitoring of HISS began in 1984 when the site was assigned to the US Department of Energy (DOE) as part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Development Appropriations Act. DOE placed responsibility for HISS under the Formerly Utilized Sites Remedial Action Program (FUSRAP), which was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. In 1992 there were no environmental occurrences or unplanned contaminant releases as defined in DOE requirements and in the Superfund Amendment and Reauthorization Act (SARA) Title III of CERCLA.

  10. Hazelwood Interim Storage Site environmental surveillance report for calendar year 1993

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    This report summarizes the results of environmental surveillance activities conducted at the Hazelwood Interim Storage Site (HISS) during calendar year 1993. It includes an overview of site operations, the basis for monitoring for radioactive and non-radioactive parameters, summaries of environmental program at HISS, a summary of the results, and the calculated hypothetical radiation dose to the offsite population. Environmental surveillance activities were conducted in accordance with the site environmental monitoring plan, which describes the rationale and design criteria for the surveillance program, the frequency of sampling and analysis, specific sampling and analysis procedures, and quality assurance requirements. The US Department of Energy (DOE) began environmental monitoring of HISS in 1984, when the site was assigned to DOE by Congress through the energy and Water Development Appropriations Act and subsequent to DOE`s Formerly Utilized Sites Remediation Action Program (FUSRAP). Contamination at HISS originated from uranium processing work conducted at Mallinckrodt Chemical Works at the St. Louis Downtown Site (SLDS) from 1942 through 1957.

  11. Safe Advantage on Dry Interim Spent Nuclear Fuel Storage

    SciTech Connect (OSTI)

    Romanato, L.S. [Centro Tecnologico da Marinha em S.Paulo, Brazilian Navy Technological Center, Sao Paulo (Brazil)

    2008-07-01T23:59:59.000Z

    This paper aims to present the advantages of dry cask storage in comparison with the wet storage (cooling water pools) for SNF. When the nuclear fuel is removed from the core reactor, it is moved to a storage unit and it wait for a final destination. Generally, the spent nuclear fuel (SNF) remains inside water pools within the reactors facility for the radioactive activity decay. After some period of time in pools, SNF can be sent to a definitive deposition in a geological repository and handled as radioactive waste or to reprocessing facilities, or still, wait for a future solution. Meanwhile, SNF remains stored for a period of time in dry or wet facilities, depending on the method adopted by the nuclear power plant or other plans of the country. Interim storage, up to 20 years ago, was exclusively wet and if the nuclear facility had to be decommissioned another storage solution had to be found. At the present time, after a preliminary cooling of the SNF elements inside the water pool, the elements can be stored in dry facilities. This kind of storage does not need complex radiation monitoring and it is safer then wet one. Casks, either concrete or metallic, are safer, especially on occurrence of earthquakes, like that occurred at Kashiwazaki-Kariwa nuclear power plant, in Japan on July 16, 2007. (authors)

  12. DOUBLE TRACKS Test Site interim corrective action plan

    SciTech Connect (OSTI)

    NONE

    1996-06-01T23:59:59.000Z

    The DOUBLE TRACKS site is located on Range 71 north of the Nellis Air Force Range, northwest of the Nevada Test Site (NTS). DOUBLE TRACKS was the first of four experiments that constituted Operation ROLLER COASTER. On May 15, 1963, weapons-grade plutonium and depleted uranium were dispersed using 54 kilograms of trinitrotoluene (TNT) explosive. The explosion occurred in the open, 0.3 m above the steel plate. No fission yield was detected from the test, and the total amount of plutonium deposited on the ground surface was estimated to be between 980 and 1,600 grams. The test device was composed primarily of uranium-238 and plutonium-239. The mass ratio of uranium to plutonium was 4.35. The objective of the corrective action is to reduce the potential risk to human health and the environment and to demonstrate technically viable and cost-effective excavation, transportation, and disposal. To achieve these objectives, Bechtel Nevada (BN) will remove soil with a total transuranic activity greater then 200 pCI/g, containerize the soil in ``supersacks,`` transport the filled ``supersacks`` to the NTS, and dispose of them in the Area 3 Radioactive Waste Management Site. During this interim corrective action, BN will also conduct a limited demonstration of an alternative method for excavation of radioactive near-surface soil contamination.

  13. Interim Activities at Corrective Action Unit 114: Area 25 EMAD Facility, Nevada National Security Site, Nevada, for Fiscal Years 2012 and 2013

    SciTech Connect (OSTI)

    Silvas, A J

    2013-10-24T23:59:59.000Z

    This letter report documents interim activities that have been completed at CAU 114 in fiscal years 2012 and 2013.

  14. An Experimental Evaluation of HVAC-Grade Carbon-Dioxide Sensors: Part 3, Humidity, Temperature, and Pressure Sensitivity Test Results

    SciTech Connect (OSTI)

    Shrestha, Som S [ORNL; Maxwell, Dr. Gregory [Iowa State University

    2010-01-01T23:59:59.000Z

    This is the third paper in a four-part series reporting on the test and evaluation of typical carbon-dioxide sensors used in building HVAC applications. Fifteen models of NDIR HVAC-grade CO2 sensors were tested and evaluated to determine the humidity, temperature, and pressure sensitivity of the sensors. This paper reports the performance of the sensors at various relative humidity, temperature, and pressure levels common to building HVAC applications and provides a comparison with manufacturer specifications. Among the 15 models tested, eight models have a single-lamp, single-wavelength configuration, four models have a dual-lamp, single-wavelength configuration, and three models have a single-lamp, dual-wavelength configuration. The sensors were tested in a chamber specifically fabricated for this research. A description of the apparatus and the method of test are described in Part 1 (Shrestha and Maxwell 2009). The test result showed a wide variation in humidity, temperature, and pressure sensitivity of CO2 sensors among manufacturers. In some cases, significant variations in sensor performance exist between sensors of the same model. Even the natural variation in relative humidity could significantly vary readings of some CO2 sensor readings. The effects of temperature and pressure variation on NDIR CO2 sensors are unavoidable without an algorithm to compensate for the changes. For the range of temperature and pressure variation in an air-conditioned space, the effect of pressure variation is more significant compared to the effect of temperature variation.

  15. Hydrogeology of the 200 Areas low-level burial grounds: An interim report: Volume 1, Text

    SciTech Connect (OSTI)

    Last, G.V.; Bjornstad, B.N.; Bergeron, M.P.; Wallace, D.W.; Newcomer, D.R.; Schramke, J.A.; Chamness, M.A.; Cline, C.S.; Airhart, S.P.; Wilbur, J.S.

    1989-01-01T23:59:59.000Z

    This report presents information derived from the installation of 35 ground-water monitoring wells around six low-level radioactive/hazardous waste burial grounds located in the 200 Areas of the Hanford Site in southeastern Washington State. This information was collected between May 20, 1987 and August 1, 1988. The contents of this report have been divided into two volumes. This volume contains the main text. Volume 2 contains the appendixes, including data and supporting information that verify content and results found in the main text. This report documents information collected by the Pacific Northwest Laboratory at the request of Westinghouse Hanford Company. Presented in this report are the preliminary interpretations of the hydrogeologic environment of six low-level burial grounds, which comprise four waste management areas (WMAs) located in the 200 Areas of the Hanford Site. This information and its accompanying interpretations were derived from sampling and testing activities associated with the construction of 35 ground-water monitoring wells as well as a multitude of previously existing boreholes. The new monitoring wells were installed as part of a ground-water monitoring program initiated in 1986. This ground-water monitoring program is based on requirements for interim status facilities in compliance with the Resource Conservation and Recovery Act (1976).

  16. Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington

    SciTech Connect (OSTI)

    Not Available

    1994-07-01T23:59:59.000Z

    This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation,`` of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues.

  17. National climate change action plans: Interim report for developing and transition countries

    SciTech Connect (OSTI)

    Benioff, R.; Ness, E.; Hirst, J. [eds.

    1997-10-01T23:59:59.000Z

    Under its Support for National Action Plans (SNAP) initiative, the U.S. Country Studies Program is providing financial and technical assistance to 18 countries for the development of climate change action plans. Although most of the countries have not yet completed their plans, the important lessons learned thus far are valuable and should be shared with other countries and international institutions that have an interest in the process of action plan development. This interim report describes the experience of 11 countries that are the furthest along in their planning activity and who have offered to share their results to date with the larger community of interested nations. These action plans delineate specific mitigation and adaptation measures that the countries will implement and integrate into their ongoing development programs. This report focuses on the measures the countries have selected and the methods they used to prepare their action plans. This executive summary presents key lessons and common themes using a structure similar to that used in the individual country chapters.

  18. Online Monitoring Technical Basis and Analysis Framework for Large Power Transformers; Interim Report for FY 2012

    SciTech Connect (OSTI)

    Nancy J. Lybeck; Vivek Agarwal; Binh T. Pham; Heather D. Medema; Kirk Fitzgerald

    2012-09-01T23:59:59.000Z

    The Light Water Reactor Sustainability program at Idaho National Laboratory (INL) is actively conducting research to develop and demonstrate online monitoring (OLM) capabilities for active components in existing Nuclear Power Plants. A pilot project is currently underway to apply OLM to Generator Step-Up Transformers (GSUs) and Emergency Diesel Generators (EDGs). INL and the Electric Power Research Institute (EPRI) are working jointly to implement the pilot project. The EPRI Fleet-Wide Prognostic and Health Management (FW-PHM) Software Suite will be used to implement monitoring in conjunction with utility partners: the Shearon Harris Nuclear Generating Station (owned by Duke Energy for GSUs, and Braidwood Generating Station (owned by Exelon Corporation) for EDGs. This report presents monitoring techniques, fault signatures, and diagnostic and prognostic models for GSUs. GSUs are main transformers that are directly connected to generators, stepping up the voltage from the generator output voltage to the highest transmission voltages for supplying electricity to the transmission grid. Technical experts from Shearon Harris are assisting INL and EPRI in identifying critical faults and defining fault signatures associated with each fault. The resulting diagnostic models will be implemented in the FW-PHM Software Suite and tested using data from Shearon-Harris. Parallel research on EDGs is being conducted, and will be reported in an interim report during the first quarter of fiscal year 2013.

  19. Online Monitoring Technical Basis and Analysis Framework for Emergency Diesel Generators - Interim Report for FY 2013

    SciTech Connect (OSTI)

    Binh T. Pham; Nancy J. Lybeck; Vivek Agarwal

    2012-12-01T23:59:59.000Z

    The Light Water Reactor Sustainability program at Idaho National Laboratory is actively conducting research to develop and demonstrate online monitoring capabilities for active components in existing nuclear power plants. Idaho National Laboratory and the Electric Power Research Institute are working jointly to implement a pilot project to apply these capabilities to emergency diesel generators and generator step-up transformers. The Electric Power Research Institute Fleet-Wide Prognostic and Health Management Software Suite will be used to implement monitoring in conjunction with utility partners: Braidwood Generating Station (owned by Exelon Corporation) for emergency diesel generators, and Shearon Harris Nuclear Generating Station (owned by Duke Energy Progress) for generator step-up transformers. This report presents monitoring techniques, fault signatures, and diagnostic and prognostic models for emergency diesel generators. Emergency diesel generators provide backup power to the nuclear power plant, allowing operation of essential equipment such as pumps in the emergency core coolant system during catastrophic events, including loss of offsite power. Technical experts from Braidwood are assisting Idaho National Laboratory and Electric Power Research Institute in identifying critical faults and defining fault signatures associated with each fault. The resulting diagnostic models will be implemented in the Fleet-Wide Prognostic and Health Management Software Suite and tested using data from Braidwood. Parallel research on generator step-up transformers was summarized in an interim report during the fourth quarter of fiscal year 2012.

  20. Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility

    SciTech Connect (OSTI)

    Bonnema, Bruce Edward

    2001-09-01T23:59:59.000Z

    This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energy’s Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

  1. E-Area Performance Assessment Interim Measures Assessment FY2005

    SciTech Connect (OSTI)

    Stallings, M

    2006-01-31T23:59:59.000Z

    After major changes to the limits for various disposal units of the E-Area Low Level Waste Facility (ELLWF) last year, no major changes have been made during FY2005. A Special Analysis was completed which removes the air pathway {sup 14}C limit from the Intermediate Level Vault (ILV). This analysis will allow the disposal of reactor moderator deionizers which previously had no pathway to disposal. Several studies have also been completed providing groundwater transport input for future special analyses. During the past year, since Slit Trenches No.1 and No.2 were nearing volumetric capacity, they were operationally closed under a preliminary closure analysis. This analysis was performed using as-disposed conditions and data and showed that concrete rubble from the demolition of 232-F was acceptable for disposal in the STs even though the latest special analysis for the STs had reduced the tritium limits so that the inventory in the rubble exceeded limits. A number of special studies are planned during the next years; perhaps the largest of these will be revision of the Performance Assessment (PA) for the ELLWF. The revision will be accomplished by incorporating special analyses performed since the last PA revision as well as revising analyses to include new data. Projected impacts on disposal limits of more recent studies have been estimated. No interim measures will be applied during this year. However, it is being recommended that tritium disposals to the Components-in-Grout (CIG) Trenches be suspended until a limited Special Analysis (SA) currently in progress is completed. This SA will give recommendations for optimum placement of tritiated D-Area tower waste. Further recommendations for tritiated waste placement in the CIG Trenches will be given in the upcoming PA revision.

  2. Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 2: Technical basis and discussion of results

    SciTech Connect (OSTI)

    Waters, R.D.; Gruebel, M.M.; Hospelhorn, M.B. [and others

    1996-03-01T23:59:59.000Z

    A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 first describes the screening process used to determine the sites to be considered in the PEs. This volume then provides the technical details of the methodology for conducting the performance evaluations. It also provides a comparison and analysis of the overall results for all sites that were evaluated. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site.

  3. Long-Term Results from Evaluation of Advanced New Construction Packages in Test Homes: Lake Elsinore, California

    SciTech Connect (OSTI)

    Stecher, D.; Brozyna, K.

    2013-08-01T23:59:59.000Z

    This report presents the long-term evaluation results from a hot-dry climate project that examines the room-to-room temperature conditions that exist in a high performance envelope, the performance of a simplified air distribution system, and a comparison of modeled energy performance with measured energy use. The project, a prototype house built by K. Hovnanian Homes' Ontario Group, is located in Lake Elsinore, Riverside County, California, and achieves a 50% level of whole house source energy savings with respect to the Building America (BA) Benchmark Definition 2009 (Hendron and Engebrecht 2010). Temperature measurements in three rooms indicate that the temperature difference between the measured locations and the thermostat were within recommendations 90.3% of the time in heating mode and 99.3% of the time in cooling mode. The air distribution system is operating efficiently with average delivered temperatures adequate to facilitate proper heating and cooling and only minor average temperature differences observed between the system's plenum and farthest register. Monitored energy use results for the house indicate that it is using less energy than predicted from modeling. A breakdown of energy use according to end use determined little agreement between comparable values.

  4. Technical considerations related to interim source-term assumptions for emergency planning and equipment qualification. [PWR; BWR

    SciTech Connect (OSTI)

    Niemczyk, S.J.; McDowell-Boyer, L.M.

    1982-09-01T23:59:59.000Z

    The source terms recommended in the current regulatory guidance for many considerations of light water reactor (LWR) accidents were developed a number of years ago when understandings of many of the phenomena pertinent to source term estimation were relatively primitive. The purpose of the work presented here was to develop more realistic source term assumptions which could be used for interim regulatory purposes for two specific considerations, namely, equipment qualification and emergency planning. The overall approach taken was to adopt assumptions and models previously proposed for various aspects of source term estimation and to modify those assumptions and models to reflect recently gained insights into, and data describing, the release and transport of radionuclides during and after LWR accidents. To obtain illustrative estimates of the magnitudes of the source terms, the results of previous calculations employing the adopted assumptions and models were utilized and were modified to account for the effects of the recent insights and data.

  5. 1988 Federal Interim Storage Fee study: A technical and economic analysis

    SciTech Connect (OSTI)

    Not Available

    1988-11-01T23:59:59.000Z

    This document is the latest in a series of reports that are published annually by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). The information in this report, which was prepared by E.R. Johnson Associates, Inc., under subcontract to PNL, will be used by the DOE to establish a payment schedule for interim storage of spent nuclear fuel under the Federal Interim Storage (FIS) Program. The FIS Program was mandated by the Nuclear Waste Policy Act of 1982. The information will be used to establish the schedule of charges for FIS services for the year commencing January 1, 1989. 13 refs.

  6. Comparison of cask and drywell storage concepts for a monitored retrievable storage/interim storage system

    SciTech Connect (OSTI)

    Rasmussen, D.E.

    1982-12-01T23:59:59.000Z

    The Department of Energy, through its Richland Operations Office is evaluating the feasibility, timing, and cost of providing a federal capability for storing the spent fuel, high-level wastes, and transuranic wastes that DOE may be obligated by law to manage until permanent waste disposal facilities are available. Three concepts utilizing a monitored retrievable storage/interim storage (MRS/IS) facility have been developed and analyzed. The first concept, co-location with a reprocessing plant, has been developed by staff of Allied General Nuclear Services. the second concept, a stand-alone facility, has been developed by staff of the General Atomic Company. The third concept, co-location with a deep geologic repository, has been developed by the Pacific Northwest Laboratory with the assistance of the Westinghouse Hanford Company and Kaiser Engineers. The objectives of this study are: to develop preconceptual designs for MRS/IS facilities: to examine various issues such as transportation of wastes, licensing of the facilities, and environmental concerns associated with operation of such facilities; and to estimate the life-cycle costs of the facilities when operated in response to a set of scenarios that define the quantities and types of waste requiring storage in specific time periods, generally spanning the years 1989 to 2037. Three scenarios are examined to develop estimates of life-cycle costs for the MRS/IS facilities. In the first scenario, the reprocessing plant is placed in service in 1989 and HLW canisters are stored until a repository is opened in the year 1998. Additional reprocessing plants and repositories are placed in service at intervals as needed to meet the demand. In the second scenario, the reprocessing plants are delayed in starting operations by 10 years, but the repositories open on schedule. In the third scenario, the repositories are delayed 10 years, but the reprocessing plants open on schedule.

  7. Development of Thermal Analysis Capability of Dry Storage Cask for Spend Fuel Interim Storage

    SciTech Connect (OSTI)

    Fu-Kuang Ko; Liang, Thomas K.S.; Chung-Yu Yang [Institute of Nuclear Energy Research P.O. Box 3-3, Longtan, 32500, Taiwan (China)

    2002-07-01T23:59:59.000Z

    As most of the nuclear power plants, on-site spent fuel pools (SFP) of Taiwan's plants were not originally designed with a storage capacity for all the spent fuel generated over the operating life by their reactors. For interim spent fuel storage, dry casks are one of the most reliable measures to on-site store over-filled assemblies from SFPs. The NUHOMS{sup R}-52B System consisting of a canister stored horizontally in a concrete module is selected for thermal evaluation in this paper. The performance of each cask in criticality, radioactive, material and thermal needs to be carefully addressed to ensure its enduring safety. Regarding the thermal features of dry storage casks, three different kinds of heat transfer mechanisms are involved, which include natural convection heat transfer outside and/or inside the canister, radiation heat transfer inside and outside the canister, and conduction heat transfer inside the canister. To analyze the thermal performance of dry storage casks, RELAP5-3D is adopted to calculate the natural air convection and radiation heat transfer outside the canister to the ambient environment, and ANSYS is applied to calculate the internal conduction and radiation heat transfer. During coupling iteration between codes, the heat energy across the canister wall needs to be conserved, and the inner wall temperature of the canister needs to be converged. By the coupling of RELAP5-3D and ANSYS, the temperature distribution within each fuel assembly inside canisters can be calculated and the peaking cladding temperature can be identified. (authors)

  8. Interim report on the Global Design Effort Global International Linear Collider (ILC) R&D

    SciTech Connect (OSTI)

    Harrison, M.

    2011-04-30T23:59:59.000Z

    The International Linear Collider: A Technical Progress Report marks the halfway point towards the Global Design Effort fulfilling its mandate to follow up the ILC Reference Design Report with a more optimised Technical Design Report (TDR) by the end of 2012. The TDR will be based on much of the work reported here and will contain all the elements needed to propose the ILC to collaborating governments, including a technical design and implementation plan that are realistic and have been better optimised for performance, cost and risk. We are on track to develop detailed plans for the ILC, such that once results from the Large Hadron Collider (LHC) at CERN establish the main science goals and parameters of the next machine, we will be in good position to make a strong proposal for this new major global project in particle physics. The two overriding issues for the ILC R&D programme are to demonstrate that the technical requirements for the accelerator are achievable with practical technologies, and that the ambitious physics goals can be addressed by realistic ILC detectors. This GDE interim report documents the impressive progress on the accelerator technologies that can make the ILC a reality. It highlights results of the technological demonstrations that are giving the community increased confidence that we will be ready to proceed with an ILC project following the TDR. The companion detector and physics report document likewise demonstrates how detector designs can meet the ambitious and detailed physics goals set out by the ILC Steering Committee. LHC results will likely affect the requirements for the machine design and the detectors, and we are monitoring that very closely, intending to adapt our design as those results become available.

  9. Evaluation of potential for MSRE spent fuel and flush salt storage and treatment at the INEL

    SciTech Connect (OSTI)

    Ougouag, A.M.; Ostby, P.A.; Nebeker, R.L.

    1996-09-01T23:59:59.000Z

    The potential for interim storage as well as for treatment of the Molten Salt Reactor Experiment spent fuel at INEL has been evaluated. Provided that some minimal packaging and chemical stabilization prerequisites are satisfied, safe interim storage of the spent fuel at the INEL can be achieved in a number of existing or planned facilities. Treatment by calcination in the New Waste Calcining Facility at the INEL can also be a safe, effective, and economical alternative to treatment that would require the construction of a dedicated facility. If storage at the INEL is chosen for the Molten Salt Reactor Experiment (MSRE) spent fuel salts, their transformation to the more stable calcine solid would still be desirable as it would result in a lowering of risks. Treatment in the proposed INEL Remote-Handled Immobilization Facility (RHIF) would result in a waste form that would probably be acceptable for disposal at one of the proposed national repositories. The cost increment imputable to the treatment of the MSRE salts would be a small fraction of the overall capital and operating costs of the facility or the cost of building and operating a dedicated facility. Institutional and legal issues regarding shipments of fuel and waste to the INEL are summarized. The transfer of MSRE spent fuel for interim storage or treatment at the INEL is allowed under existing agreements between the State of idaho and the Department of energy and other agencies of the Federal Government. In contrast, current agreements preclude the transfer into Idaho of any radioactive wastes for storage or disposal within the State of Idaho. This implies that wastes and residues produced from treating the MSRE spent fuel at locations outside Idaho would not be acceptable for storage in Idaho. Present agreements require that all fuel and high-level wastes stored at the INEL, including MSRE spent fuel if received at the INEL, must be moved to a location outside Idaho by the year 2035.

  10. T-TY Tank Farm Interim Surface Barrier Demonstration - Vadose Zone Monitoring FY10 Report

    SciTech Connect (OSTI)

    Zhang, Z. F.; Strickland, Christopher E.; Field, Jim G.; Parker, Danny L.

    2011-01-24T23:59:59.000Z

    The U.S. Department of Energy’s Office of River Protection has constructed interim surface barriers over a portion of the T and TY tank farms as part of the Interim Surface Barrier Demonstration Project. The interim surface barriers (hereafter referred to as the surface barriers or barriers) are designed to minimize the infiltration of precipitation into the soil zones containing radioactive contaminants and minimize the movement of the contaminants. As part of the demonstration effort, vadose zone moisture is being monitored to assess the effectiveness of the barriers at reducing soil moisture. Solar-powered systems were installed to continuously monitor soil water conditions at four locations in the T (i.e., instrument Nests TA, TB, TC, and TD) and the TY (i.e., instrument Nests TYA and TYB) Farms beneath the barriers and outside the barrier footprint as well as site meteorological conditions. Nests TA and TYA are placed in the area outside the barrier footprint and serve as controls, providing subsurface conditions outside the influence of the surface barriers. Nest TB provides subsurface measurements to assess surface-barrier edge effects. Nests TC, TD, and TYB are used to assess changes in soil-moisture conditions beneath the interim surface barriers. Except for occasional times for TC and TD and planned dates for TYB, during FY10, the battery voltage at the TMS and instrument Nests in both T and TY tank farms remained above 12.0 V, denoting that the battery voltages were sufficient for the stations to remain functional. All the HDUs were functioning normally, but some pressure-head values were greater than the upper measurement limit. The values that exceeded the upper limit may indicate wet soil conditions and/or measurement error, but they do not imply a malfunction of the sensors. Similar to FY07 through FY09, in FY10, the soil under natural conditions in the T Farm (Nest TA) was generally recharged during the winter period (October–March), and they discharged during the summer period (April–September). Soil water conditions above about 1.5-m to 2-m depth from all three types of measurements (i.e., CP, NP, and HDU) showed relatively large variation during the seasonal wetting-drying cycle. For the soil below 2-m depth, the seasonal variation of soil water content was relatively small. The construction of the TISB was completed in April 2008. In the soil below the TISB (Nests TC and TD), the CP-measured water content showed that ? at the soil between 0.6-m and 2.3-m depths was stable, indicating no climatic impacts on soil water conditions beneath the barrier. The NP-measured water content in the soil between about 3.4 m (11 ft) and 12.2 m (40 ft) since the completion of the barrier decreased by 0.007 to 0.014 m3 m-3. The HDU-measured soil-water pressure at 1-m, 2-m, and 5-m depths decreased by 0.7 to 2.4 m, indicating soil water drainage at these depths of the soil. In the soil below the edge of the TISB (Nest TB), the CP-measured water content was relatively stable through the year; the NP-measured water content showed that soil water drainage was occurring in the soil between about 3.4 m (11 ft) and 12.2 m (40 ft) but at a slightly smaller magnitude than in Nests TC and TD; the HDU-measurements show that the pressure head changes at Nest TB since the completion of the barrier were generally less than those at TC and TD, but more than those at TA. These results indicate that the TISB is performing as expected by intercepting the meteoric water from infiltrating into the soil, and the soil is becoming drier gradually. The barrier also had some effects on the soil below the barrier edge, but at a reduced magnitude. There was no significant difference in soil-water regime between the two nests in the TY tank farm because the barrier at the TY Farm was just completed one month before the end of the FY.

  11. Low-temperature catalytic gasification of wet industrial wastes. FY 1991--1992 interim report

    SciTech Connect (OSTI)

    Elliott, D.C.; Neuenschwander, G.G.; Hart, T.R.; Phelps, M.R.; Sealock, L.J. Jr.

    1993-07-01T23:59:59.000Z

    A catalytic gasification system operating in a pressurized water environment has been developed and refined at Pacific Northwest Laboratory (PNL) for over 12 years. Initial experiments were aimed at developing kinetics information for steam gasification of biomass in the presence of catalysts. The combined use of alkali and metal catalysts was reported for gasification of biomass and its components at low temperatures (350{degrees}C to 450{degrees}C). From the fundamental research evolved the concept of a pressurized, catalytic gasification system for converting wet biomass feedstocks to fuel gas. Extensive batch reactor testing and limited continuous reactor system (CRS) testing were undertaken in the development of this system under sponsorship of the US Department of Energy. A wide range of biomass feedstocks were tested, and the importance of the nickel metal catalyst was identified. Specific use of this process for treating food processing wastes was also studied. The concept application was further expanded to encompass cleanup of hazardous wastewater streams, and results were reported for batch reactor tests and continuous reactor tests. Ongoing work at PNL focuses on refining the catalyst and scaling the system to long-term industrial needs. The process is licensed as the Thermochemical Environmental Energy System (TEES{reg_sign}) to Onsite*Ofsite, Inc., of Duarte, California. This report is a follow-on to the 1989--90 interim report [Elliott et al. 1991], which reviewed the results of the studies conducted with a fixed-bed, continuous-feed, tubular reactor. The discussion here provides an overview of experiments on the wide range of potential feedstock materials conducted in a batch reactor; development of new catalyst materials; and tests performed in continuous-flow reactors at three scales. The appendices contain the history and background of the process development, as well as more detailed descriptions and results of the recent studies.

  12. Monitoring and Evaluation of the Prototype Surface Collector at Bonneville First Powerhouse in 2000: Synthesis of Results

    SciTech Connect (OSTI)

    Johnson, Gary E.; Carlson, Thomas J.

    2001-06-01T23:59:59.000Z

    This report describes research done to evaluate the Prototype Surface Collector at Bonneville Dam, Powerhouse I, on the Columbia River. The surface collector is being evaluated as a means for bringing downstream migrating salmon and steelhead through the powerhouse while avoiding the turbines. The report describes evaluations conducted by PNNL, National Marine Fisheries Service, and various contractors using radio telemetry, hydroacoustics, and computational fluid dynamics models. The evaluation will provide information to the U.S. Army Corps of Engineers for their 2001 decision on whether to use surface flow bypass or extended-length submersible bar screens for long-term smolt passage at Bonneville Dam.

  13. Additional EIPC Study Analysis: Interim Report on High Priority Topics

    SciTech Connect (OSTI)

    Hadley, Stanton W [ORNL

    2013-11-01T23:59:59.000Z

    Between 2010 and 2012 the Eastern Interconnection Planning Collaborative (EIPC) conducted a major long-term resource and transmission study of the Eastern Interconnection (EI). With guidance from a Stakeholder Steering Committee (SSC) that included representatives from the Eastern Interconnection States Planning Council (EISPC) among others, the project was conducted in two phases. Phase 1 involved a long-term capacity expansion analysis that involved creation of eight major futures plus 72 sensitivities. Three scenarios were selected for more extensive transmission- focused evaluation in Phase 2. Five power flow analyses, nine production cost model runs (including six sensitivities), and three capital cost estimations were developed during this second phase. The results from Phase 1 and 2 provided a wealth of data that could be examined further to address energy-related questions. A list of 13 topics was developed for further analysis; this paper discusses the first five.

  14. Interim Report: Air-Cooled Condensers for Next Generation Geothermal Power Plants Improved Binary Cycle Performance

    SciTech Connect (OSTI)

    Daniel S. Wendt; Greg L. Mines

    2010-09-01T23:59:59.000Z

    As geothermal resources that are more expensive to develop are utilized for power generation, there will be increased incentive to use more efficient power plants. This is expected to be the case with Enhanced Geothermal System (EGS) resources. These resources will likely require wells drilled to depths greater than encountered with hydrothermal resources, and will have the added costs for stimulation to create the subsurface reservoir. It is postulated that plants generating power from these resources will likely utilize the binary cycle technology where heat is rejected sensibly to the ambient. The consumptive use of a portion of the produced geothermal fluid for evaporative heat rejection in the conventional flash-steam conversion cycle is likely to preclude its use with EGS resources. This will be especially true in those areas where there is a high demand for finite supplies of water. Though they have no consumptive use of water, using air-cooling systems for heat rejection has disadvantages. These systems have higher capital costs, reduced power output (heat is rejected at the higher dry-bulb temperature), increased parasitics (fan power), and greater variability in power generation on both a diurnal and annual basis (larger variation in the dry-bulb temperature). This is an interim report for the task ‘Air-Cooled Condensers in Next- Generation Conversion Systems’. The work performed was specifically aimed at a plant that uses commercially available binary cycle technologies with an EGS resource. Concepts were evaluated that have the potential to increase performance, lower cost, or mitigate the adverse effects of off-design operation. The impact on both cost and performance were determined for the concepts considered, and the scenarios identified where a particular concept is best suited. Most, but not all, of the concepts evaluated are associated with the rejection of heat. This report specifically addresses three of the concepts evaluated: the use of recuperation, the use of turbine reheat, and the non-consumptive use of EGS make-up water to supplement heat rejection

  15. Evaluating the learning effectiveness of using simulations in software project management education: results from a twice replicated experiment

    E-Print Network [OSTI]

    Krivobokova, Tatyana

    Evaluating the learning effectiveness of using simulations in software project management education replicated experiment that evaluates the learning effectiveness of using a process simulation model a System Dynamics simulation model, the control group used the well-known COCOMO model as a predictive tool

  16. Economic Impacts of Reduced Delta Exports Resulting from the Wanger Interim Order for Delta Smelt

    E-Print Network [OSTI]

    Sunding, David L.; Ajami, Newsha K; Hatchett, Steve; Mitchell, David; Zilberman, David

    2009-01-01T23:59:59.000Z

    not available to deal with shortages and water transfers areservice associated with water shortage events. Total Costscost to consumers of a water shortage. 4 LCPSIM optimizes

  17. Results Of Initial Analyses Of The Macrobatch 7 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Washington, A. L. II

    2013-07-08T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Salt (Macro) Batch 7 for the Interim Salt Disposition Program (ISDP) through ARP/MCU. This document reports the initial results of the analyses of samples of Tank 21H. Further results on the chemistry and other tests will be issued in the future. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. Based upon a SRNL settling test, the solids should settle well within the months-long settling period to be employed in Tank 21H. However, SRNL recommends analyzing the solids to provide input to OLI modeling in order to evaluate the impacts of these solids to present and future salt batches.

  18. Interim report spent nuclear fuel retrieval system fuel handling development testing

    SciTech Connect (OSTI)

    Ketner, G.L.; Meeuwsen, P.V.; Potter, J.D.; Smalley, J.T.; Baker, C.P.; Jaquish, W.R.

    1997-06-01T23:59:59.000Z

    Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project at the Hanford Site. The project will retrieve spent nuclear fuel, clean and remove fuel from canisters, repackage fuel into baskets, and load fuel into a multi-canister overpack (MCO) for vacuum drying and interim dry storage. The FRS is required to retrieve basin fuel canisters, clean fuel elements sufficiently of uranium corrosion products (or sludge), empty fuel from canisters, sort debris and scrap from whole elements, and repackage fuel in baskets in preparation for MCO loading. The purpose of fuel handling development testing was to examine the systems ability to accomplish mission activities, optimization of equipment layouts for initial process definition, identification of special needs/tools, verification of required design changes to support performance specification development, and validation of estimated activity times/throughput. The test program was set up to accomplish this purpose through cold development testing using simulated and prototype equipment; cold demonstration testing using vendor expertise and systems; and graphical computer modeling to confirm feasibility and throughput. To test the fuel handling process, a test mockup that represented the process table was fabricated and installed. The test mockup included a Schilling HV series manipulator that was prototypic of the Schilling Hydra manipulator. The process table mockup included the tipping station, sorting area, disassembly and inspection zones, fuel staging areas, and basket loading stations. The test results clearly indicate that the Schilling Hydra arm cannot effectively perform the fuel handling tasks required unless it is attached to some device that can impart vertical translation, azimuth rotation, and X-Y translation. Other test results indicate the importance of camera locations and capabilities, and of the jaw and end effector tool design. 5 refs., 35 figs., 3 tabs.

  19. Interim-status groundwater monitoring plan for the 216-B-63 trench

    SciTech Connect (OSTI)

    Sweeney, M.D.

    1995-02-09T23:59:59.000Z

    This document outlines the groundwater monitoring plan, under RCRA regulations in 40 CFR 265 Subpart F and WAC173-300-400, for the 216-B-63 Trench. This interim status facility is being sampled under detection monitoring criteria and this plan provides current program conditions and requirements.

  20. Biennial Assessment of the Fifth Power Plan Interim Report on Electric Price Forecasts

    E-Print Network [OSTI]

    because natural gas fired electric generating plants are on the margin much of the time in Western marketsBiennial Assessment of the Fifth Power Plan Interim Report on Electric Price Forecasts Electricity prices in the Council's Power Plan are forecast using the AURORATM Electricity Market Model of the entire

  1. Healthy!Zero!Energy!Buildings!(HZEB)!Program! ! ! Interim!Report!on!Cross"Sectional!Study!of!Contaminant!!

    E-Print Network [OSTI]

    1 ! ! Healthy!Zero!Energy!Buildings!(HZEB)!Program­! ! ! Interim!R.!Chan,!Meera!Sidheswaran,!Douglas!Sullivan,!! ! ! Sebastian!Cohn,!William!J.!Fisk!! ! ! ! Environmental!Energy!Technologies!Division! ! ! Indoor,!2012! ! ! ! ! ! ! ! ! ! ! The!research!reported!here!was!supported!by!the!California!Energy!Commission! ! ! Public!Interest!Energy!Research!Program,!Energy

  2. UMBC Policy # III-1.11.02 Page 1 of 4 UMBC INTERIM POLICY ON

    E-Print Network [OSTI]

    Adali, Tulay

    UMBC Policy # III-1.11.02 Page 1 of 4 UMBC INTERIM POLICY ON INDIVIDUAL FINANCIAL CONFLICTS OF INTEREST IN PHS RESEARCH UMBC # III-1.11.02 I. POLICY STATEMENT Externally sponsored research is a vital FOR POLICY UMBC strives for excellence and academic integrity in its research enterprise while also promoting

  3. The development of a management strategy for interim storage and final disposal of nuclear wastes

    SciTech Connect (OSTI)

    Engelmann, H.J.; Popp, F.W. [Deutsche Gesellschaft zum Bau and Betrieb von Endglagern fuer Abfallostofe mbH, Peine (Germany); Arntzen, P.; Botzem, W. [NUKEM GmbH, Alzenau (Germany); Soucek, B. [Czech Power Board, Prague (Czech Republic)

    1993-12-31T23:59:59.000Z

    The overall waste management strategy for alternative routes from reactor to final disposal, including dry interim storage, is discussed. Within the framework of a preliminary structure plan possible technical solutions must be investigated, and with sufficient relevant information available the future progress of the project, can be addressed on the base of a decision analysis.

  4. To: All members of the Trinity College community From: Michael Ratcliffe, Interim Provost

    E-Print Network [OSTI]

    Sokolowski, Marla

    Memo To: All members of the Trinity College community From: Michael Ratcliffe, Interim Provost Re with Trinity College academically as teachers, may be appointed Associates of the College for a term of two to me by email via Cera Maugey (cera@trinity.utoronto.ca) and include the following information

  5. Medical Physics Letter Digital tomosynthesis of the chest for lung nodule detection: Interim

    E-Print Network [OSTI]

    Medical Physics Letter Digital tomosynthesis of the chest for lung nodule detection: Interim tomosynthesis for improving detectability of small lung nodules. Twenty-one patients under- going computed tomography CT to follow up lung nodules were consented and enrolled to receive an additional digital PA chest

  6. Annex D-200 Area Interim Storage Area Final Safety Analysis Report [FSAR] [Section 1 & 2

    SciTech Connect (OSTI)

    CARRELL, R D

    2002-07-16T23:59:59.000Z

    The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft{sup 2} and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped off-site to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the Fast Flux Test Facility (FFTF) SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF) TRIGA'--One Rad-Vault' container will store two DOT-6M3 containers and six NRF TRIGA casks currently stored in the 400 Area. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-I cask4 with an inner commercial light water reactor (LWR) canister, will be used for commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available.

  7. An Experimental Evaluation of Duct-Mounted Relative Humidity Sensors: Part 3 – Repeatability, Hysteresis and Linearity Results 

    E-Print Network [OSTI]

    Joshi, S.N.; Pate, M.B.; Nelson, R.M.; House, J.H.; Klaassen, C.J.

    2005-01-01T23:59:59.000Z

    Reproduced with permission of the copyright owner. Further reproduction prohibited without permission. An Experimental Evaluation of Duct-Mounted Relative Humidity Sensors: Part 3-Repeatability, Hyste... Joshi, Shailesh N;House, John M...

  8. Improving vegetable preference and consumption among preschool children: evaluating results from an educational intervention using vegetable gardening

    E-Print Network [OSTI]

    Lorenz, Saundra Gail

    2002-01-01T23:59:59.000Z

    's exposure to a variety of vegetables through the incorporation of weekly gardening supplemented with classroom activities. The objective of this study was to evaluate the usefulness of vegetable gardening to improve preschool children's affective responses...

  9. Impacts of the extended-weight coal haul road system (interim report). Research report

    SciTech Connect (OSTI)

    Crabtree, J.D.; Pigman, J.G.; Deacon, J.A.; Agent, K.R.

    1993-10-01T23:59:59.000Z

    The Extended-Weight Coal Haul Road System, created by Kentucky`s Legislature in 1986, consists of all roads which carry over 50,000 tons of coal in a calendar year. Trucks hauling coal on this system are authorized to exceed normal weight limits through the payment of an annual decal fee. A research study was initiated in July of 1992 to analyze the impacts of the extended-weight system. This interim report prepared after one year of a three-year study, describes the analyses performed thus far and presents preliminary findings, recommendations, and a discussion of future work. Analyses in this report are based on: historical data on coal production and transportation; data from coal decal applications; interviews of legislators, transportation officials, coal company representatives, and coal trucking representatives: newspaper articles; vehicle classification data; a pavement cost analysis; and accident data. Preliminary conclusions include: (1) The extended-weight system has apparently been somewhat successful in accomplishing the primary objectives: to enhance the competitiveness and economic viability of Kentucky`s coal industry and to eliminate the perceived need for cal haulers to violate the law in order to be competitive; (2) Overall accident rates are no higher on the extended-weight system than on other comparable routes, but the fatal accident rate is significantly higher on the extended-weight system; (3) The coal-decal fee structure results in a net annual loss in Road Fund revenue of approximately $2 million; (4) Forty percent of the revenue from decal sales is allocated to the counties, although less than ten percent of the extended-weight system in county-maintained; (5) The heavier weights of coal-decal trucks add approximately $9 million annually to pavement overlay costs and increase other highway costs. (6) Road users throughout the state are subsidizing the movement of Kentucky coal by underwriting the increased costs.

  10. PM Motor Parametric Design Analyses for Hybrid Electric Vehicle Traction Drive Application: Interim Report

    SciTech Connect (OSTI)

    Staunton, R.H.

    2004-08-11T23:59:59.000Z

    The Department of Energy's (DOE) Office of FreedomCAR (Cooperative Automotive Research) and Vehicle Technologies has a strong interest in making rapid progress in permanent magnet (PM) machine development. The program is directing various technology development projects that will advance the technology and lead to request for proposals (RFP) for manufacturer prototypes. This aggressive approach is possible because the technology is clearly within reach and the approach is deemed essential, based on strong market demand, escalating fuel prices, and competitive considerations. In response, this study began parallel development paths that included a literature search/review, development and utilization of multiple parametric models to determine the effects of design parameters, verification of the modeling methodology, development of an interior PM (IPM) machine baseline design, development of alternative machine baseline designs, and cost analyses for several candidate machines. This interim progress report summarizes the results of these activities as of June 2004. This report provides background and summary information for recent machine parametric studies and testing programs that demonstrate both the potential capabilities and technical limitations of brushless PM machines (axial gap and radial gap), the IPM machine, the surface-mount PM machines (interior or exterior rotor), induction machines, and switched reluctance machines. The FreedomCAR program, while acknowledging the progress made by Oak Ridge National Laboratory, Delphi, Delco-Remy International, and others in these programs, has redirected efforts toward a ''short path'' to a marketable and competitive PM motor for hybrid electric vehicle traction applications. The program has developed a set of performance targets for the type of traction machine desired. The short-path approach entails a comprehensive design effort focusing on the IPM machine and meeting the performance targets. The selection of the IPM machine reflects industry's confidence in this market-proven design that exhibits a power density surpassed by no other machine design.

  11. Interim Report on Customer Acceptance, Retention, and Response...

    Office of Environmental Management (EM)

    of evaluations of the utilities' consumer behavior studies include: Average peak demand reductions for customers taking service on Critical Peak Pricing (CPP) rates were...

  12. Hanford Tank Farm interim storage phase probabilistic risk assessment outline

    SciTech Connect (OSTI)

    Not Available

    1994-05-19T23:59:59.000Z

    This report is the second in a series examining the risks for the high level waste (HLW) storage facilities at the Hanford Site. The first phase of the HTF PSA effort addressed risks from Tank 101-SY, only. Tank 101-SY was selected as the initial focus of the PSA because of its propensity to periodically release (burp) a mixture of flammable and toxic gases. This report expands the evaluation of Tank 101-SY to all 177 storage tanks. The 177 tanks are arranged into 18 farms and contain the HLW accumulated over 50 years of weapons material production work. A centerpiece of the remediation activity is the effort toward developing a permanent method for disposing of the HLW tank`s highly radioactive contents. One approach to risk based prioritization is to perform a PSA for the whole HLW tank farm complex to identify the highest risk tanks so that remediation planners and managers will have a more rational basis for allocating limited funds to the more critical areas. Section 3 presents the qualitative identification of generic initiators that could threaten to produce releases from one or more tanks. In section 4 a detailed accident sequence model is developed for each initiating event group. Section 5 defines the release categories to which the scenarios are assigned in the accident sequence model and presents analyses of the airborne and liquid source terms resulting from different release scenarios. The conditional consequences measured by worker or public exposure to radionuclides or hazardous chemicals and economic costs of cleanup and repair are analyzed in section 6. The results from all the previous sections are integrated to produce unconditional risk curves in frequency of exceedance format.

  13. Assessment of Stormflow and Water Quality from Undisturbed and Site Prepared Forest Land in East Texas (Interim Report)

    E-Print Network [OSTI]

    DeHaven, M. G.; Blackburn, W. H.; Knight, R. W.; Weichert, A. T.

    TR- 117 1981 Assessment of Stormflow and Water Quality from Undisturbed and Site Prepared Forest Land in East Texas, Interim Report M.G. DeHaven W.H. Blackburn R.W. Knight A.T. Weichert...

  14. Evaluation of MHTGR fuel reliability

    SciTech Connect (OSTI)

    Wichner, R.P. [Oak Ridge National Lab., TN (United States); Barthold, W.P. [Barthold Associates, Inc., Knoxville, TN (United States)

    1992-07-01T23:59:59.000Z

    Modular High-Temperature Gas-Cooled Reactor (MHTGR) concepts that house the reactor vessel in a tight but unsealed reactor building place heightened importance on the reliability of the fuel particle coatings as fission product barriers. Though accident consequence analyses continue to show favorable results, the increased dependence on one type of barrier, in addition to a number of other factors, has caused the Nuclear Regulatory Commission (NRC) to consider conservative assumptions regarding fuel behavior. For this purpose, the concept termed ``weak fuel`` has been proposed on an interim basis. ``Weak fuel`` is a penalty imposed on consequence analyses whereby the fuel is assumed to respond less favorably to environmental conditions than predicted by behavioral models. The rationale for adopting this penalty, as well as conditions that would permit its reduction or elimination, are examined in this report. The evaluation includes an examination of possible fuel-manufacturing defects, quality-control procedures for defect detection, and the mechanisms by which fuel defects may lead to failure.

  15. Aquifer Sampling Tube Results for Fiscal Year 2003

    SciTech Connect (OSTI)

    Hartman, Mary J.; Peterson, Robert E.

    2003-10-27T23:59:59.000Z

    This report presents and discusses results of the fiscal year 2003 sampling event associated with aquifer tubes along the Columbia River in the northern Hanford Site. Aquifer tube data help define the extent of groundwater contamination near the river, determine vertical variations in contamination, monitor the performance of interim remedial actions near the river, and support impact studies.

  16. ORNL/TM-2007/065 EVALUATION OF THE SUPER ESPC

    E-Print Network [OSTI]

    Oak Ridge National Laboratory

    ORNL/TM-2007/065 EVALUATION OF THE SUPER ESPC PROGRAM -- REPORTED ENERGY AND COST SAVINGS Interim Science and Technology Division EVALUATION OF THE SUPER ESPC PROGRAM -- REPORTED ENERGY AND COST SAVINGS ESCO Energy services company ESPC Energy savings performance contract(ing) FEMP Federal Energy

  17. Engineering evaluation/cost analysis for decontamination at the St. Louis Downtown Site, St. Louis, Missouri

    SciTech Connect (OSTI)

    Picel, M.H.; Hartmann, H.M.; Nimmagadda, M.R. (Argonne National Lab., IL (USA)); Williams, M.J. (Bechtel National, Inc., Oak Ridge, TN (USA))

    1991-05-01T23:59:59.000Z

    The US Department of Energy (DOE) is implementing a cleanup program for three groups of properties in the St. Louis, Missouri, area: the St. Louis Downtown Site (SLDS), the St. Louis Airport Site (SLAPS) and vicinity properties, and the Latty Avenue Properties, including the Hazelwood Interim Storage Site (HISS). The general location of these properties is shown in Figure 1; the properties are referred to collectively as the St. Louis Site. None of the properties are owned by DOE, but each property contains radioactive residues from federal uranium processing activities conducted at the SLDS during and after World War 2. The activities addressed in this environmental evaluation/cost analysis (EE/CA) report are being proposed as interim components of a comprehensive cleanup strategy for the St. Louis Site. As part of the Department's Formerly Utilized Sites Remedial Action Program (FUSRAP), DOE is proposing to conduct limited decontamination in support of proprietor-initiated activities at the SLDS, commonly referred to as the Mallinckrodt Chemical Works. The primary goal of FUSRAP activity at the SLDS is to eliminate potential environmental hazards associated with residual contamination resulting from the site's use for government-funded uranium processing activities. 17 refs., 3 figs., 5 tabs.

  18. Evaluation of Global Monsoon Precipitation Changes based on Five Reanalysis Datasets

    SciTech Connect (OSTI)

    Lin, Renping; Zhou, Tianjun; Qian, Yun

    2014-02-01T23:59:59.000Z

    With the motivation to identify whether or not a reasonably simulated atmospheric circulation would necessarily lead to a successful reproduction of monsoon precipitation, the performances of five sets of reanalysis data (NCEP2, ERA40, JRA25, ERA-Interim and MERRA) in reproducing the climatology, interannual variation and long-term trend of global monsoon (GM) precipitation are comprehensively evaluated. In order to better understand the variability and long-term trend of GM precipitation, we also examined the major components of water budget, including evaporation, water vapor convergence and the change in local water vapor storage, based on five reanalysis datasets. The results show that all five reanalysis data reasonably reproduce the climatology of GM precipitation. The ERA-Interim (NCEP2) shows the highest (lowest) skill among the five datasets. The observed GM precipitation shows an increasing tendency during 1979-2001 along with a strong interannual variability, which is reasonably reproduced by the five sets of reanalysis data. The observed increasing trend of GM precipitation is dominated by the contribution from the North African, North American and Australian monsoons. All five data fail in reproducing the increasing tendency of North African monsoon precipitation. The wind convergence term in water budget equation dominate the GM precipitation variation, indicating a consistency between the GM precipitation and the seasonal change of prevailing wind.

  19. The Time Needed to Implement the Blue Ribbon Commission Recommendation on Interim Storage - 13124

    SciTech Connect (OSTI)

    Voegele, Michael D. [Consultant, Nye County Nuclear Waste Repository Project Office, 7404 Oak Grove Ave, Las Vegas, NV 89117 (United States)] [Consultant, Nye County Nuclear Waste Repository Project Office, 7404 Oak Grove Ave, Las Vegas, NV 89117 (United States); Vieth, Donald [1154 Chelttenham Place, Maineville, OH 45039 (United States)] [1154 Chelttenham Place, Maineville, OH 45039 (United States)

    2013-07-01T23:59:59.000Z

    The report of the Blue Ribbon Commission on America's Nuclear Future [1] makes a number of important recommendations to be considered if Congress elects to redirect U.S. high-level radioactive waste disposal policy. Setting aside for the purposes of this discussion any issues related to political forces leading to stopping progress on the Yucca Mountain project and driving the creation of the Commission, an important recommendation of the Commission was to institute prompt efforts to develop one or more consolidated storage facilities. The Blue Ribbon Commission noted that this recommended strategy for future storage and disposal facilities and operations should be implemented regardless of what happens with Yucca Mountain. It is too easy, however, to focus on interim storage as an alternative to geologic disposal. The Blue Ribbon Commission report does not go far enough in addressing the magnitude of the contentious problems associated with reopening the issues of relative authorities of the states and federal government with which Congress wrestled in crafting the Nuclear Waste Policy Act [2]. The Blue Ribbon Commission recommendation for prompt adoption of an interim storage program does not appear to be fully informed about the actions that must be taken, the relative cost of the effort, or the realistic time line that would be involved. In essence, the recommendation leaves to others the details of the systems engineering analyses needed to understand the nature and details of all the operations required to reach an operational interim storage facility without derailing forever the true end goal of geologic disposal. The material presented identifies a number of impediments that must be overcome before the country could develop a centralized federal interim storage facility. In summary, and in the order presented, they are: 1. Change the law, HJR 87, PL 107-200, designating Yucca Mountain for the development of a repository. 2. Bring new nuclear waste legislation to the floor of the Senate, overcoming existing House support for Yucca Mountain; 3. Change the longstanding focus of Congress from disposal to storage; 4. Change the funding concepts embodied in the Nuclear Waste Policy Act to allow the Nuclear Waste fund to be used to pay for interim storage; 5. Reverse the Congressional policy not to give states or tribes veto or consent authority, and to reserve to Congress the authority to override a state or tribal disapproval; 6. Promulgate interim storage facility siting regulations to reflect the new policies after such changes to policy and law; 7. Complete already underway changes to storage and transportation regulations, possibly incorporating changes to reflect changes to waste disposal law; 8. Promulgate new repository siting regulations if the interim storage facility is to support repository development; 9. Identify volunteer sites, negotiate agreements, and get Congressional approval for negotiated benefits packages; 10. Design, License and develop the interim storage facility. The time required to accomplish these ten items depends on many factors. The estimate developed assumes that certain of the items must be completed before other items are started; given past criticisms of the current program, such an assumption appears appropriate. Estimated times for completion of individual items are based on historical precedent. (authors)

  20. Diesel Emission Control -- Sulfur Effects (DECSE) Program; Phase I Interim Date Report No. 3: Diesel Fuel Sulfur Effects on Particulate Matter Emissions

    SciTech Connect (OSTI)

    DOE; ORNL; NREL; EMA; MECA

    1999-11-15T23:59:59.000Z

    The Diesel Emission Control-Sulfur Effects (DECSE) is a joint government/industry program to determine the impact of diesel fuel sulfur levels on emission control systems whose use could lower emissions of nitrogen oxides (NO{sub x}) and particulate matter (PM) from on-highway trucks in the 2002--2004 model years. Phase 1 of the program was developed with the following objectives in mind: (1) evaluate the effects of varying the level of sulfur content in the fuel on the emission reduction performance of four emission control technologies; and (2) measure and compare the effects of up to 250 hours of aging on selected devices for multiple levels of fuel sulfur content. This interim report covers the effects of diesel fuel sulfur level on particulate matter emissions for four technologies.

  1. Operations and Maintenance Concept Plan for the Immobilized High Level Waste (IHLW) Interim Storage Facility

    SciTech Connect (OSTI)

    JANIN, L.F.

    2000-08-30T23:59:59.000Z

    This O&M Concept looks at the future operations and maintenance of the IHLW/CSB interim storage facility. It defines the overall strategy, objectives, and functional requirements for the portion of the building to be utilized by Project W-464. The concept supports the tasks of safety basis planning, risk mitigation, alternative analysis, decision making, etc. and will be updated as required to support the evolving design.

  2. Seismic Safety Margins Research Program. Phase I. Interim definition of terms

    SciTech Connect (OSTI)

    Smith, P.D.; Dong, R.G.

    1980-12-19T23:59:59.000Z

    This report documents interim definitions of terms in the Seismic Safety Margins Research Program (SSMRP). Intent is to establish a common-based terminology integral to the probabilistic methods that predict more realistically the behavior of nuclear power plants during an earthquake. These definitions are a response to a request by the Nuclear Regulatory Commission Advisory Committee on Reactor Safeguards at its meeting held November 15-16, 1979.

  3. Safety of interim storage solutions of used nuclear fuel during extended term

    SciTech Connect (OSTI)

    Shelton, C.; Bader, S.; Issard, H.; Arslan, M. [AREVA, 7135 Minstrel Way, Suite 300 Columbia, MD 21045 (United States)

    2013-07-01T23:59:59.000Z

    In 2013, the total amount of stored used nuclear fuel (UNF) in the world will reach 225,000 T HM. The UNF inventory in wet storage will take up over 80% of the available total spent fuel pool (SFP) capacity. Interim storage solutions are needed. They give flexibility to the nuclear operators and ensure that nuclear reactors continue to operate. However, we need to keep in mind that they are also an easy way to differ final decision and implementation of a UNF management approach (recycling or final disposal). In term of public perception, they can have a negative impact overtime as it may appear that nuclear industry may have significant issues to resolve. In countries lacking an integrated UNF management approach, the UNF are being discharged from the SFPs to interim storage (mostly to dry storage) at the same rate as UNF is being discharged from reactors, as the SFPs at the reactor sites are becoming full. This is now the case in USA, Taiwan, Switzerland, Spain, South Africa and Germany. For interim storage, AREVA has developed different solutions in order to allow the continued operation of reactors while meeting the current requirements of Safety Authorities: -) Dry storage canisters on pads, -) Dual-purpose casks (dry storage and transportation), -) Vault dry storage, and -) Centralized pool storage.

  4. 3500-hour durability testing of commercial ceramic materials. Interim report

    SciTech Connect (OSTI)

    Carruthers, W.D.; Richerson, D.W.; Benn, K.W.

    1980-07-01T23:59:59.000Z

    A two-year durability testing program was performed by AiResearch Phoenix to evaluate four commercially available ceramic materials under simulated automotive gas turbine combustor discharge conditions. These conditions included extended cyclic thermal exposures up to 2500/sup 0/F and 3500 h. The four materials selected for evaluation were Norton NCX-34 hot pressed silicon nitride, AiResearch RBN 101 reaction bonded silicon nitride, Carborundum pressureless sintered ..cap alpha..-SiC and British Nuclear Fuels, Ltd. Refel reaction sintered silicon carbide marketed by Pure Carbon Co. These materials initially were exposed to 350 h/1750 cycles at 1200 and 1370/sup 0/C (2200 and 2500/sup 0/F). Subsequent exposures to 1050, 2100, and 3500 h were performed on the materials maintaining 50% of baseline strength after the initial exposure. Additional evaluations of exposed bars included dimension changes, weight changes, dye penetrant, specific damping capacity changes, Scanning Electron Microscope (SEM) fractography and x-ray diffraction.

  5. 3013/9975 Surveillance Program Interim Summary Report

    SciTech Connect (OSTI)

    Dunn, K.; Hackney, B.; McClard, J.

    2011-06-22T23:59:59.000Z

    The K-Area Materials Storage (KAMS) Documented Safety Analysis (DSA) requires a surveillance program to monitor the safety performance of 3013 containers and 9975 shipping packages stored in KAMS. The SRS surveillance program [Reference 1] outlines activities for field surveillance and laboratory tests that demonstrate the packages meet the functional performance requirements described in the DSA. The SRS program also supports the complexwide Integrated Surveillance Program (ISP) [Reference 2] for 3013 containers. The purpose of this report is to provide a summary of the SRS portion of the surveillance program activities through fiscal year 2010 (FY10) and formally communicate the interpretation of these results by the Surveillance Program Authority (SPA). Surveillance for the initial 3013 container random sampling of the Innocuous bin and the Pressure bin has been completed and there has been no indication of corrosion or significant pressurization. The maximum pressure observed was less than 50 psig, which is well below the design pressure of 699 psig for the 3013 container [Reference 3]. The data collected during surveillance of these bins has been evaluated by the Materials Identification and Surveillance (MIS) Working Group and no additional surveillance is necessary for these bins at least through FY13. A decision will be made whether additional surveillance of these bins is needed during future years of storage and as additional containers are generated. Based on the data collected to date, the SPA concludes that 3013 containers in these bins can continue to be safely stored in KAMS. This year, 13 destructive examinations (DE) were performed on random samples from the Pressure & Corrosion bin. To date, DE has been completed for approximately 30% of the random samples from the Pressure & Corrosion bin. In addition, DE has been performed on 6 engineering judgment (EJ) containers, for a total of 17 to date. This includes one container that exceeded the 3013 Standard moisture limit which was opened at LANL. The container pieces and an oxide sample were sent to SRNL for examination in FY11. No significant pressurization has been observed for the Pressure & Corrosion bin containers. Relatively minor corrosion has been observed on some convenience containers and the inside of two inner containers. While the limited extent of corrosion does not jeopardize the integrity of the outer 3013 containers, it does highlight the importance of continuing to perform DE and the Shelf Life program to assure that the corrosion rate is not accelerating or changing to a different corrosion mechanism (e.g., stress corrosion cracking). Statistical sampling is currently scheduled to be completed in FY17, but there is a proposed reduction of the number of DE's per year for FY11 and beyond which may delay the completion date. Since 3013 containers are stored inside 9975 containers, surveillances of 9975 containers are performed in conjunction with 3013 container surveillances. Results of 9975 container nondestructive examinations (NDEs) and DEs indicate that the containers will provide adequate protection of the 3013 containers in K-Area storage for at least 15 years [Reference 4].

  6. Stress evaluation of welded steel bridges on coal-haul routes. Interim research report

    SciTech Connect (OSTI)

    Hopwood, T.; Hogan, K.J.; Oberst, C.M.

    1993-05-01T23:59:59.000Z

    Certain roads in Kentucky are designated as `extended-weight coal haul routes.` On those roads, coal transporters are allowed to employ coal trucks loaded far in excess of legal limits in force on normal roads throughout the state. The objective of this study is to measure live-load stresses on welded steel bridges on extended-weight coal haul routes. Fatigue analyses are performed on strain (stress) data derived from field stress measurements. Those are performed to determine whether the magnitude of those stresses and frequency of their occurrence are sufficient to pose fatigue problems presently or over the anticipated service lives of those bridges (i.e., 75 years). Live-load stress data obtained from bridges not possessing fatigue-prone weld details may be of benefit to bridge designers.

  7. FedEx Gasoline Hybrid Electric Delivery Truck Evaluation: 6-Month Interim Report

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville Power AdministrationField8,Dist. CategoryFebruaryFebruary 17, 2015 - SEAB8 An employee7693 May

  8. 2000 Annual Interim Sanitary Landfill Groundwater Monitoring Report

    SciTech Connect (OSTI)

    Chase, J.A.

    2001-01-26T23:59:59.000Z

    This report includes a discussion of the groundwater flow direction and rate, the groundwater analytical results, and the methane monitoring results.

  9. SFC e-Learning Transformation Programme Interim Reporting Template

    E-Print Network [OSTI]

    Azzopardi, Leif

    by technology across three Scottish HE institutions. It is also examining how to embed good assessment practice-Engineering Assessment Practices (REAP) University of Strathclyde Report compiled by David Nicol and Catherine Owen: Summary The REAP project is implementing and evaluating new models of assessment practice supported

  10. HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT BUCKLING EVALUATION METHODS AND RESULTS FOR THE PRIMARY TANKS

    SciTech Connect (OSTI)

    MACKEY TC; JOHNSON KI; DEIBLER JE; PILLI SP; RINKER MW; KARRI NK

    2009-01-14T23:59:59.000Z

    This report documents a detailed buckling evaluation of the primary tanks in the Hanford double-shell waste tanks (DSTs), which is part of a comprehensive structural review for the Double-Shell Tank Integrity Project. This work also provides information on tank integrity that specifically responds to concerns raised by the Office of Environment, Safety, and Health (ES&H) Oversight (EH-22) during a review of work performed on the double-shell tank farms and the operation of the aging waste facility (AWF) primary tank ventilation system. The current buckling review focuses on the following tasks: (1) Evaluate the potential for progressive anchor bolt failure and the appropriateness of the safety factors that were used for evaluating local and global buckling. The analysis will specifically answer the following questions: (a) Can the EH-22 scenario develop if the vacuum is limited to -6.6-inch water gage (w.g.) by a relief valve? (b) What is the appropriate factor of safety required to protect against buckling if the EH-22 scenario can develop? (c) What is the appropriate factor of safety required to protect against buckling if the EH-22 scenario cannot develop? (2) Develop influence functions to estimate the axial stresses in the primary tanks for all reasonable combinations of tank loads based on detailed finite element analysis. The analysis must account for the variation in design details and operating conditions between the different DSTs. The analysis must also address the imperfection sensitivity of the primary tank to buckling. (3) Perform a detailed buckling analysis to determine the maximum allowable differential pressure for each of the DST primary tanks at the current specified limits on waste temperature, height, and specific gravity. Based on the concrete anchor bolt loads analysis and the small deformations that are predicted at the unfactored limits on vacuum and axial loads, it is very unlikely that the EH-22 scenario (i.e., progressive anchor bolt failure leading to global buckling of the tank under increased vacuum) could occur. After releasing Revision 0 of this report, an independent review of the Double Shell Tanks (DST) Thermal and Operating Loads Analysis (TaLA) combined with the Seismic Analysis was conducted by Dr. Robert P. Kennedy of RPK Structural Mechanics Consulting and Dr. Anestis S. Veletsos of Rice University. Revision I was then issued to address their review comments (included in Appendix D). Additional concerns involving the evaluation of concrete anchor loads and allowables were found during a second review by Drs. Kennedy and Veletsos (see Appendix G). Extensive additional analysis was performed on the anchors, which is detailed by Deibler et al. (2008a, 2008b). The current report (Revision 2) references this recent work, and additional analysis is presented to show that anchor loads do not concentrate significantly in the presence of a local buckle.

  11. EERC pilot-scale CFBC evaluation facility Project CFB test results. Topical report, Task 7.30

    SciTech Connect (OSTI)

    Mann, M.D.; Hajicek, D.R.; Henderson, A.K.; Moe, T.A.

    1992-09-01T23:59:59.000Z

    Project CFB was initiated at the University of North Dakota Energy and Environmental Research Center (EERC) in May 1988. Specific goals of the project were to (1) construct a circulating fluidized-bed combustor (CFBC) facility representative of the major boiler vendors` designs with the capability of producing scalable data, (2) develop a database for use in making future evaluations of CFBC technology, and (3) provide a facility for evaluating fuels, free of vendor bias for use in the - energy industry. Five coals were test-burned in the 1-MWth unit: North Dakota and Asian lignites, a Wyoming subbituminous, and Colorado and Pennsylvania bituminous coats. A total of 54 steady-state test periods were conducted, with the key test parameters being the average combustor temperature, excess air, superficial gas velocity, calcium-to-sulfur molar ratio, and the primary air-to-secondary air split. The capture for a coal fired in a CFBC is primarily dependent upon the total alkali-to-sulfur ratio. The required alkali-to ratio for 90% sulfur retention ranged from 1.4 to 4.9, depending upon coal type. While an alkali-to-ratio of 4.9 was required to meet 90% sulfur retention for the Salt Creek coal versus 1.4 for the Asian lignite, the total amount of sorbent addition required is much less for the Salt Creek coal, 4.2 pound sorbent per million Btu coal input, versus 62 pound/million Btu for the Asian lignite. The bituminous coals tested show optimal capture at combustor temperatures of approximately 1550{degree}F, with low-rank coals having optimal sulfur capture approximately 100{degree}F lower.

  12. Advanced membrane devices. Interim report for October 1996--September 1997

    SciTech Connect (OSTI)

    Laciak, D.V.; Langsam, M.; Lewnard, J.J.; Reichart, G.C.

    1997-12-31T23:59:59.000Z

    Under this Cooperative Agreement, Air Products and Chemicals, Inc. has continued to investigate and develop improved membrane technology for removal of carbon dioxide from natural gas. The task schedule for this reporting period included a detailed assessment of the market opportunity (Chapter 2), continued development and evaluation of membranes and membrane polymers (Chapter 3) and a detailed economic analysis comparing the potential of Air Products membranes to that of established acid gas removal processes (Chapter 4).

  13. NINTH INTERIM STATUS REPORT: MODEL 9975 PCV O-RING FIXTURE LONG-TERM LEAK PERFORMANCE

    SciTech Connect (OSTI)

    Daugherty, W.

    2014-08-06T23:59:59.000Z

    A series of experiments to monitor the aging performance of Viton® GLT O-rings used in the Model 9975 package has been ongoing since 2004 at the Savannah River National Laboratory. One approach has been to periodically evaluate the leak performance of O-rings being aged in mock-up 9975 Primary Containment Vessels (PCVs) at elevated temperatures. Other methods such as compression-stress relaxation (CSR) tests and field surveillance are also on-going to evaluate O-ring behavior. Seventy tests using PCV mock-ups were assembled and heated to temperatures ranging from 200 to 450 ºF. They were leak-tested initially and have been tested periodically to determine if they continue to meet the leak-tightness criterion defined in ANSI standard N14.5-97. Due to material substitution, fourteen additional tests were initiated in 2008 with GLT-S O-rings heated to temperatures ranging from 200 to 400 ºF. High temperature aging continues for 23 GLT O-ring fixtures at 200 – 270 ºF. Room temperature leak test failures have been experienced in all of the GLT O-ring fixtures aging at 350 ºF and higher temperatures, and in 8 fixtures aging at 300 ºF. The earliest 300 °F GLT O-ring fixture failure was observed at 34 months. The remaining GLT O-ring fixtures aging at 300 ºF have been retired from testing following more than 5 years at temperature without failure. No failures have yet been observed in GLT O-ring fixtures aging at 200 ºF for 72 - 96 months, which bounds O-ring temperatures anticipated during storage in K-Area Complex (KAC). Based on expectations that the 200 ºF fixtures will remain leak-tight for a significant period yet to come, 2 additional fixtures began aging in 2011 at 270 ºF, with hopes that they may reach a failure condition before the 200 ºF fixtures, thus providing additional time to failure data. High temperature aging continues for 6 GLT-S O-ring fixtures at 200 – 300 ºF. Room temperature leak test failures have been experienced in all 8 of the GLT-S O-ring fixtures aging at 350 and 400 ºF. No failures have yet been observed in GLT-S O-ring fixtures aging at 200 - 300 ºF for 54 - 57 months. No additional O-ring failures have been observed since the last interim report was issued. Aging and periodic leak testing will continue for the remaining PCV fixtures. Additional irradiation of several fixtures is recommended to maintain a balance between thermal and radiation exposures similar to that experienced in storage, and to show the degree of consistency of radiation response between GLT and GLT-S O-rings.

  14. Interim salt disposition program macrobatch 6 tank 21H qualification monosodium titanate and cesium mass transfer tests

    SciTech Connect (OSTI)

    Washington, A. L. II; Peters, T. B.; Fink, S. D.

    2013-02-25T23:59:59.000Z

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 6 processing. This qualification material was a set of six samples from Tank 21H in October 2012. This sample was used as a real waste demonstration of the Actinide Removal Process (ARP) and the Extraction-Scrub-Strip (ESS) tests process. The Tank 21H sample was contacted with a reduced amount (0.2 g/L) of MST and characterized for strontium and actinide removal at 0 and 8 hour time intervals in this salt batch. {sup 237}Np and {sup 243}Am were both observed to be below detection limits in the source material, and so these results are not reported in this report. The plutonium and uranium samples had decontamination factor (DF) values that were on par or slightly better than we expected from Batch 5. The strontium DF values are slightly lower than expected but still in an acceptable range. The Extraction, Scrub, and Strip (ESS) testing demonstrated cesium removal, stripping and scrubbing within the acceptable range. Overall, the testing indicated that cesium removal is comparable to prior batches at MCU.

  15. A comprehensive program to develop correlations for the physical properties of Kraft black liquor. Interim report No. 3

    SciTech Connect (OSTI)

    Fricke, A.L.; Dong, D.J.; Schmidl, G.W.; Stoy, M.A.; Zaman, A.A.

    1993-09-01T23:59:59.000Z

    The black liquor properties program has been conducted over this last period so as to systematically collect data on properties, liquor composition, and lignin characteristics very carefully by methods that have developed during this program. Complete data has been collected for Slash Pine black liquors made by experimental pulping at different pulping conditions. In addition, data has been collected for mill liquors and partial properties or composition data has been collected on Slash Pine black liquors. Data reduction methods have been developed or extended for correlation of viscosity, heat capacity, heat of dilution, and density. Correlation of properties to pulping conditions and of composition to. pulping conditions has begun. In most cases, data reduction methods have been developed that are fundamentally based and that have been shown to be generally applicable to all black liquors. In the near future, we fully expect to accomplish our goal of developing generalized correlations relating physical properties of Slash Pine kraft black liquors to liquor composition. This interim report reviews the methods used, describes examples of data reduction methods that have been developed, and presents some preliminary results for correlation of liquor composition and properties to pulping conditions for Slash Pine black liquors.

  16. T Tank Farm Interim Surface Barrier Demonstration - Vadose Zone Monitoring FY09 Report

    SciTech Connect (OSTI)

    Zhang, Z. F.; Strickland, Christopher E.; Field, Jim G.; Parker, Danny L.

    2010-01-01T23:59:59.000Z

    DOE’s Office of River Protection constructed a temporary surface barrier over a portion of the T Tank Farm as part of the T Farm Interim Surface Barrier Demonstration Project. As part of the demonstration effort, vadose zone moisture is being monitored to assess the effectiveness of the barrier at reducing soil moisture. A solar-powered system was installed to continuously monitor soil water conditions at four locations (i.e., instrument Nests A, B, C, and D) beneath the barrier and outside the barrier footprint as well as site meteorological conditions. Nest A is placed in the area outside the barrier footprint and serves as a control, providing subsurface conditions outside the influence of the surface barrier. Nest B provides subsurface measurements to assess surface-barrier edge effects. Nests C and D are used to assess changes in soil-moisture conditions beneath the interim surface barrier. Each instrument nest is composed of a capacitance probe (CP) with multiple sensors, multiple heat-dissipation units (HDUs), and a neutron probe (NP) access tube. The monitoring results in FY09 are summarized below. The solar panels functioned normally and could provide sufficient power to the instruments. The CP in Nest C after September 20, 2009, was not functional. The CP sensors in Nest B after July 13 and the 0.9-m CP sensor in Nest D before June 10 gave noisy data. Other CPs were functional normally. All the HDUs were functional normally but some pressure-head values measured by HDUs were greater than the upper measurement-limit. The higher-than-upper-limit values might be due to the very wet soil condition and/or measurement error but do not imply the malfunction of the sensors. Similar to FY07 and FY08, in FY09, the soil under natural conditions (Nest A) was generally recharged during the winter period (October-March) and discharged during the summer period (April-September). Soil water conditions above about 1.5-m to 2-m depth from all three types of measurements (i.e., CP, NP and HDU) showed relatively large variation during the seasonal wetting-drying cycle. For the soil below 2-m depth, the seasonal variation of soil water content was relatively small. The construction of the surface barrier was completed in April 2008. In the soil below the surface barrier (Nests C and D), the CP measurements showed that water content at the soil between 0.6-m and 2.3-m depths was very stable, indicating no climatic impacts on soil water condition beneath the barrier. The NP-measured water content showed that soil water drainage seemed occurring in the soil between about 3.4 m (11 ft) and 9.1 m (30 ft) in FY09. The HDU-measured water pressure decreased consistently in the soil above 5-m depth, indicating soil water drainage at these depths of the soil. In the soil below the edge of the surface barrier (Nest B), the CP-measured water content was relatively stable through the year except at the 0.9-m depth; the NP-measured water content showed that soil water drainage was occurring in the soil between about 3.4 m (11 ft) and 9.1 m (30 ft) but at a slightly smaller magnitude than those in Nests C and D; the HDU-measurements show that the pressure head changes in FY09 in Nest B were less than those for C and D but more than those for A. The soil-water-pressure head was more sensitive to soil water regime changes under dry conditions. In the soil beneath the barrier, the theoretical steady-state values of pressure head is equal to the negative of the distance to groundwater table. Hence, it is expected that, in the future, while the water content become stable, the pressure head will keep decreasing for a long time (e.g., many years). These results indicate that the T Tank Farm surface barrier was performing as expected by intercepting the meteoric water from infiltrating into the soil and the soil was becoming drier gradually. The barrier also has some effects on the soil below the barrier edge but at a reduced magnitude.

  17. An Evaluation of the Federal Energy Management Program Technical Assistance Workshops: Results of a 1998 Customer Survey

    SciTech Connect (OSTI)

    G. B. Gordon; N. Hall

    1999-04-01T23:59:59.000Z

    This report presents the results of a customer telephone survey of the participants of six workshops provided by the U. S. Department of Energy Federal Energy Management Program (FEMP) during calendar years 1995 and 1996. The primary purpose for the survey was to provide the Team Leader for FEMP Technical Assistance and members of the team with detailed customer feedback pertaining to how well selected FEMP workshops are doing and to identify areas for improvement. The information presented enables managers to see both the strengths of their workshops, as well as workshop components that can be improved. In addition, the report identifies the questions included in the survey that were the most productive for obtaining customers experiences, opinions and recommendations. The experiences gained during this survey provide a platform from which to launch an annual FEMP customer survey.

  18. DEMONSTRATION OF THE DOE INTERIM ENERGY CONSERVATION STANDARDS FOR NEW FEDERAL RESIDENTIAL BUILDINGS

    SciTech Connect (OSTI)

    Lee, A. D.; Baechler, H. C.; Di Massa, F. V.; Lucas, R. G.; Shankle, D. L.

    1992-01-01T23:59:59.000Z

    In accordance with federal legislation, the U.S. Department of Energy (DOE) has sponsored a study to demonstrate use of its Interim Energy Conservation Standards for New Federal Residential Buildings. The demonstration study was conducted by DOE and the Pacific Northwest Laboratory (PNL). The demonstration is the second step in a three-step process: I) development of interim standards, 2) demonstration of the interim standards, and 3) development of final standards. The standards are mandatory for federal agency housing procurements. Nevertheless, PNL found at the start of the demonstration that agency use of the interim standards had been minimal. The purpose of the standards is to improve the energy efficiency of federal housing and increase the use of nondepletable energy sources. In accordance with the legislation, the standards were to be performance-based rather than prescribing specific energy conservation measures. To fulfill this aspect of the legislation, the standards use a computer software program called COSTSAFR which generates a point system that individualizes the standards to specific projects based on climate, housing type, and fuel costs. The standards generate minimum energy-efficiency requirements by applying the life-cycle cost methodology developed for federal projects. For the demonstration, PNL and DOE chose five federal agency housing projects which had been built in diverse geographic and climate regions. Participating agencies were the Air Force, the Army (which provided two case studies), the Navy, and the Department of Health and Human Services. PNL worked with agency housing procurement officials and designers/architects to hypothetically apply the interim standards to the procurement and design of each housing project. The demonstration started at the point in the project where agencies would establish their energyefficiency requirements for the project and followed the procurement process through the designers' use of the point system to develop a design which would comply with the standards. PNL conducted extensive interviews with the federal agencies and design contractors to determine what impacts the standards would have on the existing agency procurement process as well as on designers. Overall, PNL found that the interim standards met the basic intent of the law. Specific actions were identified, however, that DOE could take to improve the standards and encourage the agencies to implement them. Agency personnel found the minimum efficiency levels established by the standards to be lower than expected, and lower than their existing requirements. Generally, this was because the standards factor in fuel costs, as well as energy savings due to various conservation measures such as insulation, when they determine the minimum efficiency levels required. The demonstration showed that federal agencies often pay low prices for heating fuel and electricity; these lower costs "tipped the scales," allowing designers to meet the efficiency target with designs that were relatively inefficient. It appeared, however, that the low prices paid by agencies directly to suppliers did not capture the agencies' full costs of providing energy, such as the costs of distribution and storage. Agency personnel expressed some concern about the standards' ability to incorporate new energy-efficient technologies and renewable resource technologies like solar heating systems. An alternative compliance procedure was developed to incorporate new technologies; however, demonstration participants said the procedure was not well documented and was difficult and time consuming to use. Despite these concerns, most agency personnel thought that the standards would fit into current procurement procedures with no big changes or cost increases. Many said use of the standards would decrease the time and effort they now spend to establish energy-efficiency requirements and to confirm that proposed designs comply. Personnel praised the software and documentation for being easy to use and providing energ

  19. Long-Term Results from Evaluation of Advanced New Construction Packages in Test Homes: Martha's Vineyard, Massachusetts

    SciTech Connect (OSTI)

    Stecher, D.; Allison, K.; Prahl, D.

    2012-10-01T23:59:59.000Z

    This report presents a cold climate project that examines the relationships among very energy efficient single-family residential thermal enclosures, room-to-room temperature variations, and simplified space conditioning systems. The project is located in West Tisbury, Massachusetts, on the island of Martha's Vineyard, and allowed for the comparison of room-to-room temperatures in four virtually identical houses that were all built to the same construction standard. The four homes each has a single ductless heat pump unit (DHU) located in the main living space and radiant electric resistance panels in each bedroom with individual thermostatic controls. Results indicate that temperature fluctuations in the living room due to aggressive setup and setback of the DHU may contribute to higher percentages of time where the bedroom temperatures were within +/-2 degrees F of the living room temperatures. Solar gains in the living room, door opening/closure and occupant manipulation of thermostats appear to have had a significant impact on room-to-room temperature differences, as would be expected.

  20. Feather weights : rapid redeployable structures for interim use

    E-Print Network [OSTI]

    Willis, Robin (Robin Christian)

    2011-01-01T23:59:59.000Z

    This thesis examines vacant urban parcels that are either unviable for development or stalled as a result of the economic crisis, and asks: How is it possible to generate both economic and urban value on these sites until ...

  1. BMDO: New Mexico Technology Transfer Demonstration Project. Interim final report

    SciTech Connect (OSTI)

    Not Available

    1993-11-01T23:59:59.000Z

    The BMDO-New Mexico Technology Transfer Demonstration Project(BMDO-NM) was a collaborative effort among the national laboratories to identify and evaluate the commercial potential of selected SDI-funded technologies. The project was funded by BMDO (formerly known as the Strategic Defense Initiative Office or SDIO), the Technology Enterprise Division (NM-TED) of the NM Economic Development Division, and the three National Laboratories. The project was managed and supervised by SAGE Management Partners of Albuquerque, and project funding was administered through the University of New Mexico. The BMDO-NM Demonstration Project focused on the development of a process to assist technology developers in the evaluation of selected BMDO technology programs so that commercialization decisions can be made in an accelerated manner. The project brought together BMDO, the NM-TED, the University of New Mexico, and three New Mexico Federal laboratories -- Los Alamos (DOE), Phillips (DOD) and Sandia (DOE). Each national laboratory actively participated throughout the project through its technology transfer offices. New Mexico was selected as the site for the Demonstration Program because of its three national and federal research laboratories engaged in BMDO programs, and the existing relationship among state govemment, the labs, universities and local economic development and business assistance organizations. Subsequent Commercialization and Implementation phases for the selected technologies from LANL and SNL were completed by SAGE and the Project Team. Funding for those phases was provided by the individual labs as well as BMDO and NM-TED in kind services. NM-TED played a proactive role in this New Mexico partnership. Its mandate is to promote technology-based economic development, with a commitment to facilitate the use of technology by industry and business statewide. TED assumed the role of program manager and executing agent for BMDO in this demonstration project.

  2. RCRA/UST, superfund, and EPCRA hotline training module. Introduction to: Permits and interim status (40 CFR part 270) updated as of July 1995

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    The module presents an overview of the RCRA permitting process and the requirements that apply to treatment, storage, and disposal facilities (TSDFs) operating under interim status until a permit is issued. It lists the types of activities that do and do not require a permit. It provides CFR cites for definitions of existing hazardous waste facility and new hazardous waste facility and identifies CFR sections relevant to Part A and Part B permit information requirements and describes the difference between them. It outlines steps in the process from interim status to receipt of permit. It identifies the differences among permit modification classes, and lists the special forms of permits. It lists the permit-by-rule applications, status and eligibility requirements for interim status and the conditions for termination of interim status and lists the conditions for changes during interim status.

  3. T-TY Tank Farm Interim Surface Barrier Demonstration—Vadose Zone Monitoring Plan

    SciTech Connect (OSTI)

    Zhang, Z. F.; Strickland, Christopher E.; Field, Jim G.; Parker, Danny L.

    2010-09-27T23:59:59.000Z

    The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank of the 241-T Tank Farm in 1973. Five tanks are assumed to have leaked in the TY Farm. Many of the contaminants from those leaks still reside within the vadose zone within the T and TY Tank Farms. The Department of Energy’s Office of River Protection seeks to minimize the movement of these contaminant plumes by placing interim barriers on the ground surface. Such barriers are expected to prevent infiltrating water from reaching the plumes and moving them further. The soil water regime is monitored to determine the effectiveness of the interim surface barriers. Soil-water content and water pressure are monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. Four instrument nests were installed in the T Farm in fiscal year (FY) 2006 and FY2007; two nests were installed in the TY Farm in FY2010. Each instrument nest contains a neutron probe access tube, a capacitance probe, and four heat-dissipation units. A meteorological station has been installed at the north side of the fence of the T Farm. This document summarizes the monitoring methods, the instrument calibration and installation, and the vadose zone monitoring plan for interim barriers in T farm and TY Farm.

  4. Hydrogen combustion in an MCO during interim storage (fauske and associates report 99-14)

    SciTech Connect (OSTI)

    PLYS, M.G.

    1999-05-12T23:59:59.000Z

    Flammable conditions are not expected to develop in an MCO during interim storage. This report considers potential phenomena which, although not expected t o occur, could lead t o flammable conditions. For example, reactions of hydrogen w i t h fuel over decades a r e postulated t o lead t o flammable atmospheric mixtures. For the extreme cases considered in this report, the highest attainable post-combustion pressure is about 13 atmospheres absolute, almost a factor of two and a half below the MCO design pressure of 31 atmospheres.

  5. Flatiron agc (automatic generation control) interim controller. Master station. Volume 1

    SciTech Connect (OSTI)

    Lennon, C.A. Jr; Whittemore, T.R.; Stitt, S.C.; Gish, W.B.

    1983-06-01T23:59:59.000Z

    The Flatiron Interim Automatic Generation Controller has been placed in service for the Lower Missouri Western Area Power Administration Control Area. This controller meets the requirements of the National Electric Reliability Council and controls the energy generation and transfers in northern Colorado, Wyoming, western Nebraska, western South Dakota, and southern Montana. The master controller is based on five interacting microprocessors with unique communication structures and data storage methods. The design, construction, maintenance, and operation details for the master station and the remote stations, including flow charts, schematics, and wiring diagrams, are in this four-volume series.

  6. Department of Energy Plutonium ES&H Vulnerability Assessment Savannah River Site interim compensatory measures

    SciTech Connect (OSTI)

    Bickford, W.E.

    1994-09-15T23:59:59.000Z

    The Savannah River Site (SRS) has recently completed a self-assessment of potential vulnerabilities associated with plutonium and other transuranic materials stored at the site. An independent Working Group Assessment Team (WGAT) appointed by DOE/ES&H also performed an independent assessment, and reviewed and validated the site self-assessment. The purpose of this report is to provide a status of interim compensatory measures at SRS to address hazards in advance of any corrective actions. ES&H has requested this status for all vulnerabilities ranked medium or higher with respect to potential consequences to workers, environment, and the public.

  7. Interim Final Rule and Request for Comments, Federal Register, 71 FR 70275,

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment of EnergyIndustry15Among States in theWAPA1Interim Final Rule10

  8. Interim Update: Global Automotive Power Electronics R&D Relevant To DOE

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment of EnergyIndustry15Among States in theWAPA1Interim2015 and 2020

  9. Final report of the independent counsel for Iran/Contra matters. Volume 2: Indictments, plea agreements, interim reports to the congress, and administrative matters

    SciTech Connect (OSTI)

    Walsh, L.E.

    1993-08-04T23:59:59.000Z

    In October and November 1986, two secret U.S. Government operations were publicly exposed, potentially implicating Reagan Administration officials in illegal activities. These operations were the provision of assistance to the military activities of the Nicaraguan contra rebels during an October 1984 to October 1986 prohibition on such aid, and the sale of U.S. arms to Iran in contravention of stated U.S. policy and in possible violation of arms-export controls. In late November 1986, Reagan Administration officials announced that some of the proceeds from the sale of U.S. arms to Iran had been diverted to the contras. As a result, Attorney General Edwin Meese III sought the appointment of an independent counsel to investigate and prosecute possible crimes. Volume II contains indictments, plea agreements, interim reports to Congress and administrative matters from that investigation.

  10. Interim report of the Advisory Committee on human radiation experiments

    SciTech Connect (OSTI)

    Not Available

    1994-10-21T23:59:59.000Z

    The Advisory Committee on Human Radiation Experiments was created by President Clinton to advise the Human Radiation Interagency Working Group on the ethical and scientific criteria applicable to human radiation experiments carried out or sponsored by the U.S. Government. The Committee seeks to answer several fundamental question: What ethics criteria should be used to evaluate human radiation experiments? What was the Federal Government`s role in human radiation experiments? What are the criteria for determining appropriate Federal responses where wrongs or harms have occurred? What lessons learned from studying past and present research standards and practices should be applied to the future? The Committee has been gathering vast amounts of information and working to render it orderly and accessible. In the next six months, the Committee will continue with the tasks of data gathering and organizing. The focus of the work, however, will be developing criteria for judging historical and contemporary experiments, policies, and procedures, as well as criteria for remedies that may be appropriate where harms or wrongs have ocurred. Based on findings, the Committee will make specific recommendations regarding policies for the future.

  11. Results of the mobile gamma scanning activities in Wayne and Pequannock Townships, New Jersey

    SciTech Connect (OSTI)

    Johnson, C.A.; Roberts, D.A.; Patania, V.P.; Foley, R.D.

    1994-01-01T23:59:59.000Z

    During the early 1980s the W. R. Grace site and the adjacent area were the focus of several radiological investigations. Radiological surveys revealed surface radionuclide concentrations greater than those acceptable under US Department of Energy (DOE) remedial action guidelines. In 1984, Congress assigned responsibility for cleanup of the W.R. Grace site to the Department of Energy. The property was redesignated as the Wayne Interim Storage Site (WISS) and in 1985 DOE began plans for survey/monitoring, and remedial action of nearby vicinity properties and the interim storage site. Evaluations of the radiological survey data in 1986 indicated radioactive contamination above current DOE guidelines at the off-site areas of parts of Township Park southwest of WISS, and parts of the Sheffield Brook area and railroad siding in Pequannock Township. Remedial action was conducted over several years of most of these areas and independent verification of remedial action was performed. A team from Oak Ridge National Laboratory conducted a mobile radiological scanning survey of a stretch of public roadway in the immediate vicinity south of the WISS, extending northwest to the Pompton turnpike. A mobile gamma scanning van with an on-board computer system was used to identify at least 24 anomalous areas, some attributable to the naturally elevated levels in concrete, asphalt, and natural granite found in streets, driveways and landscaping materials in the area. Analyses of the biased soil samples taken in the ballpark also revealed slightly elevated thorium concentrations. However, soil concentration measurements when averaged over 100 m{sup 2} fall below the limits prescribed by DOE radiological guidelines established for this site. The anomalies may result from a wide range of sources, such as ash, granite, and fertilizer as well as materials from the former Grace facility.

  12. TurningPoint Evaluation Results

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently AskedEnergyIssuesEnergyTransportation WorkDecember 28, 2004 PartTurning on the Fan

  13. Freeze crystallization technology for black liquor concentration. Second interim report

    SciTech Connect (OSTI)

    Not Available

    1983-07-01T23:59:59.000Z

    The pulp and paper industry is one of the largest consumers of energy. Concentration of black liquor (the stream resulting from the chemical separation of wood fibers in the pulping operation) uses 25% of the purchased energy to produce pulp, an equivalent of 33 million barrels of oil in 1982. Here it is shown that freeze concentration, an emerging concentration technology, has the potential of reducing the energy consumption by at least 45%. This amounts to a cost savings of $5 to $15 per ton of pulp depending on the cost of energy, geographical location, and method of application.

  14. Physical properties of Kraft Black Liquor. Interim report, Phase II

    SciTech Connect (OSTI)

    Fricke, A.L.

    1985-03-01T23:59:59.000Z

    Objectives are to determine the rheological, thermal, and surface properties of Kraft Black Liquors, and to relate these properties to the chemical composition and to pulping conditions. A four-variable, multi-level pulping experiment is being conducted. Pulping results are reported. Complete analyses of the liquors have been done. Thermal analyses have been done. DSC was employed to determine heat capacities of black liquors and lignins. Rheological (viscosity) studies are being conducted. Density and thermal expansion have been studied for seven liquors. Energy savings through more efficient recovery systems are appreciable.

  15. T Tank Farm Interim Surface Barrier Demonstration--Vadose Zone Monitoring Plan

    SciTech Connect (OSTI)

    Zhang, Z. F.; Keller, Jason M.; Strickland, Christopher E.

    2007-04-01T23:59:59.000Z

    The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank in 1973. Many of the contaminants from that leak still reside within the vadose zone beneath the T Tank Farm. CH2M Hill Hanford Group, Inc. seeks to minimize movement of this residual contaminant plume by placing an interim barrier on the surface. Such a barrier is expected to prevent infiltrating water from reaching the plume and moving it further. A plan has been prepared to monitor and determine the effectiveness of the interim surface barrier. Soil water content and water pressure will be monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. In fiscal year 2006, two instrument nests were installed. Each instrument nest contains a neutron probe access tube, a capacitance probe, four heat-dissipation units, and a drain gauge to measure soil water flux. A meteorological station has been installed outside of the fence. In fiscal year 2007, two additional instrument nests are planned to be installed beneath the proposed barrier.

  16. Interim data quality objectives for waste pretreatment and vitrification. Revision 1

    SciTech Connect (OSTI)

    Kupfer, M.J.; Conner, J.M.; Kirkbride, R.A.; Mobley, J.R.

    1994-09-15T23:59:59.000Z

    The Tank Waste Remediation System (TWRS) is responsible for storing, processing, and immobilizing the Hanford Site tank wastes. Characterization information on the tank wastes is needed so that safety concerns can be addressed, and retrieval, pretreatment, and immobilization processes can be designed, permitted, and implemented. This document describes the near-term tank waste sampling and characterization needs of the Pretreatment, High-Level Waste (HLW) Disposal, and Low-Level Waste (LLW) Disposal Programs to support the TWRS disposal mission. The final DQO (Data Quality Objective) will define specific waste tanks to be sampled, sample timing requirements, an appropriate analytical scheme, and a list of required analytes. This interim DQO, however, focuses primarily on the required analytes since the tanks to be sampled in FY 1994 and early FY 1995 are being driven most heavily by other considerations, particularly safety. The major objective of this Interim DQO is to provide guidance for tank waste characterization requirements for samples taken before completion of the final DQO. The characterization data needs defined herein will support the final DQO to help perform the following: Support the TWRS technical strategy by identification of the chemical and physical composition of the waste in the tanks and Guide development efforts to define waste pretreatment processes, which will in turn define HLW and LLW feed to vitrification processes.

  17. Energy policy act transportation study: Interim report on natural gas flows and rates

    SciTech Connect (OSTI)

    NONE

    1995-11-17T23:59:59.000Z

    This report, Energy Policy Act Transportation Study: Interim Report on Natural Gas Flows and Rates, is the second in a series mandated by Title XIII, Section 1340, ``Establishment of Data Base and Study of Transportation Rates,`` of the Energy Policy Act of 1992 (P.L. 102--486). The first report Energy Policy Act Transportation Study: Availability of Data and Studies, was submitted to Congress in October 1993; it summarized data and studies that could be used to address the impact of legislative and regulatory actions on natural gas transportation rates and flow patterns. The current report presents an interim analysis of natural gas transportation rates and distribution patterns for the period from 1988 through 1994. A third and final report addressing the transportation rates and flows through 1997 is due to Congress in October 2000. This analysis relies on currently available data; no new data collection effort was undertaken. The need for the collection of additional data on transportation rates will be further addressed after this report, in consultation with the Congress, industry representatives, and in other public forums.

  18. COMPLETION OF THE FIRST INTEGRATED SPENT NUCLEAR FUEL TRANSSHIPMENT/INTERIM STORAGE FACILITY IN NW RUSSIA

    SciTech Connect (OSTI)

    Dyer, R.S.; Barnes, E.; Snipes, R.L.; Hoeibraaten, S.; Gran, H.C.; Foshaug, E.; Godunov, V.

    2003-02-27T23:59:59.000Z

    Northwest and Far East Russia contain large quantities of unsecured spent nuclear fuel (SNF) from decommissioned submarines that potentially threaten the fragile environments of the surrounding Arctic and North Pacific regions. The majority of the SNF from the Russian Navy, including that from decommissioned nuclear submarines, is currently stored in on-shore and floating storage facilities. Some of the SNF is damaged and stored in an unstable condition. Existing Russian transport infrastructure and reprocessing facilities cannot meet the requirements for moving and reprocessing this amount of fuel. Additional interim storage capacity is required. Most of the existing storage facilities being used in Northwest Russia do not meet health and safety, and physical security requirements. The United States and Norway are currently providing assistance to the Russian Federation (RF) in developing systems for managing these wastes. If these wastes are not properly managed, they could release significant concentrations of radioactivity to these sensitive environments and could become serious global environmental and physical security issues. There are currently three closely-linked trilateral cooperative projects: development of a prototype dual-purpose transport and storage cask for SNF, a cask transshipment interim storage facility, and a fuel drying and cask de-watering system. The prototype cask has been fabricated, successfully tested, and certified. Serial production is now underway in Russia. In addition, the U.S. and Russia are working together to improve the management strategy for nuclear submarine reactor compartments after SNF removal.

  19. Interim Action Proposed Plan for the old radioactive waste burial ground (643-E)

    SciTech Connect (OSTI)

    McFalls, S.

    1995-12-01T23:59:59.000Z

    This Interim Action Proposed (IAPP) is issued by the U.S. Department of Energy (DOE), which functions as the lead agency for SRS remedial activities, and with concurrence by the U.S. Environmental Protection Agency (EPA) and the South Carolina Department of Health and Environmental Control (SCDHEC). The purpose of this IAPP is to describe the preferred interim remedial action for addressing the Old Radioactive Waste Burial Ground (ORWBG) unit located in the Burial Ground Complex (BGC) at the Savannah River Site (SRS) in Aiken, South Carolina. On December 21, 1989, SRS was included on the National Priorities List (NPL). In accordance with Section 120 of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), DOE has negotiated a Federal Facility Agreement (FFA, 1993) with EPA and SCDHEC to coordinate remedial activities at SRS. Public participation requirements are listed in Sections 113 and 117 of CERCLA. These requirements include establishment of an Administrative Record File that documents the selection of remedial alternatives and allows for review and comment by the public regarding those alternatives. The SRS Public Involvement Plan (PIP) (DOE, 1994) is designed to facilitate public involvement in the decision-making process for permitting closure, and the selection of remedial alternatives. Section 117(a) of CERCLA, 1980, as amended, requires publication of a notice of any proposed remedial action.

  20. INTERIM BARRIER AT HANFORDS TY FARM TO PROTECT GROUNDWATER AT THE HANFORD SITE WASHINGTON USA

    SciTech Connect (OSTI)

    PARKER DL; HOLM MJ; HENDERSON JC; LOBER RW

    2011-01-13T23:59:59.000Z

    An innovative interim surface barrier was constructed as a demonstration project at the Hanford Site's TY Tank Farm. The purpose of the demonstration barrier is to stop rainwater and snowmelt from entering the soils within the tank farm and driving contamination from past leaks and spills toward the ground water. The interim barrier was constructed using a modified asphalt material with very low permeability developed by MatCon{reg_sign}. Approximately 2,400 cubic yards of fill material were added to the tank farm to create a sloped surface that will gravity drain precipitation to collection points where it will be routed through buried drain lines to an evapotranspiration basin adjacent to the farm. The evapotranspiration basin is a lined basin with a network of perforated drain lines covered with soil and planted with native grasses. The evapotranspiration concept was selected because it prevents the runoff from percolating into the soil column and also avoids potential monitoring and maintenance issues associated with standing water in a traditional evaporation pond. Because of issues associated with using standard excavation and earth moving equipment in the farm a number of alternate construction approaches were utilized to perform excavations and prepare the site for the modified asphalt.

  1. T Tank Farm Interim Surface Barrier Demonstration - Vadose Zone Monitoring FY08 Report

    SciTech Connect (OSTI)

    Zhang, Z. F.; Strickland, Christopher E.; Field, Jim G.; Parker, Danny L.

    2009-02-01T23:59:59.000Z

    DOE’s Office of River Protection constructed a temporary surface barrier over a portion of the T Tank Farm as part of the T Farm Interim Surface Barrier Demonstration Project. The surface barrier is designed to minimize the infiltration of precipitation into the contaminated soil zone created by the Tank T-106 leak and minimize movement of the contamination. As part of the demonstration effort, vadose zone moisture is being monitored to assess the effectiveness of the barrier at reducing soil moisture. A solar-powered system was installed to continuously monitor soil water conditions at four locations (i.e., instrument Nests A, B, C, and D) beneath the barrier and outside the barrier footprint as well as site meteorological conditions. Nest A is placed in the area outside the barrier footprint and serves as a control, providing subsurface conditions outside the influence of the surface barrier. Nest B provides subsurface measurements to assess surface-barrier edge effects. Nests C and D are used to assess changes in soil-moisture conditions beneath the interim surface barrier.

  2. DEMONSTRATION OF THE DOE INTERIM ENERGY CONSERVATION STANDARDS FOR NEW FEDERAL RESIDENTIAL BUILDINGS: EXECUTIVE SUMMARY

    SciTech Connect (OSTI)

    Lee, A. D.; Baechler, M / C.; Di Massa, F. V.; Lucas, R. G.; Shankle, D. L.

    1992-01-01T23:59:59.000Z

    In accordance with federal legislation, the U.S. Department of Energy (DOE) bas conducted a project to demonstrate use of its Interim Energy Conservation Standards for New Federal Residential Buildings. The demonstration is the second step in a three-step process: development of interim standards, demonstration of the interim standards, and development of final standards. Pacific Northwest Laboratory (PNL) collected information from the demonstration project and prepared this report under a contract with DOE. The purpose of the standards is to improve the energy efficiency of federal housing and increase the use of nondepletable energy sources. In accordance with the legislation, the standards were to be performance-based rather than prescribing specific energy conservation measures. The standards use a computer software program called COSTSAFR which individualizes the standards based on climate, housing type, and fuel costs. The standards generate minimum energy-efficiency requirements by applying the life-cycle cost methodology developed for federal projects, For the demonstration, the DOE chose live federal agency housing projects: four military housing projects and one project for the Department of Health and Human Services. DOE and PNL worked with agency housing procurement officials and designers/architects to hypothetically apply the interim standards to each housing project. PNL conducted extensive interviews with the federal agencies and design contractors to determine what impacts the standards would have on the existing agency procurement process as well as on designers. Overall, PNL found that the interim standards met the basic intent of the law. Specific actions were identified, however, that DOE could take to improve the standards and encourage the agencies to implement them. Agency personnel and designers expressed similar concerns about the standards: the minimum efficiency levels established by the standards were lower than expected and the standards did not provide an easy way to incorporate new energy-efficient and renewable resource tec.:hnolog:ies like solar heating systems. Agency personnel said the standards would fit into current procurement procedures with no big changes or cost increases, Many said the standards would decrease the time and effort they now spend to establish energy-efficiency requirements and to confirm that proposed designs comply with those requirements. Agency personnel praised the software and documentation for being easy to use and providing energy-efficiency requirements in energy dollars. Housing designers agreed that the DOE standards were easy to use to determine that their designs meet energy-efficiency goals. Many felt the information provided by the standards could be useful in the design process. Based on the demonstration, PNL recommends establishing task forces that will actively involve agency personnel and others in future revisions and development of the final standards. PNL also recommends that DOE and federal agencies investigate the use of market fuel and energy prices in the standards, rather than the prices paid by the agencies, to better reflect actual costs. A number of recommendations are made for improving communications between DOE and the users of the standards and for enhancing tools to implement the standards. Several recommendations are made for increasing the number of renewable resources that are included in the standards. Finally, PNL recommends ongoing monitoring activities to continue to identify ways in which the standards can be improved.

  3. Interim report for SNL/NM environmental drilling project

    SciTech Connect (OSTI)

    Wemple, R.P.; Meyer, R.D. [Sandia National Labs., Albuquerque, NM (United States); Layne, R.R. [Charles Machine Works, Inc., Perry, OK (United States)

    1994-02-01T23:59:59.000Z

    Concern for the environment and cost reduction are the driving forces for a broad effort in government and the private sector to develop new, more cost-effective technologies for characterizing, monitoring and remediating environmental sites. Secondary goals of the characterization, monitoring and remediation (CMR) activity are: minimize secondary waste generation, minimize site impact, protect water tables, and develop methods/strategies to apply new technologies. The Sandia National Laboratories (SNL) project in directional boring for CMR of waste sites with enhanced machinery from the underground utility installation industry was initiated in 1990. Preliminary activities included surveying the directional drilling access needs of various DOE sites, identifying an existing class of machinery that could be enhanced for environmental work through development, and establishing a mutually beneficial working relationship with an industry partner. Since that time the project has tested a variety of prototype machinery and hardware built by the industrial partner, and SNL. The project continues to test and develop the machinery and technique refinements needed for future applications at DOE, DOD, and private sector sites. The original goal of cost-effectiveness is being met through innovation, adaptation, and application of fundamental concepts. Secondary goals are being met via a basic philosophy of ``cut/thrust and compact cuttings without adding large quantities of fluid`` to an environmental problem site. Technology transfer to the private sector is ongoing and ultimately should result in commercial availability of the machinery. Education of regulatory agencies resulting in restructuring appropriate regulatory standards for specification of the horizontal drilling techniques will be a final project goal.

  4. INTERIM REPORT ON CONCRETE DEGRADATION MECHANISMS AND ONLINE MONITORING TECHNIQUES

    SciTech Connect (OSTI)

    Mahadevan, Sankaran; Agarwal, Vivek; Neal, Kyle; Kosson, David; Adams, Douglas

    2014-09-01T23:59:59.000Z

    The existing fleets of nuclear power plants in the United States have initial operating licenses of 40 years, though most these plants have applied for and received license extensions. As plant structures, systems, and components age, their useful life—considering both structural integrity and performance—is reduced as a result of deterioration of the materials. The online monitoring of concrete structure conducted under the Advanced Instrumentation, Information, and Control Technologies Pathway of the Light Water Reactor Sustainability program at Idaho National Laboratory will develop and demonstrate concrete structures health monitoring capabilities. Assessment and management of aging concrete structures in nuclear plants require a more systematic approach than simple reliance on existing code margins of safety. Therefore, the structural health monitoring is required to produce actionable information regarding structural integrity that supports operational and maintenance decisions. Through this research project, several national laboratories and Vanderbilt University proposes to develop a framework of research activities for the health monitoring of nuclear power plant concrete structures that includes integration of four elements—damage modeling, monitoring, data analytics, and uncertainty quantification. This report briefly discusses available techniques and ongoing challenges in each of the four elements of the proposed framework with emphasis on degradation mechanisms and online monitoring techniques.

  5. A Comparison of Extra-tropical Cyclones in Recent Re-analyses; ERA-INTERIM, NASA-MERRA,

    E-Print Network [OSTI]

    Hodges, Kevin

    separation of the identically same cyclones is typically less than 20 geodesic in both hemispheresA Comparison of Extra-tropical Cyclones in Recent Re-analyses; ERA-INTERIM, NASA-MERRA, NCEP Corresponding author: Kevin Hodges email: kih@mail.nerc-essc.ac.uk #12;Abstract Extra-tropical cyclones

  6. Results and code predictions for ABCOVE (aerosol behavior code validation and evaluation) aerosol code validation: Test AB6 with two aerosol species. [LMFBR

    SciTech Connect (OSTI)

    Hilliard, R K; McCormack, J C; Muhlestein, L D

    1984-12-01T23:59:59.000Z

    A program for aerosol behavior code validation and evaluation (ABCOVE) has been developed in accordance with the LMFBR Safety Program Plan. The ABCOVE program is a cooperative effort between the USDOE, the USNRC, and their contractor organizations currently involved in aerosol code development, testing or application. The second large-scale test in the ABCOVE program, AB6, was performed in the 850-m/sup 3/ CSTF vessel with a two-species test aerosol. The test conditions simulated the release of a fission product aerosol, NaI, in the presence of a sodium spray fire. Five organizations made pretest predictions of aerosol behavior using seven computer codes. Three of the codes (QUICKM, MAEROS and CONTAIN) were discrete, multiple species codes, while four (HAA-3, HAA-4, HAARM-3 and SOFIA) were log-normal codes which assume uniform coagglomeration of different aerosol species. Detailed test results are presented and compared with the code predictions for seven key aerosol behavior parameters.

  7. PROJECT W-551 DETERMINATION DATA FOR EARLY LAW INTERIM PRETREATMENT SYSTEM SELECTION

    SciTech Connect (OSTI)

    TEDESCHI AR

    2008-08-11T23:59:59.000Z

    This report provides the detailed assessment forms and data for selection of the solids separation and cesium separation technology for project W-551, Interim Pretreatment System. This project will provide early pretreated low activity waste feed to the Waste Treatment Plant to allow Waste Treatment Plan Low Activity Waste facility operation prior to construction completion of the Pretreatment and High Level Waste facilities. The candidate solids separations technologies are rotary microfiltration and crossflow filtration, and the candidate cesium separation technologies are fractional crystallization, caustic-side solvent extraction, and ion-exchange using spherical resorcinol-formaldehyde resin. This data was used to prepare a cross-cutting technology summary, reported in RPP-RPT-37740.

  8. Interim-status groundwater monitoring plan for the 216-B-63 trench. Revision 1

    SciTech Connect (OSTI)

    Sweeney, M.D.

    1995-06-13T23:59:59.000Z

    This document outlines the groundwater monitoring plan for interim-status detection-level monitoring of the 216-B-63 Trench. This is a revision of the initial groundwater monitoring plan prepared for Westinghouse Hanford Company (WHC) by Bjornstad and Dudziak (1989). The 216-B-63 Trench, located at the Hanford Site in south-central Washington State, is an open, unlined, earthern trench approximately 1.2 m (4 ft) wide at the bottom, 427 m (1400 ft) long, and 3 m (10 ft) deep that received wastewater containing hazardous waste and radioactive materials from B Plant, located in the 200 East Area. Liquid effluent discharge to the 216-B-63 Trench began in March 1970 and ceased in February 1992. The trench is now managed by Waste Tank Operations.

  9. PROJECT W-551 SUMMARY INFORMATION FOR EARLY LAW INTERIM PRETREATMENT SYSTEM SELECTION

    SciTech Connect (OSTI)

    TEDESCHI AR

    2008-08-11T23:59:59.000Z

    This report provides summary data for use by the decision board to assess and select the final technology for project W-551, Interim Pretreatment System. This project will provide early pretreated low activity waste feed to the Waste Treatment Plant to allow Waste Treatment Plan Low Activity Waste facility operation prior to construction completion of the Pretreatment and High Level Waste facilities. The candidate solids separations technologies are rotary microfiltration and crossflow filtration, and the candidate cesium separation technologies are fractional crystallization, caustic-side solvent extraction, and ion-exchange using spherical resorcinol-fonnaldebyde resin. This document provides a summary of comparative data against prior weighted criteria to support technology selection. Supporting details and background for this summary are documented in the separate report, RPP-RPT-37741.

  10. Interim storage cask (ISC), a concrete and steel dry storage cask

    SciTech Connect (OSTI)

    Grenier, R.M.; Koploy, M.A. [General Atomics, San Diego, CA (United States)

    1995-12-31T23:59:59.000Z

    General Atomics (GA) has designed and is currently fabricating the Interim Storage Cask (ISC) for Westinghouse Hanford Company (WHC). The ISC is a dry storage cask that will safely store a Core Component Container (CCC) with Fast Flux Test Facility (FFTF) spent fuel assemblies or fuel pin containers for a period of up to 50 years at the US Department of Energy (DOE) Hanford site. The cask may also be used to transfer the fuel to different areas within the Hanford site. The ISC is designed to stringent criteria from both 10CFR71 and 10CFR72 for safe storage and on-site transportation of FFTF spent fuel and fuel pin containers. The cask design uses a combination of steel and concrete materials to achieve a cost-effective means of storing spent fuel. The casks will be extensively tested before use to verify that the design and construction meet the design requirements.

  11. Energy conservation potential of the US Department of Energy interim commercial building standards

    SciTech Connect (OSTI)

    Hadley, D.L.; Halverson, M.A.

    1993-12-01T23:59:59.000Z

    This report describes a project conducted to demonstrate the whole-building energy conservation potential achievable from full implementation of the US Department of Energy (DOE) Interim Energy Conservation Performance Standards for New Commercial and Multi-Family High Rise Residential Buildings. DOE`s development and implementation of energy performance standards for commercial buildings were established by the Energy Conservation Standards for New Buildings Act of 1976, as amended, Public Law (PL) 94-385, 42 USC 6831 et seq., hereinafter referred to as the Act. In accordance with the Act, DOE was to establish performance standards for both federal and private sector buildings ``to achieve the maximum practicable improvements in energy efficiency and use of non-depletable resources for all new buildings``.

  12. Interim Status Closure Plan Open Burning Treatment Unit Technical Area 16-399 Burn Tray

    SciTech Connect (OSTI)

    Vigil-Holterman, Luciana R. [Los Alamos National Laboratory

    2012-05-07T23:59:59.000Z

    This closure plan describes the activities necessary to close one of the interim status hazardous waste open burning treatment units at Technical Area (TA) 16 at the Los Alamos National Laboratory (LANL or the Facility), hereinafter referred to as the 'TA-16-399 Burn Tray' or 'the unit'. The information provided in this closure plan addresses the closure requirements specified in the Code of Federal Regulations (CFR), Title 40, Part 265, Subparts G and P for the thermal treatment units operated at the Facility under the Resource Conservation and Recovery Act (RCRA) and the New Mexico Hazardous Waste Act. Closure of the open burning treatment unit will be completed in accordance with Section 4.1 of this closure plan.

  13. Interim Safe Storage of Plutonium Production Reactors at the US DOE Hanford Site - 13438

    SciTech Connect (OSTI)

    Schilperoort, Daryl L.; Faulk, Darrin [Washington Closure Hanford, 2620 Fermi Avenue, Richland, Washington 99352 (United States)] [Washington Closure Hanford, 2620 Fermi Avenue, Richland, Washington 99352 (United States)

    2013-07-01T23:59:59.000Z

    Nine plutonium production reactors located on DOE's Hanford Site are being placed into an Interim Safe Storage (ISS) period that extends to 2068. The Environmental Impact Statement (EIS) for ISS [1] was completed in 1993 and proposed a 75-year storage period that began when the EIS was finalized. Remote electronic monitoring of the temperature and water level alarms inside the safe storage enclosure (SSE) with visual inspection inside the SSE every 5 years are the only planned operational activities during this ISS period. At the end of the ISS period, the reactor cores will be removed intact and buried in a landfill on the Hanford Site. The ISS period allows for radioactive decay of isotopes, primarily Co-60 and Cs-137, to reduce the dose exposure during disposal of the reactor cores. Six of the nine reactors have been placed into ISS by having an SSE constructed around the reactor core. (authors)

  14. Interim report on the Causes of and Circumstances attending the Explosion which occured at Whitehaven William Colliery, Cumberland, on the 15th August, 1947 

    E-Print Network [OSTI]

    Bryan, A. M.

    MINISTRY OF FUEL AND POWER INTERIM REPORT On the Causes of and Circumstances attending the Explosion which occurred at Whitehaven "William" Colliery, Cumberland, on the 15th August, 1947 By A. M. BRYAN, Esq., J.P., ...

  15. Interim Report: 100-NR-2 Apatite Treatability Test: Low Concentration Calcium Citrate-Phosphate Solution Injection for In Situ Strontium-90 Immobilization

    SciTech Connect (OSTI)

    Williams, Mark D.; Fritz, Brad G.; Mendoza, Donaldo P.; Rockhold, Mark L.; Thorne, Paul D.; Xie, YuLong; Bjornstad, Bruce N.; Mackley, Rob D.; Newcomer, Darrell R.; Szecsody, James E.; Vermeul, Vincent R.

    2008-07-11T23:59:59.000Z

    Following an evaluation of potential Sr-90 treatment technologies and their applicability under 100-NR-2 hydrogeologic conditions, U.S. Department of Energy, Fluor Hanford, Inc., Pacific Northwest National Laboratory, and the Washington Department of Ecology agreed that the long-term strategy for groundwater remediation at 100-N Area will include apatite sequestration as the primary treatment, followed by a secondary treatment if necessary (most likely phytoremediation). Since then, the agencies have worked together to agree on which apatite sequestration technology has the greatest chance of reducing Sr-90 flux to the river at a reasonable cost. In July 2005, aqueous injection, (i.e., the introduction of apatite-forming chemicals into the subsurface) was endorsed as the interim remedy and selected for field testing. Studies are in progress to assess the efficacy of in situ apatite formation by aqueous solution injection to address both the vadose zone and the shallow aquifer along the 300 ft of shoreline where Sr-90 concentrations are highest. This report describes the field testing of the shallow aquifer treatment.

  16. Environmental effects of dredging. Interim results: The relationship between sediment organic carbon and biological uptake of contaminants. Technical note

    SciTech Connect (OSTI)

    Brannon, J.M.; Price, C.B.; Reilly, F.J.

    1991-11-01T23:59:59.000Z

    This technical note describes testing conducted to determine the partitioning of contaminants between sediment organic carbon and sediment interstitial water, assess the effects of sediment organic carbon upon bioaccumulation of a selected polychlorinated biphenyl (PCB) and polycyclic aromatic hydrocarbon (PAH) by two organisms, and investigate the accuracy of the apparent preference factor as a predictive tool by comparing predicted uptake with actual uptake.

  17. Interim Project Results: United Parcel Service's Second-Generation Hybrid-Electric Delivery Vans (Fact Sheet), Vehicle Technologies Program (VTP)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHigh SchoolIn Other NewsSpinInteragency PanelIntergovernmentalAs part of

  18. 2H2A Hydrogen Delivery Infrastructure Analysis Models and Conventional Pathway Options Analysis Results - Interim Report

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny: The Future of BadTHEEnergyReliability2015 Peer Review. d r a m a1, in:

  19. Hurricane Andrew's impact on natural gas and oil facilities on the outer continental shelf (interim report as of November 1993)

    SciTech Connect (OSTI)

    Daniels, G.R.

    1994-01-01T23:59:59.000Z

    The interim report reviews Hurricane Andrew's impact on Federal Outer Continental Shelf (OCS) natural gas and oil drilling and production facilities. The report provides background on Hurricane Andrew's progression, discusses how OCS operators responded to the storm, summarizes the types of damage to offshore facilies caused by Hurricane Andrew, and discusses Minerals Management Service's continuing damage assessment and repair efforts. The summaries of damage estimates are presented in tables in Appendix 1. A glossary of report terminology is provided in Appendix 2.

  20. RCRA, superfund and EPCRA hotline training module. Introduction to: Permits and interim status (40 cfr part 270) updated July 1996

    SciTech Connect (OSTI)

    NONE

    1996-07-01T23:59:59.000Z

    Owners/operators of facilities that treat, store, or dispose of hazardous waste must obtain an operating permit, as required by Subtitle C of the Resource Conservation and Recovery Act (RCRA). The module presents an overview of the RCRA permitting process and the requirements that apply to TSDFs operating under interim status until a permit is issued. The regulations governing the permit process are found in 40 CFR Parts 124 through 270.

  1. Wayne Interim Storage Site environmental report for calendar year 1992, 868 Black Oak Ridge Road, Wayne, New Jersey. Formerly Utilized Sites Remedial Action Program (FUSRAP)

    SciTech Connect (OSTI)

    Not Available

    1993-05-01T23:59:59.000Z

    This report describes the environmental surveillance program at the Wayne Interim Storage Site (WISS) and provides the results for 1992. The fenced, site, 32 km (20 mi) northwest of Newark, New Jersey, was used between 1948 and 1971 for commercial processing of monazite sand to separate natural radioisotopes - predominantly thorium. Environmental surveillance of WISS began in 1984 in accordance with Department of Energy (DOE) Order 5400.1 when Congress added the site to DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). The environmental surveillance program at WISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; radium-226, radium-228, thorium-230, thorium-232, total uranium, and several chemicals in surface water and sediment; and total uranium, radium-226, radium-228, thorium-230, thorium-232, and organic and inorganic chemicals in groundwater. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. This monitoring program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results for environmental surveillance in 1992 show that the concentrations of all radioactive and most chemical contaminants were below applicable standards.

  2. Physiologic Responses to Acupuncture Point Stimulation: A Pilot Study to Evaluate Methods and

    E-Print Network [OSTI]

    , and electrodermal response (EDR) were measured along with the times of needle insertion, interim needle stimulation and electrodermal responses (EDR) [1]­[12]. The results of these individual studies, in which commonly used APs] determined that activation of an auricular AP decreased a stimulus-induced EDR while Wang and Cain [13

  3. Colonie Interim Storage Site environmental report for calendar year 1992, 1130 Central Avenue, Colonie, New York. Formerly Utilized Sites Remedial Action Program (FUSRAP)

    SciTech Connect (OSTI)

    Not Available

    1993-05-01T23:59:59.000Z

    This report describes the environmental surveillance program at the Colonie Interim Storage Site (CISS) and provides the results for 1992. The site is located in eastern New York State, approximately 6.4 km (4.0 mi) northwest of downtown Albany. From 1958 to 1984, National Lead (NL) Industries used the facility to manufacture various components from depleted and enriched uranium natural thorium. Environmental monitoring of CISS began in 1984 when Congress added, the site to the US Department of Energy`s (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a program established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental surveillance program at CISS includes sampling networks for external gamma radiation exposure and for thorium-232 and total uranium concentrations in surface water, sediment, and groundwater. Several chemical parameters are also measured in groundwater, including total metals, volatile organics, and water quality parameters. This surveillance program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results are compared with applicable Environmental Protection Agency (EPA) and New York State Department of Environmental Conservation (NYSDEC) standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements.

  4. Maywood Interim Storage Site environmental report for calendar year 1992, 100 West Hunter Avenue, Maywood, New Jersey. Formerly Utilized Sites Remedial Action Program (FUSRAP)

    SciTech Connect (OSTI)

    Not Available

    1993-05-01T23:59:59.000Z

    This report describes the environmental surveillance program at the Maywood Interim Storage Site (MISS) and provides the results for 1992. Environmental monitoring of MISS began in 1984, when the site was assigned to DOE by Congress through the Energy and Water Development Appropriations Act and was placed under DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. MISS is part of a National Priorities List (NPL) site. The environmental surveillance program at MISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium in surface water, sediment, and groundwater. Additionally, chemical analysis includes metals and organic compounds in surface water and groundwater and metals in sediments. This program assists in fulfilling the DOE objective of measuring and monitoring effluents from DOE activities and calculating hypothetical doses to members of the general public. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. Environmental standards are established to protect public health and the environment. The radiological data for all media sampled support the conclusion that doses to the public are not distinguishable from natural background radiation.

  5. Hazard evaluation for transfer of waste from tank 241-SY-101 to tank 241-SY-102

    SciTech Connect (OSTI)

    SHULTZ, M.V.

    1999-02-12T23:59:59.000Z

    Tank 241-SY-101 (SY-101) waste level growth is an emergent, high priority issue. The purpose of this document is to record the hazards evaluation process and document potential hazardous conditions that could lead to the release of radiological and toxicological material from the proposed transfer of a limited quantity (approximately 100,000 gallons) of waste from SY-101 to 241-SY-102 (SY-102). The results of the hazards evaluation will be compared to the current Tank Waste Remediation System (TWRS) Basis for Interim Operation (HNF-SD-WM-BIO-001, 1998, Revision 1) to identify any hazardous conditions where Authorization Basis (AB) controls may not be sufficient or may not exist. Comparison to LA-UR-92-3196, A Safety Assessment for Proposed Pump Mixing Operations to Mitigate Episodic Gas Releases in Tank 241-SY-101, was also made in the case of transfer pump removal activities. This document is not intended to authorize the activity or determine the adequacy of controls; it is only intended to provide information about the hazardous conditions associated with this activity. The Unreviewed Safety Question (USQ) process will be used to determine the adequacy of controls and whether the proposed activity is within the AB. This hazard evaluation does not constitute an accident analysis.

  6. Hazard evaluation for transfer of waste from tank 241-SY-101 to tank 241-SY-102

    SciTech Connect (OSTI)

    SHULTZ, M.V.

    1999-04-05T23:59:59.000Z

    Tank 241-SY-101 waste level growth is an emergent, high priority issue. The purpose of this document is to record the hazards evaluation process and document potential hazardous conditions that could lead to the release of radiological and toxicological material from the proposed transfer of a limited quantity (approximately 100,000 gallons) of waste from Tank 241-SY-101 to Tank 241-SY-102. The results of the hazards evaluation were compared to the current Tank Waste Remediation System (TWRS) Basis for Interim Operation (HNF-SD-WM-BIO-001, 1998, Revision 1) to identify any hazardous conditions where Authorization Basis (AB) controls may not be sufficient or may not exist. Comparison to LA-UR-92-3196, A Safety Assessment for Proposed Pump Mixing Operations to Mitigate Episodic Gas Releases in Tank 241-SY-101, was also made in the case of transfer pump removal activities. Revision 1 of this document deletes hazardous conditions no longer applicable to the current waste transfer design and incorporates hazardous conditions related to the use of an above ground pump pit and overground transfer line. This document is not part of the AB and is not a vehicle for requesting authorization of the activity; it is only intended to provide information about the hazardous conditions associated with this activity. The AB Control Decision process will be used to determine the adequacy of controls and whether the proposed activity is within the AB. This hazard evaluation does not constitute an accident analysis.

  7. Evaluation of a complex intervention for depression in patients with lung cancer: the design, execution and results of a randomised controlled trial. 

    E-Print Network [OSTI]

    Walker, Jane

    2014-07-05T23:59:59.000Z

    The aim of this thesis was to develop and evaluate a complex intervention for major depression in patients with lung cancer. Major depression is a leading cause of disease burden worldwide and is particularly important ...

  8. Power Transfer Potential to the Southeast in Response to a Renewable Portfolio Standard: Interim Report 1

    SciTech Connect (OSTI)

    Hadley, Stanton W [ORNL; Key, Thomas S [Electric Power Research Institute (EPRI)

    2009-03-01T23:59:59.000Z

    The power transfer potential for bringing renewable energy into the Southeast in response to a renewable portfolio standard (RPS) will depend not only on available transmission capacity but also on electricity supply and demand factors. This interim report examines how the commonly used EIA NEMS and EPRI NESSIE energy equilibrium models are considering such power transfers. Using regional estimates of capacity expansion and demand, a base case for 2008, 2020 and 2030 are compared relative to generation mix, renewable deployments, planned power transfers, and meeting RPS goals. The needed amounts of regional renewable energy to comply with possible RPS levels are compared to inter-regional transmission capacities to establish a baseline available for import into the Southeast and other regions. Gaps in the renewable generation available to meet RPS requirements are calculated. The initial finding is that the physical capability for transferring renewable energy into the SE is only about 10% of what would be required to meet a 20% RPS. Issues that need to be addressed in future tasks with respect to modeling are the current limitations for expanding renewable capacity and generation in one region to meet the demand in another and the details on transmission corridors required to deliver the power.

  9. Interim report:feasibility of microscale glucose reforming for renewable hydrogen.

    SciTech Connect (OSTI)

    Norman, Kirsten (New Mexico Institute of Mining and Technology, Socorro, NM)

    2007-03-01T23:59:59.000Z

    Micro-scale aqueous steam reforming of glucose is suggested as a novel method of H{sub 2} production for micro fuel cells. Compact fuel cell systems are a viable alternative to batteries as a portable electrical power source. Compared with conventional lithium polymer batteries, hydrocarbon powered fuel cells are smaller, weigh less, and have a much higher energy density. The goal of this project is to develop a hydrocarbon powered microfuel processor capable of driving an existing microfuel cell, and this interim report provides a summary of the engineering information for microscale reforming of carbohydrates and the summarizes the work completed as of September 2006. Work on this program will continue. Gas analysis of the gas evolved from glucose breakdown using a quadrupole mass spectrometer is now possible due do significant modifications to the vacuum chamber and to the mass spectrometer electronics. Effective adhesion of Pt/Al{sub 2}O{sub 3} to 316SS microstructured catalyst plates is still under investigation. Electrophoretic and dip coat methods of catalyst deposition have produced coatings with poor adhesion and limited available Pt surface area.

  10. Resource Conservation and Recovery Act (RCRA) Closure Plan Summary for Interim reasctive Waste Treatment Area (IRWTA)

    SciTech Connect (OSTI)

    Collins, E.T.

    1997-07-01T23:59:59.000Z

    This closure plan has been prepared for the interim Reactive Waste Treatment Area (IRWT'A) located at the Y-12 Pkmt in oak Ridge, Tennessee (Environmental Protection Agency [EPA] Identification TN 389-009-0001). The actions required to achieve closure of the IRWTA are outlined in this plan, which is being submitted in accordance with Tennessee Ruie 1200- 1-1 1-.0S(7) and Title 40, Code of Federal Regulations (CFR), Part 265, Subpart G. The IRWTA was used to treat waste sodium and potassium (NaK) that are regulated by the Resource Conservation and Recovery Act (RCRA). The location of the IRWT'A is shown in Figures 1 and 2, and a diagram is shown in Figure 3. This pkm details all steps that wdi be petiormed to close the IRWTA. Note that this is a fmai ciosure.and a diagram is shown in Figure 3. This pkm details all steps that wdi be petiormed to close the IRWTA. Note that this is a fmai ciosure.

  11. Hybrid energy storage test procedures and high power battery project FY-1995 interim report

    SciTech Connect (OSTI)

    Hunt, G.L.

    1995-12-01T23:59:59.000Z

    Near the end of FY 1994, DOE provided funding and guidance to INEL for two separate but closely related tasks involving high power energy storage technology. One task was intended to develop and refine application-specific test procedures appropriate to high power energy storage devices for potential use in hybrid vehicles, including batteries, ultracapacitors, flywheels, and similar devices. The second task was intended to characterize the high power capabilities of presently available battery technologies, as well as eventually to evaluate the potential high power capabilities of advanced battery technologies such as those being developed by the USABC. Since the evaluation of such technologies is necessarily dependent to some extent on the availability of appropriate test methods, these two tasks have been closely coordinated. This report is intended to summarize the activities and results for both tasks accomplished during FY-1995.

  12. Postconstruction report for the mercury tanks interim action at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Voskuil, T.L.

    1993-09-01T23:59:59.000Z

    Three underground concrete settling tanks (tanks 2101-U, 2104-U, and 2100-U) at the Y-12 Plant on the Oak Ridge Reservation in Oak Ridge, Tennessee, contained contaminated sludges contributing mercury to the Upper East Fork Poplar Creek (UEFPC). These tanks were cleaned out as an interim action under the Comprehensive Environmental Response, Compensation, and Liability Act as part of the Reduction of Mercury in Plant Effluent subproject. Cleaning out these tanks prevented the sludge that had settled in the bottom from resuspending and carrying mercury into UEFPC. Tanks 2104-U and 2100-U were returned to service and will continue to receive effluent from buildings 9201-4 and 9201-5. Tank 2101-U had been abandoned and its effluent redirected to Tank 2100-U during previous activities. This interim action permanently sealed Tank 2101-U from the storm sewer system. Upon removal of materials and completion of cleanup, inspections determined that the project`s cleanup criteria had been met. The structural integrity of the tanks was also inspected, and minor cracks identified in tanks 2101-U and 2104-U were repaired. This project is considered to have been completed successfully because it met its performance objectives as addressed in the Interim Record of Decision and the work plan: to remove the waste from the three storage tanks; to ensure that the tanks were cleaned to the levels specified; to return tanks 2100-U and 2104-U to service; to isolate Tank 2101-U permanently; and to manage the wastes in an appropriate fashion.

  13. Interim measure conceptual design for remediation of source area contamination at Agra, Kansas.

    SciTech Connect (OSTI)

    LaFreniere, L. M.; Environmental Science Division

    2007-07-31T23:59:59.000Z

    This document presents a conceptual design for the implementation of a non-emergency interim measure (IM) at the site of the grain storage facility formerly operated by the Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) in Agra, Kansas. The IM is recommended to mitigate localized carbon tetrachloride contamination in the vadose zone soils at the former CCC/USDA facility and eliminate ongoing soil-to-groundwater contamination. The objectives of this IM conceptual design report include the following: 1. Obtain written acknowledgement from the Kansas Department of Health and the Environment (KDHE) that remediation on the former CCC/USDA property is required. 2. Provide information (IM description, justification for the IM, and project schedule) that the KDHE can include in a pending fact sheet. 3. Obtain KDHE approval for the IM conceptual design, so that the CCC/USDA can initiate a formal request for access to the privately owned property and proceed with preparation of a remedial design plan (RDP). Investigations conducted on behalf of the CCC/USDA by Argonne National Laboratory (Argonne 2006) have demonstrated that soil and groundwater at the Agra site are contaminated with carbon tetrachloride. The levels in groundwater exceed the Kansas Tier 2 Risk-Based Screening Level (RBSL) and the U.S. Environmental Protection Agency (EPA) maximum contaminant level (MCL) of 5.0 {micro}g/L for this compound. The soil and groundwater contamination identified at the former CCC/USDA facility currently poses no unacceptable health risks.

  14. Interim Report on Consumer Acceptance, Retention, and response to Time-based rates from the Consumer Behavior Studies

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment of EnergyIndustry15Among States in theWAPA1Interim Final

  15. Gen IV Nuclear Energy Systems Interim Status Report on Pre-conceptual LFR Design Studies and Evaluations

    SciTech Connect (OSTI)

    Halsey, W G; Brown, N W; Smith, C F; Sienicki, J J; Moisseytsev, A V; Kim, S J; Smith, M A; Yang, W S; Williamson, M; Li, N

    2005-02-09T23:59:59.000Z

    Previous pre-conceptual core neutronics and system thermal hydraulics calculations initiated the investigation of viability of a Small Secure Transportable Autonomous Reactor (SSTAR) lead-cooled small modular fast reactor concept.1 The calculations indicated that a single-phase natural circulation SSTAR reactor concept with good core reactor physics performance, good system thermal hydraulics performance, and a high Supercritical Carbon Dioxide (S-CO{sub 2}) Brayton cycle efficiency of 40 % may be viable at an electrical power of 18 MWe (45 MWt). Pre-conceptual studies of SSTAR viability have continued with the objective of improving the system thermal hydraulic performance and raising the plant efficiency as well as extending the neutronics analysis. This effort has been motivated by several considerations. First, the initial Pre-conceptual studies were focused upon a ''pancake'' core having a height-to-diameter of 0.5. It was found that a compact core with high average burn up could be realized with a height-to-diameter ratio of 0.8. Second, the initial assumed reactor vessel height of 12.2 meters limited the height of the Pb-to-CO{sub 2} in-reactor heat exchangers (HXs) which reduced the efficiency of supercritical carbon dioxide (S-CO2) Brayton cycle power converter. It was found that by increasing the reactor vessel height to 18 meters, the greater driving head for single-phase natural circulation would offset both the greater pressure drop of the 0.8 height-to-diameter ratio core as well as the pressure drop of taller HXs. This has enabled the plant efficiency to be increased from 40 to 43 % and the plant electrical power to be raised from 18 to 20 MWe. Third, reactivity feedback coefficients, which had previously not been generated for SSTAR, have now been calculated for the core. The reactivity feedback coefficients provide a basis for future investigation of the autonomous load following and passive shutdown behavior of the reactor. The current status of SSTAR and the Pre-conceptual viability studies are described below.

  16. Interim reliability evaluation program: analysis of the Arkansas Nuclear One. Unit 1 nuclear power plant. Volume 2 of 2

    SciTech Connect (OSTI)

    Kolb, G.J.

    1982-06-01T23:59:59.000Z

    Appendices are presented concerning systemic event tree analysis; analysis of the ANO-1 front-line and support systems; high pressure injection/high pressure recirculation system; low pressure injection/low pressure recirculation system; core flood system; reactor building spray system; emergency feedwater system; reactor building cooling system; reactor protection system; power conversion system; engineered safeguards activation system; service water system; class 1E AC power system; 125 volt DC system; battery and switchgear emergency cooling system; emergency feedwater initiation and control system; human interface system; sequence quantification; and supporting calculations.

  17. Performance of Trasuranic-Loaded Fully Ceramic Micro-Encapsulated Fuel in LWRs Interim Report, Including Void Reactivity Evaluation

    SciTech Connect (OSTI)

    Michael A. Pope; Brian Boer; Gilles Youinou; Abderrafi M. Ougouag

    2011-03-01T23:59:59.000Z

    The current focus of the Deep Burn Project is on once-through burning of transuranice (TRU) in light water reactors (LWRs). The fuel form is called Fully-Ceramic Micro-encapsulated (FCM) fuel, a concept that borrows the tri-isotropic (TRISO) fuel particle design from high-temperature reactor technology. In the Deep Burn LWR (DB-LWR) concept, these fuel particles would be pressed into compacts using SiC matrix material and loaded into fuel pins for use in conventional LWRs. The TRU loading comes from the spent fuel of a conventional LWR after 5 years of cooling. Unit cell calculations have been performed using the DRAGON-4 code in order assess the physics attributes of TRU-only FCM fuel in an LWR lattice. Depletion calculations assuming an infinite lattice condition were performed with calculations of various reactivity coefficients performed at each step. Unit cells containing typical UO2 and MOX fuel were analyzed in the same way to provide a baseline against which to compare the TRU-only FCM fuel. Loading of TRU-only FCM fuel into a pin without significant quantities of uranium challenges the design from the standpoint of several key reactivity parameters, particularly void reactivity, and to some degree, the Doppler coefficient. These unit cells, while providing an indication of how a whole core of similar fuel would behave, also provide information of how individual pins of TRU-only FCM fuel would influence the reactivity behavior of a heterogeneous assembly. If these FCM fuel pins are included in a heterogeneous assembly with LEU fuel pins, the overall reactivity behavior would be dominated by the uranium pins while attractive TRU destruction performance of the TRU-only FCM fuel pins may be preserved. A configuration such as this would be similar to CONFU assemblies analyzed in previous studies. Analogous to the plutonium content limits imposed on MOX fuel, some amount of TRU-only FCM pins in an otherwise-uranium fuel assembly may give acceptable reactivity performance. Assembly calculations will be performed in future work to explore the design options for heterogeneous assemblies of this type and their impact on reactivity coefficients.

  18. Methodology for the evaluation of a 4000-home geothermal heat pump retrofit at Fort Polk, Louisiana

    SciTech Connect (OSTI)

    Hughes, P.J.; Shonder, J.A.; White, D.L.; Huang, H.L.

    1998-03-01T23:59:59.000Z

    The US Army and a private energy service company are developing a comprehensive energy efficiency project to upgrade the family housing at Fort Polk, Louisiana. The project includes converting the space conditioning systems of more than 4,000 housing units to geothermal (or ground-source) heat pumps (GHPs). This interim report describes the methodology of the evaluation associated with this project, including the field monitoring that has been conducted at the base.

  19. Interim Models Developed to Predict Key Hanford Waste Glass Properties Using Composition

    SciTech Connect (OSTI)

    Vienna, John D.; Kim, Dong-Sang; Hrma, Pavel R.

    2003-08-08T23:59:59.000Z

    Over the past several years the amount of waste glass property data available in the open literature has increased markedly. We have compiled the data from over 2000 glass compositions, evaluated the data for consistency, and fit glass property models to portions of this database.[1] The properties modeled include normalized releases of boron (rB), sodium (rNa), and lithium (rLi) from glass exposed to the product consistency test (PCT), liquidus temperature (TL) of glasses in the spinel and zircon primary phase field, viscosity (?) at 1150°C (?1150) and as a function of temperature (?T), and molar volume (V). These models were compared to some of the previously available models and were found to predict the properties of glasses not used in model fitting better and covered broader glass composition regions than the previous ones. This paper summarizes the data collected and the models that resulted from this effort.

  20. TAILORING INORGANIC SORBENTS FOR SRS STRONTIUM AND ACTINIDE SEPARATIONS: OPTIMIZED MONOSODIUM TITANATEPHASE II INTERIM REPORT FOR EXTERNAL RELEASE

    SciTech Connect (OSTI)

    Hobbs, D; Michael Poirier, M; Mark Barnes, M; Mary Thompson, M

    2006-08-31T23:59:59.000Z

    This document provides an interim summary report of Phase II testing activities for the development of a modified monosodium titanate (MST) that exhibits improved strontium and actinide removal characteristics compared to the baseline MST materials. The activities included determining the key synthesis conditions for preparation of the modified MST, preparation of the modified MST at a larger laboratory scale, demonstration of the strontium and actinide removal characteristics with actual tank waste supernate and characterization of the modified MST. Key findings and conclusions include the following: (1) Samples of the modified MST prepared by Method 2 and Method 3 exhibited the best combination of strontium and actinide removal. (2) We selected Method 3 to scale up and test performance with actual waste solution. (3) We successfully prepared three batches of the modified MST using the Method 3 procedure at a 25-gram scale. (4) Performance tests indicated successful scale-up to the 25-gram scale with excellent performance and reproducibility among each of the three batches. For example, the plutonium decontamination factors (6-hour contact time) for the modified MST samples averaged 13 times higher than that of the baseline MST sample at half the sorbent concentration (0.2 g L{sup -1} for modified MST versus 0.4 g L{sup -1} for baseline MST). (5) Performance tests with actual waste supernate demonstrated that the modified MST exhibited better strontium and plutonium removal performance than that of the baseline MST. For example, the decontamination factors for the modified MST measured 2.6 times higher for strontium and between 5.2 to 11 times higher for plutonium compared to the baseline MST sample. The modified MST did not exhibit improved neptunium removal performance over that of the baseline MST. (6) Two strikes of the modified MST provided increased removal of strontium and actinides from actual waste compared to a single strike. The improved performance exhibited by the modified MST indicates that fewer strikes of the modified MST would be needed to successfully treat waste that contain very high activities of {sup 90}Sr and alpha-emitting radionuclides compared to the baseline MST. (7) Reuse tests with actual waste confirmed that partially loaded MST exhibits reduced removal of strontium and actinides when contacted with fresh waste. (8) Samples of modified MST prepared by Method 3 and the baseline MST exhibited very similar particle size distributions. (9) Dead-end filtration tests showed that the modified MST samples exhibited similar filtration characteristics as the baseline MST sample. (10) Performance testing indicated no change in strontium and neptunium removal after storing the modified MST for 6-months at ambient temperature. The results suggested that plutonium removal performance may be decreased slightly after 6-months of storage. However, the change in plutonium removal is not statistically significant at the 95% confidence limit. Based on these findings we recommend continued development of the modified MST as a replacement for the baseline MST for waste treatment facilities at the Savannah River Site.

  1. Application of the CALIOP Layer Product to Evaluate the Vertical Distribution of Aerosols Estimated by Global Models: AeroCom Phase I Results

    SciTech Connect (OSTI)

    Koffi, Brigitte; Schultz, Michael; Breon, Francois-Marie; Griesfeller, Jan; Winker, D.; Balkanski, Y.; Bauer, Susanne E.; Berntsen, T.; Chin, Mian; Collins, William D.; Dentener, Frank; Diehl, Thomas; Easter, Richard C.; Ghan, Steven J.; Ginoux, P.; Gong, S.; Horowitz, L.; Iversen, T.; Kirkevag, A.; Koch, Dorothy; Krol, Maarten; Myhre, G.; Stier, P.; Takemura, T.

    2012-05-19T23:59:59.000Z

    The CALIOP (Cloud-Aerosol Lidar with Orthogonal Polarization) layer product is used for a multimodel evaluation of the vertical distribution of aerosols. Annual and seasonal aerosol extinction profiles are analyzed over 13 sub-continental regions representative of industrial, dust, and biomass burning pollution, from CALIOP 2007-2009 observations and from AeroCom (Aerosol Comparisons between Observations and Models) 2000 simulations. An extinction mean height diagnostic (Z{sub a}) is defined to quantitatively assess the models performance. It is calculated over the 0-6 km and 0-10 km altitude ranges by weighting the altitude of each 100 m altitude layer by its aerosol extinction coefficient. The mean extinction profiles derived from CALIOP layer products provide consistent regional and seasonal specificities and a low inter-annual variability. While the outputs from most models are significantly correlated with the observed Z{sub a} climatologies, some do better than others, and 2 of the 12 models perform particularly well in all seasons. Over industrial and maritime regions, most models show higher Z{sub a} than observed by CALIOP, whereas over the African and Chinese dust source regions, Z{sub a} is underestimated during Northern Hemisphere Spring and Summer. The positive model bias in Z{sub a} is mainly due to an overestimate of the extinction above 6 km. Potential CALIOP and model limitations, and methodological factors that might contribute to the differences are discussed.

  2. Return-on-investment indicators for energy program evaluation. Results of the technical review of TA reports and grant applications: Cycle VII - ICP. Final report

    SciTech Connect (OSTI)

    Not Available

    1985-09-17T23:59:59.000Z

    The state of Michigan technical review evaluted about forty-five grantees. The reviewers at the state level seem to have screened out bad submissions or illogical calculation sequences. Michigan reviewers were careful to a fault, and at times had gone through and recalculated many of the smaller energy savings ECM's so that the submission could in fact progress towards the federal level at an appropriate speed. The depth of analysis was very good and the coverage was certainly adequate. There were no submissions in the state of Michigan which warrant detailed commentary about their lack of any part of the submission. The state of Indiana had approximately 33 grantee submissions. The federal level technical review looked at each and every submission to see if it met criteria and calculation adequacy. In many cases the state of Indiana showed evidence of not having had adequate state review. Certainly there were no marks, corrections of any kind in most of the submitted documentation. It is apparent that the state of Indiana will warrant continuous evaluation over the next few cycles in order to upgrade their overall review of their grants. It is suggested that some help be given to the Indiana review agency. The technical reviewers for Cycle VII suggest a continuation of the review process for Indiana, and some additional support to aid them in the review function at the state level to insure that the state reviewers are not skimming the projects at an inadequate level.

  3. Fresh Water Generation from Aquifer-Pressured Carbon Storage: Interim Progress Report

    SciTech Connect (OSTI)

    Aines, R D; Wolery, T J; Hao, Y; Bourcier, W L

    2009-07-22T23:59:59.000Z

    This project is establishing the potential for using brine pressurized by Carbon Capture and Storage (CCS) operations in saline formations as the feedstock for desalination and water treatment technologies including nanofiltration (NF) and reverse osmosis (RO). The aquifer pressure resulting from the energy required to inject the carbon dioxide provides all or part of the inlet pressure for the desalination system. Residual brine would be reinjected into the formation at net volume reduction. This process provides additional storage space (capacity) in the aquifer, reduces operational risks by relieving overpressure in the aquifer, and provides a source of low-cost fresh water to offset costs or operational water needs. Computer modeling and laboratory-scale experimentation are being used to examine mineral scaling and osmotic pressure limitations for brines typical of CCS sites. Computer modeling is being used to evaluate processes in the aquifer, including the evolution of the pressure field. This progress report deals mainly with our geochemical modeling of high-salinity brines and covers the first six months of project execution (September, 2008 to March, 2009). Costs and implementation results will be presented in the annual report. The brines typical of sequestration sites can be several times more concentrated than seawater, requiring specialized modeling codes typical of those developed for nuclear waste disposal calculations. The osmotic pressure developed as the brines are concentrated is of particular concern, as are precipitates that can cause fouling of reverse osmosis membranes and other types of membranes (e.g., NF). We have now completed the development associated with tasks (1) and (2) of the work plan. We now have a contract with Perlorica, Inc., to provide support to the cost analysis and nanofiltration evaluation. We have also conducted several preliminary analyses of the pressure effect in the reservoir in order to confirm that reservoir pressure can indeed be used to drive the reverse osmosis process. Our initial conclusions from the work to date are encouraging: (1) The concept of aquifer-pressured RO to provide fresh water associated with carbon dioxide storage appears feasible. (2) Concentrated brines such as those found in Wyoming are amenable to RO treatment. We have looked at sodium chloride brines from the Nugget Formation in Sublette County. 20-25% removal with conventional methods is realistic; higher removal appears achievable with NF. The less concentrated sulfate-rich brines from the Tensleep Formation in Sublette County would support >80% removal with conventional RO. (3) Brines from other proposed sequestration sites can now be analyzed readily. An osmotic pressure curve appropriate to these brines can be used to evaluate cost and equipment specifications. (4) We have examined a range of subsurface brine compositions that is potentially pertinent to carbon sequestration and noted the principal compositional trends pertinent to evaluating the feasibility of freshwater extraction. We have proposed a general categorization for the feasibility of the process based on total dissolved solids (TDS). (5) Withdrawing pressurized brine can have a very beneficial effect on reservoir pressure and total available storage capacity. Brine must be extracted from a deeper location in the aquifer than the point of CO{sub 2} injection to prevent CO{sub 2} from migrating to the brine extraction well.

  4. Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants – Interim Study FY13

    SciTech Connect (OSTI)

    Simmons, Kevin L.; Fifield, Leonard S.; Westman, Matthew P.; Ramuhalli, Pradeep; Pardini, Allan F.; Tedeschi, Jonathan R.; Jones, Anthony M.

    2013-09-27T23:59:59.000Z

    The most important criterion for cable performance is its ability to withstand a design-basis accident. With nearly 1000 km of power, control, instrumentation, and other cables typically found in an NPP, it would be a significant undertaking to inspect all of the cables. Degradation of the cable jacket, electrical insulation, and other cable components is a key issue that is likely to affect the ability of the currently installed cables to operate safely and reliably for another 20 to 40 years beyond the initial operating life. The development of one or more nondestructive evaluation (NDE) techniques and supporting models that could assist in determining the remaining life expectancy of cables or their current degradation state would be of significant interest. The ability to nondestructively determine material and electrical properties of cable jackets and insulation without disturbing the cables or connections has been deemed essential. Currently, the only technique accepted by industry to measure cable elasticity (the gold standard for determining cable insulation degradation) is the indentation measurement. All other NDE techniques are used to find flaws in the cable and do not provide information to determine the current health or life expectancy. There is no single NDE technique that can satisfy all of the requirements needed for making a life-expectancy determination, but a wide range of methods have been evaluated for use in NPPs as part of a continuous evaluation program. The commonly used methods are indentation and visual inspection, but these are only suitable for easily accessible cables. Several NDE methodologies using electrical techniques are in use today for flaw detection but there are none that can predict the life of a cable. There are, however, several physical and chemical ptoperty changes in cable insulation as a result of thermal and radiation damage. In principle, these properties may be targets for advanced NDE methods to provide early warning of aging and degradation. Examples of such key indicators include changes in chemical structure, mechanical modulus, and dielectric permittivity. While some of these indicators are the basis of currently used technologies, there is a need to increase the volume of cable that may be inspected with a single measurement, and if possible, to develop techniques for in-situ inspection (i.e., while the cable is in operation). This is the focus of the present report.

  5. Field test evaluation of conservation retrofits of low-income, single-family buildings in Wisconsin: Audit field test implementation and results

    SciTech Connect (OSTI)

    McCold, L.N.; Schlegel, J.A.; O'Leary, L.; Hewitt, D.C.

    1988-06-01T23:59:59.000Z

    This report describes the field test of a retrofit audit. The field test was performed during the winter of 1985-86 in four south central Wisconsin counties. The purpose of the field test was to measure the energy savings and cost effectiveness of the audit-directed retrofit program for optimizing the program's benefit-to-cost ratio. The audit-directed retrofit program is described briefly in this report and in more detail by another report in this series (ORNL/CON-228/P3). The purpose of this report is to describe the methods and results of the field test. 3 refs., 7 figs., 10 tabs.

  6. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Summary of results. Volume 1

    SciTech Connect (OSTI)

    Whitehead, D.W. [ed.; Staple, B.D.; Daniel, S.L. [and others

    1995-07-01T23:59:59.000Z

    During 1989 the Nuclear Regulatory Commission (NRC) initiated an extensive program to examine the potential risks during low power and shutdown operations. Two plants, Surry and Grand Gulf, were selected as the plants to be studied by Brookhaven National Laboratory (Surry) and Sandia National Laboratories (Grand Gulf). This report documents the work performed during the analysis of the Grand Gulf plant. A phased approach was used for the overall study. In Phase 1, the objectives were to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenario frequencies and risks, and to provide a foundation for a detailed Phase 2 analysis. It was in Phase 1 that the concept of plant operational states (POSs) was developed to allow the analysts to better represent the plant as it transitions from power operation to nonpower operation than was possible with the traditional technical specification divisions of modes of operation. This phase consisted of a coarse screening analysis performed for all POSs, including seismic and internal fire and flood for some POSs. In Phase 2, POS 5 (approximately cold shutdown as defined by Grand Gulf Technical Specifications) during a refueling outage was selected as the plant configuration to be analyzed based on the results of the Phase 1 study. The scope of the Level 1 study includes plant damage state analysis and uncertainty analysis and is documented in a multi-volume NUREG/CR report (i.e., NUREG/CR-6143). The internal events analysis is documented in Volume 2. Internal fire and internal flood analyses are documented in Volumes 3 and 4, respectively. A separate study on seismic analysis, documented in Volume 5, was performed for the NRC by Future Resources Associates, Inc. The Level 2/3 study of the traditional internal events is documented in Volume 6, and a summary of the results for all analyses is documented in Volume 1.

  7. Statement of work for conceptual design of solidified high-level waste interim storage system project (phase I)

    SciTech Connect (OSTI)

    Calmus, R.B., Westinghouse Hanford

    1996-12-17T23:59:59.000Z

    The U.S. Department of Energy (DOE) has embarked upon a course to acquire Hanford Site tank waste treatment and immobilization services using privatized facilities. This plan contains a two phased approach. Phase I is a ``proof-of-principle/commercial demonstration- scale`` effort and Phase II is a full-scale production effort. In accordance with the planned approach, interim storage (IS) and disposal of various products from privatized facilities are to be DOE furnished. The path forward adopted for Phase I solidification HLW IS entails use of Vaults 2 and 3 in the Spent Nuclear Fuel Canister Storage Building, to be located in the Hanford Site 200 East Area. This Statement of Work describes the work scope to be performed by the Architect-Engineer to prepare a conceptual design for the solidified HLW IS System.

  8. Technical Competencies for the Safe Interim Storage and Management of 233U at U.S. Department of Energy Facilities

    SciTech Connect (OSTI)

    Campbell, D.O.; Krichinsky, A.M.; Laughlin, S.S.; Van Essen, D.C.; Yong, L.K.

    1999-02-17T23:59:59.000Z

    Uranium-233 (with concomitant {sup 232}U) is a man-made fissile isotope of uranium with unique nuclear characteristics which require high-integrity alpha containment biological shielding, and remote handling. The special handling considerations and the fact that much of the {sup 233}U processing and large-scale handling was performed over a decade ago underscore the importance of identifying the people within the DOE complex who are currently working with or have worked with {sup 233}U. The availability of these key personnel is important in ensuring safe interim storage, management and ultimate disposition of {sup 233}U at DOE facilities. Significant programs are ongoing at several DOE sites with actinides. The properties of these actinide materials require many of the same types of facilities and handling expertise as does {sup 233}U.

  9. Advanced Fuels for LWRs: Fully-Ceramic Microencapsulated and Related Concepts FY 2012 Interim Report

    SciTech Connect (OSTI)

    R. Sonat Sen; Brian Boer; John D. Bess; Michael A. Pope; Abderrafi M. Ougouag

    2012-03-01T23:59:59.000Z

    This report summarizes the progress in the Deep Burn project at Idaho National Laboratory during the first half of fiscal year 2012 (FY2012). The current focus of this work is on Fully-Ceramic Microencapsulated (FCM) fuel containing low-enriched uranium (LEU) uranium nitride (UN) fuel kernels. UO2 fuel kernels have not been ruled out, and will be examined as later work in FY2012. Reactor physics calculations confirmed that the FCM fuel containing 500 mm diameter kernels of UN fuel has positive MTC with a conventional fuel pellet radius of 4.1 mm. The methodology was put into place and validated against MCNP to perform whole-core calculations using DONJON, which can interpolate cross sections from a library generated using DRAGON. Comparisons to MCNP were performed on the whole core to confirm the accuracy of the DRAGON/DONJON schemes. A thermal fluid coupling scheme was also developed and implemented with DONJON. This is currently able to iterate between diffusion calculations and thermal fluid calculations in order to update fuel temperatures and cross sections in whole-core calculations. Now that the DRAGON/DONJON calculation capability is in place and has been validated against MCNP results, and a thermal-hydraulic capability has been implemented in the DONJON methodology, the work will proceed to more realistic reactor calculations. MTC calculations at the lattice level without the correct burnable poison are inadequate to guarantee zero or negative values in a realistic mode of operation. Using the DONJON calculation methodology described in this report, a startup core with enrichment zoning and burnable poisons will be designed. Larger fuel pins will be evaluated for their ability to (1) alleviate the problem of positive MTC and (2) increase reactivity-limited burnup. Once the critical boron concentration of the startup core is determined, MTC will be calculated to verify a non-positive value. If the value is positive, the design will be changed to require less soluble boron by, for example, increasing the reactivity hold-down by burnable poisons. Then, the whole core analysis will be repeated until an acceptable design is found. Calculations of departure from nucleate boiling ratio (DNBR) will be included in the safety evaluation as well. Once a startup core is shown to be viable, subsequent reloads will be simulated by shuffling fuel and introducing fresh fuel. The PASTA code has been updated with material properties of UN fuel from literature and a model for the diffusion and release of volatile fission products from the SiC matrix material . Preliminary simulations have been performed for both normal conditions and elevated temperatures. These results indicated that the fuel performs well and that the SiC matrix has a good retention of the fission products. The path forward for fuel performance work includes improvement of metallic fission product release from the kernel. Results should be considered preliminary and further validation is required.

  10. Nuclear Dynamics Consequence Analysis (NDCA) for the Disposal of Spent Nuclear Fuel in an Underground Geologic Repository--Volume 2: Methodology and Results

    SciTech Connect (OSTI)

    Taylor, L.L.; Wilson, J.R.; Sanchez, L.C.; Aguilar, R.; Trellue, H.R.; Cochrane, K.; Rath, J.S.

    1998-10-01T23:59:59.000Z

    The US Department of Energy Office of Environmental Management's (DOE/EM's) National Spent Nuclear Fuel Program (NSNFP), through a collaboration between Sandia National Laboratories (SNL) and Idaho National Engineering and Environmental Laboratory (INEEL), is conducting a systematic Nuclear Dynamics Consequence Analysis (NDCA) of the disposal of SNFs in an underground geologic repository sited in unsaturated tuff. This analysis is intended to provide interim guidance to the DOE for the management of the SNF while they prepare for final compliance evaluation. This report presents results from a Nuclear Dynamics Consequence Analysis (NDCA) that examined the potential consequences and risks of criticality during the long-term disposal of spent nuclear fuel owned by DOE-EM. This analysis investigated the potential of post-closure criticality, the consequences of a criticality excursion, and the probability frequency for post-closure criticality. The results of the NDCA are intended to provide the DOE-EM with a technical basis for measuring risk which can be used for screening arguments to eliminate post-closure criticality FEPs (features, events and processes) from consideration in the compliance assessment because of either low probability or low consequences. This report is composed of an executive summary (Volume 1), the methodology and results of the NDCA (Volume 2), and the applicable appendices (Volume 3).

  11. Pantex Plant final safety analysis report, Zone 4 magazines. Staging or interim storage for nuclear weapons and components: Issue D

    SciTech Connect (OSTI)

    Not Available

    1993-04-01T23:59:59.000Z

    This Safety Analysis Report (SAR) contains a detailed description and evaluation of the significant environmental, safety, and health (ES&H) issues associated with the operations of the Pantex Plant modified-Richmond and steel arch construction (SAC) magazines in Zone 4. It provides (1) an overall description of the magazines, the Pantex Plant, and its surroundings; (2) a systematic evaluations of the hazards that could occur as a result of the operations performed in these magazines; (3) descriptions and analyses of the adequacy of the measures taken to eliminate, control, or mitigate the identified hazards; and (4) analyses of potential accidents and their associated risks.

  12. 2012 Michigan State University IPM Program Report Larry Olsen, Interim IPM Coordinator, Associate Chair Entomology

    E-Print Network [OSTI]

    cooperative Enviro-weather program. New MSU IPM Academy Integrated Pest Management (IPM) is relevant participants 46 returned evaluations. These 46 participants reported directly impacting the management of 57

  13. Geothermal evaluation of Kansas: preliminary results

    SciTech Connect (OSTI)

    Steeples, D.W.; Ruscetta, C.A.; Foley, D. (eds.)

    1981-05-01T23:59:59.000Z

    Information from the literature and from four drill holes in Kansas is presented. Geothermal gradients and heat flow measurements are presented. An aeromagnetic map of Kansas is included. (MHR)

  14. Small Reactor Designs Suitable for Direct Nuclear Thermal Propulsion: Interim Report

    SciTech Connect (OSTI)

    Bruce G. Schnitzler

    2012-01-01T23:59:59.000Z

    Advancement of U.S. scientific, security, and economic interests requires high performance propulsion systems to support missions beyond low Earth orbit. A robust space exploration program will include robotic outer planet and crewed missions to a variety of destinations including the moon, near Earth objects, and eventually Mars. Past studies, in particular those in support of both the Strategic Defense Initiative (SDI) and the Space Exploration Initiative (SEI), have shown nuclear thermal propulsion systems provide superior performance for high mass high propulsive delta-V missions. In NASA's recent Mars Design Reference Architecture (DRA) 5.0 study, nuclear thermal propulsion (NTP) was again selected over chemical propulsion as the preferred in-space transportation system option for the human exploration of Mars because of its high thrust and high specific impulse ({approx}900 s) capability, increased tolerance to payload mass growth and architecture changes, and lower total initial mass in low Earth orbit. The recently announced national space policy2 supports the development and use of space nuclear power systems where such systems safely enable or significantly enhance space exploration or operational capabilities. An extensive nuclear thermal rocket technology development effort was conducted under the Rover/NERVA, GE-710 and ANL nuclear rocket programs (1955-1973). Both graphite and refractory metal alloy fuel types were pursued. The primary and significantly larger Rover/NERVA program focused on graphite type fuels. Research, development, and testing of high temperature graphite fuels was conducted. Reactors and engines employing these fuels were designed, built, and ground tested. The GE-710 and ANL programs focused on an alternative ceramic-metallic 'cermet' fuel type consisting of UO2 (or UN) fuel embedded in a refractory metal matrix such as tungsten. The General Electric program examined closed loop concepts for space or terrestrial applications as well as open loop systems for direct nuclear thermal propulsion. Although a number of fast spectrum reactor and engine designs suitable for direct nuclear thermal propulsion were proposed and designed, none were built. This report summarizes status results of evaluations of small nuclear reactor designs suitable for direct nuclear thermal propulsion.

  15. Disposal systems evaluations and tool development : Engineered Barrier System (EBS) evaluation.

    SciTech Connect (OSTI)

    Rutqvist, Jonny (LBNL); Liu, Hui-Hai (LBNL); Steefel, Carl I. (LBNL); Serrano de Caro, M. A. (LLNL); Caporuscio, Florie Andre (LANL); Birkholzer, Jens T. (LBNL); Blink, James A. (LLNL); Sutton, Mark A. (LLNL); Xu, Hongwu (LANL); Buscheck, Thomas A. (LLNL); Levy, Schon S. (LANL); Tsang, Chin-Fu (LBNL); Sonnenthal, Eric (LBNL); Halsey, William G. (LLNL); Jove-Colon, Carlos F.; Wolery, Thomas J. (LLNL)

    2011-01-01T23:59:59.000Z

    Key components of the nuclear fuel cycle are short-term storage and long-term disposal of nuclear waste. The latter encompasses the immobilization of used nuclear fuel (UNF) and radioactive waste streams generated by various phases of the nuclear fuel cycle, and the safe and permanent disposition of these waste forms in geological repository environments. The engineered barrier system (EBS) plays a very important role in the long-term isolation of nuclear waste in geological repository environments. EBS concepts and their interactions with the natural barrier are inherently important to the long-term performance assessment of the safety case where nuclear waste disposition needs to be evaluated for time periods of up to one million years. Making the safety case needed in the decision-making process for the recommendation and the eventual embracement of a disposal system concept requires a multi-faceted integration of knowledge and evidence-gathering to demonstrate the required confidence level in a deep geological disposal site and to evaluate long-term repository performance. The focus of this report is the following: (1) Evaluation of EBS in long-term disposal systems in deep geologic environments with emphasis on the multi-barrier concept; (2) Evaluation of key parameters in the characterization of EBS performance; (3) Identification of key knowledge gaps and uncertainties; and (4) Evaluation of tools and modeling approaches for EBS processes and performance. The above topics will be evaluated through the analysis of the following: (1) Overview of EBS concepts for various NW disposal systems; (2) Natural and man-made analogs, room chemistry, hydrochemistry of deep subsurface environments, and EBS material stability in near-field environments; (3) Reactive Transport and Coupled Thermal-Hydrological-Mechanical-Chemical (THMC) processes in EBS; and (4) Thermal analysis toolkit, metallic barrier degradation mode survey, and development of a Disposal Systems Evaluation Framework (DSEF). This report will focus on the multi-barrier concept of EBS and variants of this type which in essence is the most adopted concept by various repository programs. Empasis is given mainly to the evaluation of EBS materials and processes through the analysis of published studies in the scientific literature of past and existing repository research programs. Tool evaluations are also emphasized, particularly on THCM processes and chemical equilibria. Although being an increasingly important aspect of NW disposition, short-term or interim storage of NW will be briefly discussed but not to the extent of the EBS issues relevant to disposal systems in deep geologic environments. Interim storage will be discussed in the report Evaluation of Storage Concepts FY10 Final Report (Weiner et al. 2010).

  16. Interim Design Report for the International Design Study for a Neutrino Factory

    SciTech Connect (OSTI)

    Choubey, S.; Gandhi, R.; Goswami, S.; /Harish-Chandra Res. Inst.; Berg, J.S.; Fernow, R.; Gallardo, J.C.; Gupta, R.; Kirk, H.; Simos, N.; Souchlas, N.; /Brookhaven; Ellis, M.; /Brunel U. /CERN /Durham U., IPPP /Fermilab /Geneva U. /Glasgow U. /Heidelberg, Max Planck Inst. /Imperial Coll., London /Jefferson Lab /Saha Inst.

    2011-10-01T23:59:59.000Z

    The starting point for the International Design Study for the Neutrino Factory (the IDS-NF) was the output of the earlier International Scoping Study for a future Neutrino Factory and super-beam facility (the ISS). The accelerator facility described in section 2 incorporates the improvements that have been derived from the substantial amount of work carried out within the Accelerator Working Group. Highlights of these improvements include: (1) Initial concepts for the implementation of the proton driver at each of the three example sites, CERN, FNAL, and RAL; (2) Detailed studies of the energy deposition in the target area; (3) A reduction in the length of the muon beam phase-rotation and bunching systems; (4) Detailed analyses of the impact of the risk that stray magnetic field in the accelerating cavities in the ionization cooling channel will reduce the maximum operating gradient. Several alternative ionization-cooling lattices have been developed as fallback options to mitigate this technical risk; (5) Studies of particle loss in the muon front-end and the development of strategies to mitigate the deleterious effects of such losses; (6) The development of more complete designs for the muon linac and re-circulating linacs; (7) The development of a design for the muon FFAG that incorporates insertions for injection and extraction; and (8) Detailed studies of diagnostics in the decay ring. Other sub-systems have undergone a more 'incremental' evolution; an indication that the design of the Neutrino Factory has achieved a degree of maturity. The design of the neutrino detectors described in section 3 has been optimized and the Detector Working Group has made substantial improvements to the simulation and analysis of the Magnetized Iron Neutrino Detector (MIND) resulting in an improvement in the overall neutrino-detection efficiency and a reduction in the neutrino-energy threshold. In addition, initial consideration of the engineering of the MIND has generated a design that is feasible and a finite element analysis of the toroidal magnetic field to produce a realistic field map has been carried out. Section 3 also contains, for the first time, a specification for the near-detector systems and a demonstration that the neutrino flux can be determined with a precision of 1% through measurements of inverse muon decay at the near detector. The performance of the facility, the work of the Physics and Performance Evaluation Group, is described in section 1. The effect of the improved MIND performance is to deliver a discovery reach for CP-invariance violation in the lepton sector, the determination of the mass hierarchy, and of {theta}{sub 13} that extends down to values of sin{sup 2} 2{theta}{sub 13} {approx} 5 x 10{sup -5} and is robust against systematic uncertainties. In addition, the improved neutrino-energy threshold has allowed an indicative analysis of the kind of re-optimization of the facility that could be carried out should {theta}{sub 13} be found close to the current upper bound. The results presented in section 1 demonstrate that the discovery reach as well as the precision with which the oscillation parameters can be measured at the baseline Neutrino Factory is superior to that of other proposed facilities for all possible values of sin{sup 2} 2{theta}{sub 13}.

  17. Explanation of Significant Differences for the Record of Decision for Interim Actions in Zone 1, East Tennessee Technology Park, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Bechtel Jacobs

    2011-02-01T23:59:59.000Z

    Zone 1 is a 1400-acre area outside the fence of the main plant at The East Tennessee Technology Park (ETTP) in Oak Ridge, Tennessee. The Record of Decision for Interim Actions in Zone, ETTP (Zone 1 Interim ROD) (DOE 2002) identifies the remedial actions for contaminated soil, buried waste, and subsurface infrastructure necessary to protect human health and to limit further contamination of groundwater. Since the Zone 1 Interim Record of Decision (ROD) was signed, new information has been obtained that requires the remedy to be modified as follows: (1) Change the end use in Contractor's Spoil Area (CSA) from unrestricted industrial to recreational; (2) Remove Exposure Units (EU5) ZI-50, 51, and 52 from the scope of the Zone I Interim ROD; (3) Change the end use of the duct bank corridor from unrestricted industrial to restricted industrial; and (4) Remove restriction for the disturbance of soils below 10 feet in Exposure Unit (EU) Z1-04. In accordance with 40 Code of Federal Regulations (CFR) 300.435, these scope modifications are a 'significant' change to the Zone 1 Interim ROD. In accordance with CERCLA Sect. 117 (c) and 40 CFR 300.435 (c)(2)(i), such a significant change is documented with an Explanation of Significant Differences (ESD). The purpose of this ESD is to make the changes listed above. This ESD is part of the Administrative Record file, and it, and other information supporting the selected remedy, can be found at the DOE Information Center, 475 Oak Ridge Turnpike, Oak Ridge, Tennessee 37830, from 8:00 a.m. to 5:00 p.m., Monday through Friday. The ORR is located in Roane and Anderson counties, within and adjacent to the corporate city limits of Oak Ridge, Tennessee. ETTP is located in Roane County near the northwest corner of the ORR. ETTP began operation during World War II as part of the Manhattan Project. The original mission of ETTP was to produce enriched uranium for use in atomic weapons. The plant produced enriched uranium from 1945 until 1985. Uranium production was terminated in 1987. ORR was placed on the National Priorities List in 1989, so remediation activities are conducted under CERCLA. The primary contaminants of concern at ETTP follow: (1) In groundwater - volatile organic compounds (VOCs) at multiple locations (trichloroethene is generally the most prevalent compound); (2) In sediment - inorganic elements, radionuclides, and polychlorinated biphenyls; (3) In soil - inorganic elements, radionuclides, semivolatile organic compounds (particularly the polycyclic aromatic hydrocarbons), and VOCs; and (4) In facilities - radionuclides and polychlorinated biphenyls (abandoned facilities also pose a safety and health hazard to workers.) The purposes of the remedial actions selected in the Zone 1 Interim ROD are to allow unrestricted industrial use down to 10 feet and to remediate potential sources of groundwater contamination. Following is a summary of the major components of the Zone 1 Interim ROD remedy: (1) Excavation of the Blair Quarry burial area and associated contaminated soil; (2) Excavation of miscellaneous contaminated soil in the K-895 Cylinder Destruct Facility area and in the Powerhouse Area; (3) Removal of sludge and demolition of the K-710 sludge beds and Imhoff tanks; (4) Implementation of land use controls (LUCs); and (5) Characterization of soil and remediation of areas that exceed remediation levels.

  18. Interim Report on the Optimization and Feasibility Studies for the Neutron Detection without Helium-3 Project

    SciTech Connect (OSTI)

    Ely, James H.

    2012-03-19T23:59:59.000Z

    This report provides the status and results of the first year's effort in modeling and simulation to investigate alternatives to helium-3 for neutron detection in safeguards applications.

  19. NRC Technical Research Program to Evaluate Extended Storage and Transportation of Spent Nuclear Fuel - 12547

    SciTech Connect (OSTI)

    Einziger, R.E.; Compton, K.; Gordon, M.; Ahn, T.; Gonzales, H. [United States Nuclear Regulatory Commission, Rockville, Maryland 20852 (United States); Pan, Y. [Center for Nuclear Waste Regulatory Analyses, San Antonio, TX 78238 (United States)

    2012-07-01T23:59:59.000Z

    Any new direction proposed for the back-end of spent nuclear fuel (SNF) cycle will require storage of SNF beyond the current licensing periods. The Nuclear Regulatory Commission (NRC) has established a technical research program to determine if any changes in the 10 CFR part 71, and 72 requirements, and associated guidance might be necessary to regulate the safety of anticipated extended storage, and subsequent transport of SNF. This three part program of: 1) analysis of knowledge gaps in the potential degradation of materials, 2) short-term research and modeling, and 3) long-term demonstration of systems, will allow the NRC to make informed regulatory changes, and determine when and if additional monitoring and inspection of the systems is necessary. The NRC has started a research program to obtain data necessary to determine if the current regulatory guidance is sufficient if interim dry storage has to be extended beyond the currently approved licensing periods. The three-phased approach consists of: - the identification and prioritization of potential degradation of the components related to the safe operation of a dry cask storage system, - short-term research to determine if the initial analysis was correct, and - a long-term prototypic demonstration project to confirm the models and results obtained in the short-term research. The gap analysis has identified issues with the SCC of the stainless steel canisters, and SNF behavior. Issues impacting the SNF and canister internal performance such as high and low temperature distributions, and drying have also been identified. Research to evaluate these issues is underway. Evaluations have been conducted to determine the relative values that various types of long-term demonstration projects might provide. These projects or follow-on work is expected to continue over the next five years. (authors)

  20. EIS-0163-S: Supplemental EIS/1993 Interim Columbia and Snake Rivers Flow Improvement Measures for Salmon

    Broader source: Energy.gov [DOE]

    The U.S. Army Corps of Engineers – Walla Walla District has prepared this statement to assess alternatives to improve flows of water in the lower Columbia-Snake rivers in 1993 and future years to assist the migration of juvenile and adult anadromous fish past eight hydropower dams. The U.S. Department of Energy’s Bonneville Power Administration served as a cooperating agency in developing this supplement due to its key role in direct operation of the integrated and coordinated Columbia-Snake River System, and adopted this statement in March of 1993. This statement supplements the 1992 Columbia River Salmon Flow Measures Options Analysis Environmental Impact Statement, which evaluated ways to alter water management operations in 1992 on the lower Columbia and Snake rivers to enhance the survival of wild Snake River salmon.

  1. Interim Letter Report - Verification Survey Results for Activities Performed in March 2009 for the Vitrification Test Facility Warehouse at the West Valley Demonstration Project, Ashford, New York

    SciTech Connect (OSTI)

    B.D. Estes

    2009-04-24T23:59:59.000Z

    The objective of the verification activities was to provide independent radiological surveys and data for use by the Department of Energy (DOE) to ensure that the building satisfies the requirements for release without radiological controls.

  2. Conceptual waste package interim product specifications and data requirements for disposal of borosilicate glass defense high-level waste forms in salt geologic repositories

    SciTech Connect (OSTI)

    Not Available

    1983-06-01T23:59:59.000Z

    The conceptual waste package interim product specifications and data requirements presented are applicable specifically to the normal borosilicate glass product of the Defense Waste Processing Facility (DWPF). They provide preliminary numerical values for the defense high-level waste form parameters and properties identified in the waste form performance specification for geologic isolation in salt repositories. Subject areas treated include containment and isolation, operational period safety, criticality control, waste form/production canister identification, and waste package performance testing requirements. This document was generated for use in the development of conceptual waste package designs in salt. It will be revised as additional data, analyses, and regulatory requirements become available.

  3. Environmental Assessment and Finding of No Significant Impact: Interim Measures for the Mixed Waste Management Facility Groundwater at the Burial Ground Complex at the Savannah River Site

    SciTech Connect (OSTI)

    N /A

    1999-12-08T23:59:59.000Z

    The U. S. Department of Energy (DOE) prepared this environmental assessment (EA) to analyze the potential environmental impacts associated with the proposed interim measures for the Mixed Waste Management Facility (MW) groundwater at the Burial Ground Complex (BGC) at the Savannah River Site (SRS), located near Aiken, South Carolina. DOE proposes to install a small metal sheet pile dam to impound water around and over the BGC groundwater seepline. In addition, a drip irrigation system would be installed. Interim measures will also address the reduction of volatile organic compounds (VOCS) from ''hot-spot'' regions associated with the Southwest Plume Area (SWPA). This action is taken as an interim measure for the MWMF in cooperation with the South Carolina Department of Health and Environmental Control (SCDHEC) to reduce the amount of tritium seeping from the BGC southwest groundwater plume. The proposed action of this EA is being planned and would be implemented concurrent with a groundwater corrective action program under the Resource Conservation and Recovery Act (RCRA). On September 30, 1999, SCDHEC issued a modification to the SRS RCRA Part B permit that adds corrective action requirements for four plumes that are currently emanating from the BGC. One of those plumes is the southwest plume. The RCRA permit requires SRS to submit a corrective action plan (CAP) for the southwest plume by March 2000. The permit requires that the initial phase of the CAP prescribe a remedy that achieves a 70-percent reduction in the annual amount of tritium being released from the southwest plume area to Fourmile Branch, a nearby stream. Approval and actual implementation of the corrective measure in that CAP may take several years. As an interim measure, the actions described in this EA would manage the release of tritium from the southwest plume area until the final actions under the CAP can be implemented. This proposed action is expected to reduce the release of tritium from the southwest plume area to Fourmile Branch between 25 to 35 percent. If this proposed action is undertaken and its effectiveness is demonstrated, it may become a component of the final action in the CAP. This document was prepared in compliance with the National Environmental Policy Act (NEPA) of 1969, as amended; the requirements of the Council on Environmental Quality Regulations for Implementing NEPA (40 CFR 1500-1508); and the DOE Regulations for Implementing NEPA (10 CFR 1021). NEPA requires the assessment of environmental consequences of Federal actions that may affect the quality of the human environment. Based on the potential for impacts described herein, DOE will either publish a Finding of No Significant Impact (FONSI) or prepare an environmental impact statement (EM).

  4. Hydrodynamics and heat transfer aspects of corium-water interactions: Interim report

    SciTech Connect (OSTI)

    Spencer, B.W.; Sienicki, J.J.; McUmber, L.M.

    1987-03-01T23:59:59.000Z

    The results of reactor-material experiments are described in which molten corium entered a scaled mock-up of the reactor cavity region of a PWR containment. The experiments address ex-vessel cavity interactions such as corium quench and steam generation rates (for those cases in which water is present in the cavity), hydrodynamic dispersal of water and corim from the cavity, hydrogen generation, containment atmosphere heatup by dispersed corium, and debris characterization. Generic aspects of corium/water mixing, fragmentation, and quench were also investigated. The results include extensive modeling of the hydrodynamic and heat transfer processes and application of the models to the full size reactor system.

  5. Energy Conservation Program of the Division of Substation and Control Engineering : An Interim Report.

    SciTech Connect (OSTI)

    ,

    1981-04-01T23:59:59.000Z

    Energy conservation projects undertaken by BPA that could benefit residential and commercial users and development of prototype equipment are described. Progress reports are presented and directions that the projects will take are indicated. The first projects presented are those being done at BPA's Midway Residential Community: studies on air infiltration and weatherization, and evaluation of such energy conservation measures as heat pump and solar water heaters. The next section involves an energy audit and retrofit program undertaken to reduce energy consumption in BPA's own buildings. The third section, also concerned with BPA's efforts to reduce internal energy consumption, presents the application of passive solar techniques to the design of new BPA buildings. The fourth section reports on a system developed to utilize waste thermal energy from transformers and solar energy for space heating and cooling. The fifth section also involves the development of a prototype system, one to monitor energy usage of industrial equipment. The final sections report on projects involving solar and wind energy, the Photovoltaic Applications Program, and the Mod-2 Wind Generator project at Goodnoe Hills. (MCW)

  6. Spent fuel test - Climax: technical measurements. Interim report, fiscal year 1981

    SciTech Connect (OSTI)

    Patrick, W.C.; Ballou, L.B.; Butkovich, T.R.

    1982-04-30T23:59:59.000Z

    The Spent Fuel Test-Climax (SFT-C) is located 420 m below surface in the Climax granite stock on the Nevada Test Site. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized from April to May 1980, initiating the 3- to 5-year-duration test. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. Technical objectives of the test led to development of a technical measurements program, which is the subject of this report. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the first 1-1/2 years of the test on more than 900 channels. Much of the acquired data are now available for analysis and are presented here. Highlights of activities this year include completion of site characterization field work, major modifications to the data acquisition and the management systems, and the addition of instrument evaluation as an explicit objective of the test.

  7. Spent fuel sabotage test program, characterization of aerosol dispersal : interim final report.

    SciTech Connect (OSTI)

    Gregson, Michael Warren; Brockmann, John E.; Loiseau, Olivier (Institut de Radioprotection et de Surete Nucleaire, France); Klennert, Lindsay A.; Nolte, Oliver (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Molecke, Martin Alan; Autrusson, Bruno A. (Institut de Radioprotection et de Surete Nucleaire, France); Koch, Wolfgang (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Pretzsch, Gunter Guido (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Brucher, Wenzel (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Steyskal, Michele D.

    2008-03-01T23:59:59.000Z

    This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program provides source-term data that are relevant to plausible sabotage scenarios in relation to spent fuel transport and storage casks and associated risk assessments. We present details and significant results obtained from this program from 2001 through 2007. Measured aerosol results include: respirable fractions produced; amounts, nuclide content, and produced particle size distributions and morphology; measurements of volatile fission product species enhanced sorption--enrichment factors onto respirable particles; and, status on determination of the spent fuel ratio, SFR, needed for scaling studies. Emphasis is provided on recent Phase 3 tests using depleted uranium oxide pellets plus non-radioactive fission product dopants in surrogate spent fuel test rodlets, plus the latest surrogate cerium oxide results and aerosol laboratory supporting calibration work. The DUO{sub 2}, CeO{sub 2}, plus fission product dopant aerosol particle results are compared with available historical data. We also provide a status review on continuing preparations for the final Phase 4 in this program, tests using individual short rodlets containing actual spent fuel from U.S. PWR reactors, with both high- and lower-burnup fuel. The source-term data, aerosol results, and program design have been tailored to support and guide follow-on computer modeling of aerosol dispersal hazards and radiological consequence assessments. This spent fuel sabotage, aerosol test program was performed primarily at Sandia National Laboratories, with support provided by both the U.S. Department of Energy and the Nuclear Regulatory Commission. This program has significant input from, and is cooperatively supported and coordinated by both the U.S. and international program participants in Germany, France, and others, as part of the International Working Group for Sabotage Concerns of Transport and Storage Casks (WGSTSC).

  8. Building Performance Evaluation

    E-Print Network [OSTI]

    King, A.; Harris, J.; Mbentin, B.

    2012-01-01T23:59:59.000Z

    Building Performance Evaluation Anne King and Jo Harris, MBEKTN and BSRIA Agenda ? Background to funding and programme ? The Building Performance Evaluation Programme in the UK ? Requirements ? Results ? Impact ? Discussion ? Do you/ How do... you do Building Performance Evaluation? ? What gaps are there and what could research do to fill them? Background ? The Technology Strategy Board ? the funders ? Low Impact Building programme ? BSRIA and others ? evaluators ? Soft Landings...

  9. Hydrogeology of the 200 Areas low-level burial grounds: An interim report: Volume 2, Appendixes

    SciTech Connect (OSTI)

    Last, G.V.; Bjornstad, B.N.; Bergeron, M.P.; Wallace, D.W.; Newcomer, D.R.; Schramke, J.A.; Chamness, M.A.; Cline, C.S.; Airhart, S.P.; Wilbur, J.S.

    1989-01-01T23:59:59.000Z

    This report presents information derived form the installation of 35 ground-water monitoring wells around six low-level radioactive/hazardous waste burial grounds located in the 200 Areas of the Hanford Site in southeastern Washington State. This information was collected between May 20, 1987 and August 1, 1988. The contents of this report have been divided into two volumes. Volume 1 contains the main text. This Volume contains the appendixes, including data and supporting information that verify content and results found in the main text.

  10. Local-Level Prognostics Health Management Systems Framework for Passive AdvSMR Components – Interim Report

    SciTech Connect (OSTI)

    Ramuhalli, Pradeep; Roy, Surajit; Hirt, Evelyn H.; Pardini, Allan F.; Jones, Anthony M.; Deibler, John E.; Pitman, Stan G.; Tucker, Joseph C.; Prowant, Matthew S.; Suter, Jonathan D.

    2014-09-12T23:59:59.000Z

    This report describes research results to date in support of the integration and demonstration of diagnostics technologies for prototypical AdvSMR passive components (to establish condition indices for monitoring) with model-based prognostics methods. The focus of the PHM methodology and algorithm development in this study is at the localized scale. Multiple localized measurements of material condition (using advanced nondestructive measurement methods), along with available measurements of the stressor environment, enhance the performance of localized diagnostics and prognostics of passive AdvSMR components and systems.

  11. Analysis and comparison of biomass pyrolysis/gasification condensates: an interim report

    SciTech Connect (OSTI)

    Elliott, D.C.

    1985-09-01T23:59:59.000Z

    This report provides results of chemical and physical analysis of condensates from eleven biomass gasification and pyrolysis systems. The analyses were performed in order to provide more detailed data concerning these condensates for the different process research groups and to allow a determination of the differences in properties of the condensates as a function of reactor environment. The samples were representative of the various reactor configurations being researched within the Department of Energy, Biomass Thermochemical Conversion program. The condensates included tar phases, aqueous phases and, in some cases, both phases depending on the output of the particular reactor system. The analyses included gross compositional analysis (elemental analysis, ash, moisture), physical characterization (pour point, viscosity, density, heat of combustion, distillation), specific chemical analysis (gas chromatography/mass spectrometry, infrared spectrophotometry, proton and carbon-13 nuclear magnetic resonance spectrometry) and biological activity (Ames assay). The analytical data demonstrate the wide range of chemical composition of the organics recovered in the condensates and suggests a direct relationship between operating temperature and chemical composition of the condensates. A continuous pathway of thermal degradation of the tar components as a function of temperature is proposed. Variations in the chemical composition of the organic components in the tars are reflected in the physical properties of tars and phase stability in relation to water in the condensate. The biological activity appears to be limited to the tars produced at high temperatures as a result of formation of polycyclic aromatic hydrocarbons in high concentrations. 55 refs., 13 figs., 6 tabs.

  12. Finding of no significant impact for the interim action for cleanup of Pit 9 at the Radioactive Waste Management Complex, Idaho National Engineering Laboratory

    SciTech Connect (OSTI)

    Not Available

    1993-10-01T23:59:59.000Z

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0854, for an interim action under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The proposed action would be conducted at Pit 9, Operable Unit 7--10, located at the Subsurface Disposal Area (SDA) of the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). The proposed action consists of construction of retrieval and processing buildings, excavation and retrieval of wastes from Pit 9, selective physical separation and chemical extraction, and stabilization of wastes either through thermal processing or by forming a stabilized concentrate. The proposed action would involve limited waste treatment process testing and full-scale waste treatment processing for cleaning up pre-1970 Transuranic (TRU) wastes in Pit 9. The purpose of this interim action is to expedite the overall cleanup at the RWMC and to reduce the risks associated with potential migration of Pit 9 wastes to the Snake River Plain Aquifer.

  13. Information management architecture for an integrated computing environment for the Environmental Restoration Program. Environmental Restoration Program, Volume 3, Interim technical architecture

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    This third volume of the Information Management Architecture for an Integrated Computing Environment for the Environmental Restoration Program--the Interim Technical Architecture (TA) (referred to throughout the remainder of this document as the ER TA)--represents a key milestone in establishing a coordinated information management environment in which information initiatives can be pursued with the confidence that redundancy and inconsistencies will be held to a minimum. This architecture is intended to be used as a reference by anyone whose responsibilities include the acquisition or development of information technology for use by the ER Program. The interim ER TA provides technical guidance at three levels. At the highest level, the technical architecture provides an overall computing philosophy or direction. At this level, the guidance does not address specific technologies or products but addresses more general concepts, such as the use of open systems, modular architectures, graphical user interfaces, and architecture-based development. At the next level, the technical architecture provides specific information technology recommendations regarding a wide variety of specific technologies. These technologies include computing hardware, operating systems, communications software, database management software, application development software, and personal productivity software, among others. These recommendations range from the adoption of specific industry or Martin Marietta Energy Systems, Inc. (Energy Systems) standards to the specification of individual products. At the third level, the architecture provides guidance regarding implementation strategies for the recommended technologies that can be applied to individual projects and to the ER Program as a whole.

  14. Solar resource: Utility load-matching assessment. Interim subcontract report, 20 September 1991--19 December 1993

    SciTech Connect (OSTI)

    Perez, R.; Seals, R.; Stewart, R. [State Univ. of New York, Albany, NY (United States). Atmospheric Sciences Research Center

    1994-03-01T23:59:59.000Z

    This report describes work performed to estimate the load-matching capability of photovoltaics (PV) for a selected group of utilities in the continental United States. The report provides an initial quantitative estimate of this capability for 20 utilities. This characteristic is important because it may indicate that the effective capacity, hence the value, of PV is higher than is traditionally assigned to such non-controllable, non-dispatchable resources. Load-matching capability is determined experimentally by analyzing the interaction between the load requirements of each utility and the output of locally sited PV systems. This type of investigation requires site- and time-specific insolation data that are not commonly available. Here, the needed data were inferred from geostationary satellite remote sensing of the Earth`s cloud cover. A secondary objective of this study was to evaluate the suitability of this approach. The results of this investigation are presented in this report.

  15. COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS

    SciTech Connect (OSTI)

    THIELGES, J.R.; CHASTAIN, S.A.

    2007-06-21T23:59:59.000Z

    The Disposable Solid Waste Cask (DSWC) is a shielded cask capable of transporting, storing, and disposing of six non-fuel core components or approximately 27 cubic feet of radioactive solid waste. Five existing DSWCs are candidates for use in storing and disposing of non-fuel core components and radioactive solid waste from the Interim Examination and Maintenance Cell, ultimately shipping them to the 200 West Area disposal site for burial. A series of inspections, studies, analyses, and modifications were performed to ensure that these casks can be used to safely ship solid waste. These inspections, studies, analyses, and modifications are summarized and attached in this report. Visual inspection of the casks interiors provided information with respect to condition of the casks inner liners. Because water was allowed to enter the casks for varying lengths of time, condition of the cask liner pipe to bottom plate weld was of concern. Based on the visual inspection and a corrosion study, it was concluded that four of the five casks can be used from a corrosion standpoint. Only DSWC S/N-004 would need additional inspection and analysis to determine its usefulness. The five remaining DSWCs underwent some modification to prepare them for use. The existing cask lifting inserts were found to be corroded and deemed unusable. New lifting anchor bolts were installed to replace the existing anchors. Alternate lift lugs were fabricated for use with the new lifting anchor bolts. The cask tiedown frame was modified to facilitate adjustment of the cask tiedowns. As a result of the above mentioned inspections, studies, analysis, and modifications, four of the five existing casks can be used to store and transport waste from the Interim Examination and Maintenance Cell to the disposal site for burial. The fifth cask, DSWC S/N-004, would require further inspections before it could be used.

  16. Electrical properties of nitrogen-doped float-zone silicon. Interim report, March-1984-March 1985

    SciTech Connect (OSTI)

    O'Leary, M.A.; Mitchel, W.C.

    1985-07-01T23:59:59.000Z

    Examination of nitrogen doped float zone silicon indicates that electrical properties are similiar to commerical Czochralski material. This material deserves further consideration for use in high power device and intrinsic infrared detector applications. Temperature-dependent Hall-effect measurements were made on as-received and neutron-transmutation-doped (NTD) sample of a nitrogen-doped float-zone silicon crystal to determine its electrical properties. Samples were studied in both as-received state and after various high-temperature anneals. Results were compared with commerical n-type Czochralski silicon and conventional neutron doped float zone silcion. Undoped, annealed samples of Si:N showed signs of inhomogeneities were not seen in lightly NTD's and annealed nitrogen-doped material, indicating that even light doping will mask effects of the proposed precipitation. No evidence was detected for any electrically active level that could be directly related to the nitrogen.

  17. Results of Stainless Steel Canister Corrosion Studies and Environmental Sample Investigations

    SciTech Connect (OSTI)

    Bryan, Charles R; Enos, David

    2014-12-01T23:59:59.000Z

    This progress report describes work being done at Sandia National Laboratories (SNL) to assess the localized corrosion performance of container/cask materials used in the interim storage of used nuclear fuel. The work involves both characterization of the potential physical and chemical environment on the surface of the storage canisters and how it might evolve through time, and testing to evaluate performance of the canister materials under anticipated storage conditions. To evaluate the potential environment on the surface of the canisters, SNL is working with the Electric Power Research Institute (EPRI) to collect and analyze dust samples from the surface of in-service SNF storage canisters. In FY 13, SNL analyzed samples from the Calvert Cliffs Independent Spent Fuel Storage Installation (ISFSI); here, results are presented for samples collected from two additional near-marine ISFSI sites, Hope Creek NJ, and Diablo Canyon CA. The Hope Creek site is located on the shores of the Delaware River within the tidal zone; the water is brackish and wave action is normally minor. The Diablo Canyon site is located on a rocky Pacific Ocean shoreline with breaking waves. Two types of samples were collected: SaltSmart™ samples, which leach the soluble salts from a known surface area of the canister, and dry pad samples, which collected a surface salt and dust using a swipe method with a mildly abrasive ScotchBrite™ pad. The dry samples were used to characterize the mineralogy and texture of the soluble and insoluble components in the dust via microanalytical techniques, including mapping X-ray Fluorescence spectroscopy and Scanning Electron Microscopy. For both Hope Creek and Diablo Canyon canisters, dust loadings were much higher on the flat upper surfaces of the canisters than on the vertical sides. Maximum dust sizes collected at both sites were slightly larger than 20 ?m, but Phragmites grass seeds ~1 mm in size, were observed on the tops of the Hope Creek canisters. At both sites, the surface dust could be divided into fractions generated by manufacturing processes and by natural processes. The fraction from manufacturing processes consisted of variably-oxidized angular and spherical particles of stainless steel and iron, generated by machining and welding/cutting processes, respectively. Dust from natural sources consisted largely of detrital quartz and aluminosilicates (feldspars and clays) at both sites. At Hope Creek, soluble salts were dominated by sulfates and nitrates, mostly of calcium. Chloride was a trace component and the only chloride mineral observed by SEM was NaCl. Chloride surface loads measured by the Saltsmart™ sensors were very low, less than 60 mg m{sup –2} on the canister top, and less than 10 mg m{sup –2} on the canister sides. At Diablo Canyon, sea-salt aggregates of NaCl and Mg-SO{sub 4}, with minor K and Ca, were abundant in the dust, in some cases dominating the observed dust assemblage. Measured Saltsmart™ chloride surface loads were very low (<5 mg m{sup –2}); however, high canister surface temperatures damaged the Saltsmart™ sensors, and, in view of the SEM observations of abundant sea-salts on the package surfaces, the measured surface loads may not be valid. Moreover, the more heavily-loaded canister tops at Diablo Canyon were not sampled with the Saltsmart™ sensors. The observed low surface loads do not preclude chloride-induced stress corrosion cracking (CISCC) at either site, because (1) the measured data may not be valid for the Diablo Canyon canisters; (2) the surface coverage was not complete (for instance, the 45º offset between the outlet and inlet vents means that near-inlet areas, likely to have heavier dust and salt loads, were not sampled); and (3) CISCC has been experimentally been observed at salt loads as low as 5-8 mg/m{sup 2}. Experimental efforts at SNL to assess corrosion of interim storage canister materials include three tasks in FY14. First, a full-diameter canister mockup, made using materials and techniques identical to those used to make interim st

  18. Deposition and corrosion phenomena on aluminum surfaces under deluged dry cooling-tower condisions. Interim report

    SciTech Connect (OSTI)

    Wheeler, K.R.; May, R.P.; Douglas, J.G.; Tylczak, J.H.

    1981-07-01T23:59:59.000Z

    Deposition and corrosion on aluminum heat exchanger surfaces resulting from deluge in wet/dry cooling towers is simulated in a laboratory Corrosion/Deposition Loop (CDL). Heat exchanger deposition buildup was found to be linearly dependent on concentration factor and number of wet/dry cycles. Deionized water rising after deluge reduced rate of deposition. Laboratory data obtained from CDL relates directly to operation of the Advanced Concepts Test (ACT) demonstration cooling tower. Technology transferable to ACT shows that deposition from supersaturated solution can be effectively controlled by attention to water chemistry, pH, water conditioning, and good heat transfer design. The additional mechanism of deposition by water film evaporation is effectively managed by soft water rinsing and uniform surface wetting. Exposure of a model TRANE surface (the ACT wet/dry exchanger) produced short-term deposition extrapolating to 0.011 mm buildup in three years. Studies continue to verify 4X as maximum cycles of concentration through control of water chemistry and rinsing after deluge. Deluge water used at ACT facility is sufficiently aggressive to warrant use of Alclad to extend tube service life.

  19. Environmental radiation safety: source term modification by soil aerosols. Interim report

    SciTech Connect (OSTI)

    Moss, O.R.; Allen, M.D.; Rossignol, E.J.; Cannon, W.C.

    1980-08-01T23:59:59.000Z

    The goal of this project is to provide information useful in estimating hazards related to the use of a pure refractory oxide of /sup 238/Pu as a power source in some of the space vehicles to be launched during the next few years. Although the sources are designed and built to withstand re-entry into the earth's atmosphere, and to impact with the earth's surface without releasing any plutonium, the possibility that such an event might produce aerosols composed of soil and /sup 238/PuO/sub 2/ cannot be absolutely excluded. This report presents the results of our most recent efforts to measure the degree to which the plutonium aerosol source term might be modified in a terrestrial environment. The five experiments described represent our best effort to use the original experimental design to study the change in the size distribution and concentration of a /sup 238/PuO/sub 2/ aerosol due to coagulation with an aerosol of clay or sandy loam soil.

  20. Experimental program for the development of peat gasification. Process designs and cost estimates for the manufacture of 250 billion Btu/day SNG from peat by the PEATGAS Process. Interim report No. 8

    SciTech Connect (OSTI)

    Arora, J.L.; Tsaros, C.L.

    1980-02-01T23:59:59.000Z

    This report presents process designs for the manufacture of 250 billion Btu's per day of SNG by the PEATGAS Process from peats. The purpose is to provide a preliminary assessment of the process requirements and economics of converting peat to SNG by the PEATGAS Process and to provide information needed for the Department of Energy (DOE) to plan the scope of future peat gasification studies. In the process design now being presented, peat is dried to 35% moisture before feeding to the PEATGAS reactor. This is the basic difference between the Minnesota peat case discussed in the current report and that presented in the Interim Report No. 5. The current design has overall economic advantages over the previous design. In the PEATGAS Process, peat is gasified at 500 psig in a two-stage reactor consisting of an entrained-flow hydrogasifier followed by a fluidized-bed char gasifier using steam and oxygen. The gasifier operating conditions and performance are necessarily based on the gasification kinetic model developed for the PEATGAS reactor using the laboratory- and PDU-scale data as of March 1978 and April 1979, respectively. On the basis of the available data, this study concludes that, although peat is a low-bulk density and low heating value material requiring large solids handling costs, the conversion of peat to SNG appears competitive with other alternatives being considered for producing SNG because of its very favorable gasification characteristics (high methane formation tendency and high reactivity). As a direct result of the encouraging technical and economic results, DOE is planning to modify the HYGAS facility in order to begin a peat gasification pilot plant project.

  1. Interim operations report for atmospheric fluidized-bed combustion conversion at Northern States Power Company

    SciTech Connect (OSTI)

    Thimsen, D. (Hamilton Maurer International, Inc., Falcon Heights, MN (USA))

    1991-03-01T23:59:59.000Z

    Northern States Power Company converted its Black Dog Station Unit No. 2 boiler from a front wall fired pulverized coal boiler to a bubbling atmospheric fluidized bed combustor (AFBC) boiler. The resulting unit was uprated from 85 MWe to 130 MWe burning western subbituminous coal. This report describes the AFBC operating and maintenance experience in the startup period from initial operation in June 1986 through March 1989 when a turbine oil fire caused a forced outage of 8 months. A brief review of the construction history is given in Section 1. Section 2 chronicles the AFBC operation. Section 3 describes how the boiler is restarted under several conditions. The performance history of the systems in the AFBC that are peculiar to the AFBC process or directly impacted by the AFBC process are described in detail in Section 4. The AFBC conversion at the Black Dog station has met nearly all of the original design objectives: (1) The unit can operate at rated output of 130 MWe burning western subbituminous coal, (2) The design life of the unit has been extended 25 years, (3) It has been shown that the EPA New Source Performance Standards for NO{sub x} and SO{sub 2} can be met with no flue gas treatment, (4) Operators have conducted over 200 routine daily unit restarts confirming the ability of the unit to serve in daily cycling mode, and (5) A variety of fuels have been successfully burned in the AFBC. The only objective that remains partially achieved is routine operation at full load. The boiler/turbine/generator have been shown to be fully capable of operation at full load, but the electrostatic precipitators (which were largely unchanged during the retrofit) have been inadequate to allow full load operation while remaining within permitted opacity and particulate emissions. The unit is currently dispatched in daily cycling service and is limited to operation below 106 MWe by its emissions control permit. 12 refs., 34 figs., 6 tabs.

  2. AFCI Transmutation Fuel Processes and By-Products Planning: Interim Report

    SciTech Connect (OSTI)

    Eric L. Shaber

    2005-09-01T23:59:59.000Z

    The goals of the Advanced Fuel Cycle Initiative (AFCI) Program are to reduce high-level waste volume, reduce long-lived and radiotoxic elements, and reclaim valuable energy content of spent nuclear fuel. The AFCI chartered the Fuel Development Working Group (FDWG) to develop advanced fuels in support of the AFCI goals. The FDWG organized a phased strategy of fuel development that is designed to match the needs of the AFCI program: Phase 1 - High-burnup fuels for light-water reactors (LWRs) and tri-isotopic (TRISO) fuel for gas-cooled reactors Phase 2 – Mixed oxide fuels with minor actinides for LWRs, Am transmutation targets for LWRs, inert matrix fuels for LWRs, and TRISO fuel containing Pu and other transuranium for gas-cooled reactors Phase 3 – Fertile free or low-fertile metal, ceramic, ceramic dispersed in a metal matrix (CERMET), and ceramics dispersed in a ceramic matrix (CERCER) that would be used primarily in fast reactors. Development of advanced fuels requires the fabrication, assembly, and irradiation of prototypic fuel under bounding reactor conditions. At specialized national laboratory facilities small quantities of actinides are being fabricated into such fuel for irradiation tests. Fabrication of demonstration quantities of selected fuels for qualification testing is needed but not currently feasible, because existing manual glovebox fabrication approaches result in significant radiation exposures when larger quantities of actinides are involved. The earliest demonstration test fuels needed in the AFCI program are expected to be variants of commercial mixed oxide fuel for use in an LWR as lead test assemblies. Manufacture of such test assemblies will require isolated fabrication lines at a facility not currently available in the U.S. Such facilities are now being planned as part of an Advanced Fuel Cycle Facility (AFCF). Adequate planning for and specification of actinide fuel fabrication facilities capable of producing transmutation fuels dictates the need for detailed process flows, mass balances, batch size data, and radiological dose estimates. Full definition of the materials that will need to be handled in the facility as feed material inputs, in-process fuel, scrap recycle, scrap requiring recovery, and by-product wastes is required. The feed material for demonstrating transmutation fuel fabrication will need to come from the separations of actinides from spent nuclear fuel processed in the same AFCF.

  3. Interim status report on lead-cooled fast reactor (LFR) research and development.

    SciTech Connect (OSTI)

    Tzanos, C. P.; Sienicki, J. J.; Moisseytsev, A.; Smith, C. F.; de Caro, M.; Halsey, W. G.; Li, N.; Hosemann, P.; Zhang, J.; Bolind, A.; LLNL; LANL; Univ. of Illinois

    2008-03-31T23:59:59.000Z

    This report discusses the status of Lead-Cooled Fast Reactor (LFR) research and development carried out during the first half of FY 2008 under the U.S. Department of Energy Generation IV Nuclear Energy Systems Initiative. Lead-Cooled Fast Reactor research and development has recently been transferred from Generation IV to the Reactor Campaign of the Global Nuclear Energy Partnership (GNEP). Another status report shall be issued at the end of FY 2008 covering all of the LFR activities carried out in FY 2008 for both Generation IV and GNEP. The focus of research and development in FY 2008 is an initial investigation of a concept for a LFR Advanced Recycling Reactor (ARR) Technology Pilot Plant (TPP)/demonstration test reactor (demo) incorporating features and operating conditions of the European Lead-cooled SYstem (ELSY) {approx} 600 MWe lead (Pb)-cooled LFR preconceptual design for the transmutation of waste and central station power generation, and which would enable irradiation testing of advanced fuels and structural materials. Initial scoping core concept development analyses have been carried out for a 100 MWt core composed of sixteen open-lattice 20 by 20 fuel assemblies largely similar to those of the ELSY preconceptual fuel assembly design incorporating fuel pins with mixed oxide (MOX) fuel, central control rods in each fuel assembly, and cooled with Pb coolant. For a cycle length of three years, the core is calculated to have a conversion ratio of 0.79, an average discharge burnup of 108 MWd/kg of heavy metal, and a burnup reactivity swing of about 13 dollars. With a control rod in each fuel assembly, the reactivity worth of an individual rod would need to be significantly greater than one dollar which is undesirable for postulated rod withdrawal reactivity insertion events. A peak neutron fast flux of 2.0 x 10{sup 15} (n/cm{sup 2}-s) is calculated. For comparison, the 400 MWt Fast Flux Test Facility (FFTF) achieved a peak neutron fast flux of 7.2 x 10{sup 15} (n/cm{sup 2}-s) and the initially 563 MWt PHENIX reactor attained 2.0 x 10{sup 15} (n/cm{sup 2}-s) before one of three intermediate cooling loops was shut down due to concerns about potential steam generator tube failures. The calculations do not assume a test assembly location for advanced fuels and materials irradiation in place of a fuel assembly (e.g., at the center of the core); the calculations have not examined whether it would be feasible to replace the central assembly by a test assembly location. However, having only fifteen driver assemblies implies a significant effect due to perturbations introduced by the test assembly. The peak neutron fast flux is low compared with the fast fluxes previously achieved in FFTF and PHENIX. Furthermore, the peak neutron fluence is only about half of the limiting value (4 x 10{sup 23} n/cm{sup 2}) typically used for ferritic steels. The results thus suggest that a larger power level (e.g., 400 MWt) and a larger core would be better for a TPP based upon the ELSY fuel assembly design and which can also perform irradiation testing of advanced fuels and materials. In particular, a core having a higher power level and larger dimensions would achieve a suitable average discharge burnup, peak fast flux, peak fluence, and would support the inclusion of one or more test assembly locations. Participation in the Generation IV International Forum Provisional System Steering Committee for the LFR is being maintained throughout FY 2008. Results from the analysis of samples previously exposed to flowing lead-bismuth eutectic (LBE) in the DELTA loop are summarized and a model for the oxidation/corrosion kinetics of steels in heavy liquid metal coolants was applied to systematically compare the calculated long-term (i.e., following several years of growth) oxide layer thicknesses of several steels.

  4. Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes

    SciTech Connect (OSTI)

    Not Available

    1984-01-01T23:59:59.000Z

    The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables.

  5. Medium Truck Duty Cycle Data from Real-World Driving Environments: Project Interim Report

    SciTech Connect (OSTI)

    Franzese, Oscar [ORNL; Lascurain, Mary Beth [ORNL; Capps, Gary J [ORNL

    2011-01-01T23:59:59.000Z

    Since the early part of the 20th century, the US trucking industry has provided a safe and economical means of moving commodities across the country. At the present time, nearly 80% of the US domestic freight movement involves the use of trucks. The US Department of Energy (DOE) is spearheading a number of research efforts to improve heavy vehicle fuel efficiencies. This includes research in engine technologies (including hybrid and fuel cell technologies), lightweight materials, advanced fuels, and parasitic loss reductions. In addition, DOE is developing advanced tools and models to support heavy vehicle truck research, and is leading the 21st Century Truck Partnership whose stretch goals involve a reduction by 50% of the fuel consumption of heavy vehicles on a ton-mile basis. This Medium Truck Duty Cycle (MTDC) Project is a critical element in DOE s vision for improved heavy vehicle energy efficiency and is unique in that there is no other national database of characteristic duty cycles for medium trucks. It involves the collection of real-world data for various situational characteristics (rural/urban, freeway/arterial, congested/free-flowing, good/bad weather, etc.) and looks at the unique nature of medium trucks drive cycles (stop-and-go delivery, power takeoff, idle time, short-radius trips), to provide a rich source of data that can contribute to the development of new tools for fuel efficiency and modeling, provide DOE a sound basis upon which to make technology investment decisions, and provide a national archive of real-world-based medium-truck operational data to support heavy vehicle energy efficiency research. The MTDC project involves a two-part field operational test (FOT). For the Part-1 FOT, three vehicles, each from two vocations (urban transit and dry-box delivery) were instrumented for one year of data collection. The Part-2 FOT will involve the towing/recovery and utility vocations. The vehicles participating in the MTDC project are doing so through gratis partnerships in return for early access to the results of this study. Partnerships such as these are critical to FOTs in which real-world data is being collected. In Part 1 of the project, Oak Ridge National Laboratory(ORNL) established partnerships with the H.T. Hackney Company, one of the largest wholesale distributors in the country, distributing products to 21 states; and with the Knoxville Area Transit (KAT), the City of Knoxville s transit system, operating services across the city of Knoxville and parts of Knox co. These partnerships and agreements provided ORNL access to three Class-7 2005/2007 International day-cab tractors, model 8600, which regularly haul 28 ft pup trailers (H.T. Hackney Co) and three Class-7 2005 Optima LF-34 buses (KAT), for collection of duty cycle data. In addition, ORNL has collaborated with the Federal Motor Carrier Safety Administration (FMCSA) to determine if there were possible synergies between this duty cycle data collection effort and FMCSA s need to learn more about the operation and duty cycles of the second-largest fuel consuming commercial vehicle category in the US. FMCSA s primary interest was in collecting safety data relative to the driver, carrier, and vehicle. In order to collect the duty cycle and safety-related data, ORNL developed a data acquisition and wireless communication system that was placed on each test vehicle. Each signal recorded in this FOT was collected by means of one of the instruments incorporated into each data acquisition system (DAS). Native signals were obtained directly from the vehicle s J1939 and J1708 data buses. A VBOX II Lite collected Global Positioning System related information including speed, acceleration, and spatial location information at a rate of 5 Hz, and communicated this data via the CAN (J1939) protocol. The Air-Weigh LoadMaxx, a self-weighing system which determines the vehicle s gross weight by means of pressure transducers and posts the weight to the vehicle s J1939 data bus, was used to collect vehicle payload information. A cellular modem, the Raven X

  6. Interim reliability-evaluation program: analysis of the Millstone Point Unit 1 nuclear power plant. Volume IV. Appendix B. 9 through B. 19 and C

    SciTech Connect (OSTI)

    Curry, J J; Gallagher, D W; Modarres, M; Radder, J A

    1983-05-01T23:59:59.000Z

    Appendices are presented concerning isolation condenser makeup; vapor suppression system; station air system; reactor building closed cooling water system; turbine building secondary closed water system; service water system; emergency service water system; fire protection system; emergency ac power; dc power system; event probability estimation; methodology of accident sequence quantification; and assignment of dominant sequences to release categories.

  7. Interim Chronic Beryllium Disease

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-12-08T23:59:59.000Z

    Establishes Departmental expectations for addressing chronic beryllium disease throughout the Department until a Departmental rule on beryllium is promulgated. This Notice was replaced by final rule 10 CFR Part 850, Chronic Beryllium Disease Prevention Program, published December 8, 1999.

  8. Interim DOE O 331

    Broader source: Energy.gov (indexed) [DOE]

    Uses communication tools and resources, e.g., email, voicemail, power point, graphics, etc., effectively NOTE: Inherent in this factor is the need to be resourceful in...

  9. Interim Action Determination

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment of EnergyIndustry15Among States in theWAPA1 DOEAnalysis

  10. COMPARISON OF FINAL TREATMENT & PROCESS METHODS FOR THE PREPARATION & INTERIM STORAGE OF K BASIN KNOCKOUT POT SLUDGE ENGINEERING STUDY

    SciTech Connect (OSTI)

    ERPENBECK, E.G.

    2004-06-22T23:59:59.000Z

    Fluor Hanford (FH) directed British Nuclear Fuels, Inc. (BNFL) to prepare a Knock Out Pot (KOP) study ''using cold vacuum drying (CVD) to dry the KOP sludge with a final disposition to Canister Storage Building (CSB) or evaluate a process to corrode the sludge in water and grout it to meet the end state criteria for the Waste Isolation Pilot Plant (WIPP).'' BNFL initially identified four process options: (1) Incorporate sludges into grout with no pre-conditioning; (2) Corrode the Uranium metal in the sludges then incorporate the resulting sludge into grout; (3) Separate sludge into two streams by washing/size separation with: Larger particle/Uranium metal rich stream being vacuum dried at CVD; and Smaller particle/lower Uranium metal stream being incorporated into grout; and (4) Cold vacuum dry all sludge at CVD. A coarse down selection meeting discounted option 1 as the number of drums required was prohibitive in terms of cost and schedule; and option 4 due to the technical inability of CVD to dry this waste.

  11. Evaluation of improved polyamides

    SciTech Connect (OSTI)

    Hishaw, R.J.

    1980-06-01T23:59:59.000Z

    Three polyamides, nylon 11, nylon 12, and a transparent nylon, were evaluated by physical testing, characterization and analytical methods, and injection molding. None of the materials proved to be clearly superior to the others. Results of the evaluation will be used to determine applications for the materials in future production programs.

  12. Norcal Prototype LNG Truck Fleet: Final Results

    SciTech Connect (OSTI)

    Not Available

    2004-07-01T23:59:59.000Z

    U.S. DOE and National Renewable Energy Laboratory evaluated Norcal Waste Systems liquefied natural gas (LNG) waste transfer trucks. Trucks had prototype Cummins Westport ISXG engines. Report gives final evaluation results.

  13. EA-0995: Drum Storage Facility for Interim Storage of Materials Generated by Environmental Restoration Operations, Golden, Colorado

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to construct and operate a drum storage facility at the U.S. Department of Energy's Rocky Flats Environmental Technology Site in Golden,...

  14. Measure and Evaluate Institutional Change for Sustainability...

    Broader source: Energy.gov (indexed) [DOE]

    to ensure that institutional change efforts produce successful results in meeting sustainability goals. To measure success, an evaluation is needed. An effective evaluation:...

  15. Measure and Evaluate Institutional Change for Sustainability

    Broader source: Energy.gov [DOE]

    The measure and evaluation step is crucial to ensure that institutional change efforts produce successful results in meeting sustainability goals. To measure success, an evaluation is needed.

  16. Final report of the accident phenomenology and consequence (APAC) methodology evaluation. Spills Working Group

    SciTech Connect (OSTI)

    Brereton, S.; Shinn, J. [Lawrence Livermore National Lab., CA (United States); Hesse, D [Battelle Columbus Labs., OH (United States); Kaninich, D. [Westinghouse Savannah River Co., Aiken, SC (United States); Lazaro, M. [Argonne National Lab., IL (United States); Mubayi, V. [Brookhaven National Lab., Upton, NY (United States)

    1997-08-01T23:59:59.000Z

    The Spills Working Group was one of six working groups established under the Accident Phenomenology and Consequence (APAC) methodology evaluation program. The objectives of APAC were to assess methodologies available in the accident phenomenology and consequence analysis area and to evaluate their adequacy for use in preparing DOE facility safety basis documentation, such as Basis for Interim Operation (BIO), Justification for Continued Operation (JCO), Hazard Analysis Documents, and Safety Analysis Reports (SARs). Additional objectives of APAC were to identify development needs and to define standard practices to be followed in the analyses supporting facility safety basis documentation. The Spills Working Group focused on methodologies for estimating four types of spill source terms: liquid chemical spills and evaporation, pressurized liquid/gas releases, solid spills and resuspension/sublimation, and resuspension of particulate matter from liquid spills.

  17. Management Plan for Experimental Reintroduction of Sockeye into Skaha Lake; Proposed Implementation, Monitoring, and Evaluation, 2004 Technical Report.

    SciTech Connect (OSTI)

    Wright, Howie; Smith, Howard (Okanagan Nation Alliance, Fisheries Department, Westbank, BC, Canada)

    2004-01-01T23:59:59.000Z

    Okanagan River sockeye salmon, which spawn near the town of Oliver, B.C., have their farther upstream migration limited by several water control and diversion dams. Stock numbers have been declining for many years and the Okanagan Native Alliance Fisheries Department (ONAFD) has been the principal advocate of a program to restore their numbers and range by reintroducing them into upstream waters where they may once have occurred in substantial numbers Some investigators have warned that without effective intervention Okanagan sockeye are at considerable risk of extinction. Among a host of threats, the quality of water in the single nursery areas in Osoyoos Lake. is deteriorating and a sanctuary such as that afforded in larger lakes higher in the system could be essential. Because the proposed reintroduction upstream has implications for other fish species, (particularly kokanee, the so-called ''landlocked sockeye'' which reside in many Okanagan lakes), the proponents undertook a three-year investigation, with funding from the Bonneville Power Administration and the Confederated Tribes of the Colville Reservation, to identify possible problem areas, and they committed to an interim experimental reintroduction to Skaha Lake where any problems could be worked out before a more ambitious reintroduction, (e.g. to Okanagan Lake) could be formally considered. The three-year investigation was completed in the spring of 2003. It included an assessment of risks from disease or the possible introduction of unwanted exotic species. It also considered the present quality and quantity of sockeye habitat, and opportunities for expanding or improving it. Finally ecological complexity encouraged the development of a life history model to examine interactions of sockeye with other fishes and their food organisms. While some problem areas were exposed in the course of these studies, they appeared to be manageable and the concept of an experimental reintroduction was largely supported but with the proviso that there should be a thorough evaluation and reporting of progress and results. A 2004 start on implementation and monitoring has now been proposed.

  18. Request for interim approval to operate Trench 94 of the 218-E-12B Burial Ground as a chemical waste landfill for disposal of polychlorinated biphenyl waste in submarine reactor compartments. Revision 2

    SciTech Connect (OSTI)

    Cummins, G.D.

    1994-06-01T23:59:59.000Z

    This request is submitted to seek interim approval to operate a Toxic Substances Control Act (TSCA) of 1976 chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) waste. Operation of a chemical waste landfill for disposal of PCB waste is subject to the TSCA regulations of 40 CFR 761. Interim approval is requested for a period not to exceed 5 years from the date of approval. This request covers only the disposal of small 10 quantities of solid PCB waste contained in decommissioned, defueled submarine reactor compartments (SRC). In addition, the request applies only to disposal 12 of this waste in Trench 94 of the 218-E-12B Burial Ground (Trench 94) in the 13 200 East Area of the US Department of Energy`s (DOE) Hanford Facility. Disposal of this waste will be conducted in accordance with the Compliance 15 Agreement (Appendix H) between the DOE Richland Operations Office (DOE-RL) and 16 the US Environmental Protection Agency (EPA), Region 10. During the 5-year interim approval period, the DOE-RL will submit an application seeking final 18 approval for operation of Trench 94 as a chemical waste landfill, including 19 any necessary waivers, and also will seek a final dangerous waste permit from 20 the Washington State Department of Ecology (Ecology) for disposal of lead 21 shielding contained in the SRCS.

  19. Nondestructive evaluation

    SciTech Connect (OSTI)

    Martz, H.E.

    1997-02-01T23:59:59.000Z

    Research reported in the thrust area of nondestructive evaluation includes: advanced 3-D imaging technologies; new techniques in laser ultrasonic testing; infrared computed tomography for thermal NDE of materials, structures, sources, and processes; automated defect detection for large laser optics; multistatic micropower impulse radar imaging for nondestructive evaluation; and multi-modal NDE for AVLIS pod shielding components.

  20. Superfund record of decision (EPA Region 8): Monticello Mill Tailings (USDOE), Operable Unit 3, Monticello, UT, September 29, 1998

    SciTech Connect (OSTI)

    NONE

    1998-11-01T23:59:59.000Z

    This decision document presents the selected interim remedial action for Operable Unit (OU) 3 surface water and ground water at the Monticello Mill Tailings Site (MMTS) in San Juan County, Utah. The selected alternative for the interim remedial action for OU 3 surface water runoff, continuation of ongoing monitoring efforts, and evaluation of a permeable reactive treatment (PeRT) wall through the use of a pilot-scale treatability study. If monitoring results indicate that the interim remedial action is not achieving the objectives of preventing exposure to and reducing contaminants in contaminated ground water, other alternatives will be evaluated from the OU 3 feasibility study.

  1. Evaluation of the TWRS SRID for Additional Requirements Resulting from W-420 Stack Monitoring System Upgrades [for 241C and 244A and BX and CF and S and TX

    SciTech Connect (OSTI)

    TUCK, J.A.

    1999-08-19T23:59:59.000Z

    Project W-420, Stack Monitoring System Upgrades, will provide new effluent sampling equipment on six Tank Waste Remediation System (TWRS) facilities. The upgraded systems will support the safe, continued conduct of operations and maintenance, will meet current environmental and Authorization Basis (AB) requirements, and will provide for high reliability and flexibility in support of Hanford's long term cleanup mission. The purpose of this paper is to describe the Project W-420 upgrade activities, and to show that the upgraded stack monitoring systems will be similar to existing systems in use in TWRS facilities and functionally identical to what is described in the safety bases for the affected facilities. Therefore, the current TWRS Standards/Requirements Identification Document (S/RID) is sufficient to cover the project and no new S/RID requirements are needed as a result of Project W-420. Additionally, Project W-420 hereby requests that the S/RID functional area Facility Experts (FEs) signify their concurrence with the signing the distribution sheet attached to this document.

  2. Evaluating dredged material placement alternatives 

    E-Print Network [OSTI]

    Wooters, Kelly Lynne

    1989-01-01T23:59:59.000Z

    , but are required in some environmentally sensitive areas. An example of an innovative disposal alternative is the application of oil spill clean-up technology to dredging sites in the form of interim storage. 1. 3 Related Research The environmental impacts... of alternatives, sociopolitical implication, and environmental impact. Specific procedural guidelines are presented for marsh, upland, and island development. Gupta et al. (1978) establish the appropriate agricultural use for the dredged materiaL Dredged...

  3. Monitoring and Evaluation of Smolt Migration in the Columbia Basin : Volume XVIII: Survival and Transportation Effects of Migrating Snake River Wild Chinook Salmon and Steelhead: Historical Estimates From 1996-2004 and Comparison to Hatchery Results. Draft.

    SciTech Connect (OSTI)

    Buchanan, Rebecca A.; Skalski, John R.; Broms, Kristin

    2008-12-03T23:59:59.000Z

    The combined juvenile and adult detection histories of PIT-tagged wild salmonids migrating through the Federal Columbia River Power System (FCRPS) were analyzed using the ROSTER (River-Ocean Survival and Transportation Effects Routine) statistical release-recapture model. This model, implemented by software Program ROSTER, was used to estimate survival on large temporal and spatial scales for PIT-tagged wild spring and summer Chinook salmon and steelhead released in the Snake River Basin upstream of Lower Granite Dam from 1996 to 2004. In addition, annual results from wild salmonids were compared with results from hatchery salmonids, which were presented in a previous report in this series (Buchanan, R. A., Skalski, J. R., Lady, J. L., Westhagen, P., Griswold, J., and Smith, S. 2007, 'Survival and Transportation Effects for Migrating Snake River Hatchery Chinook Salmon and Steelhead: Historical Estimates from 1996-2003', Technical report, Bonneville Power Administration, Project 1991-051-00). These results are reported here. Annual estimates of the smolt-to-adult return ratio (SAR), juvenile inriver survival from Lower Granite to Bonneville, the ocean return probability from Bonneville to Bonneville, and adult upriver survival from Bonneville to Lower Granite are reported. Annual estimates of transport-inriver (T/I) ratios and differential post-Bonneville mortality (D) are reported on a dam-specific basis for release years with sufficient numbers of wild PIT-tagged smolts transported. Transportation effects are estimated only for dams where at least 1,000 tagged wild smolts were transported from a given upstream release group. Because few wild Chinook salmon and steelhead tagged upstream of Lower Granite Dam were transported before the 2003 release year, T/I and D were estimated only for the 2003 and 2004 release years. Performance measures include age-1-ocean adult returns for steelhead, but not for Chinook salmon. Spring and summer Chinook salmon release groups were pooled across the entire Snake River Basin upstream of Lower Granite Dam for this report. Annual estimates of SAR from Lower Granite back to Lower Granite averaged 0.92% with an estimated standard error (dSE) of 0.25% for wild spring and summer Chinook salmon for tagged groups released from 1996 through 2004, omitting age-1-ocean (jack) returns. Only for the 1999 and 2000 release years did the wild Chinook SAR approach the target value of 2%, identified by the NPCC as the minimum SAR necessary for recovery. Annual estimates of SAR for wild steelhead from the Snake River Basin averaged 0.63% (dSE = 0.15%), including age-1-ocean returns, for release years 1996 through 2004. For release years when the ocean return probability from Bonneville back to Bonneville could be estimated (i.e., 1999 through 2004), it was estimated that on average approximately 83% of the total integrated mortality for nontransported, tagged wild spring and summer Chinook, and 78% for steelhead (omitting the 2001 release year), occurred during the ocean life stage (i.e., from Bonneville to Bonneville). This suggests that additional monitoring and research efforts should include the ocean and estuary environment. Annual estimates of the dam-specific T/I for Lower Granite Dam were available for the 2003 and 2004 release years for both wild Chinook salmon and wild steelhead. The estimated T/I for Lower Granite was significantly > 1.0 for Chinook in 2004 (P < 0.0001) and for steelhead in both 2003 (P < 0.0001) and 2004 (P < 0.0001), indicating that for these release years, wild fish transported at Lower Granite returned there in higher proportions than fish that were returned to the river at Lower Granite, or that passed Lower Granite without detection as juveniles. Annual estimates of the dam-specific T/I for Little Goose Dam were available for wild Chinook salmon for both 2003 and 2004. The estimated T/I for Little Goose was significantly > 1.0 for wild Chinook in 2004 (P = 0.0024), but not in 2003 (P = 0.1554). Differential post-Bonneville mortality (D) is the ratio of pos

  4. AN APPROACH TO CHARACTERIZING & EVALUATING ALTERNATIVES FOR THE DECOMMISSIONING OF SUB-GRADE STRUCTURES AT THE PLUTONIUM FINISHING PLANT (PFP)

    SciTech Connect (OSTI)

    HOPKINS, A.M.; KLOS, D.B.

    2007-01-25T23:59:59.000Z

    In 2002, the Richland Operations Office (RL) of the US Department of Energy (DOE), the US Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) developed milestones for transitioning the Plutonium Finishing Plant (PFP) facility to a clean slab-on-grade configuration. These milestones required developing an engineering evaluation/cost analysis (EF/CA) for the facility's sub-grade structures and installations as part of a series of evaluations intended to provide for the transition of the facility to a clean slab-on-grade configuration. In addition to supporting decisions for interim actions, the analyses of sub-grade structures and installations performed through this EE/CA will contribute to the remedial investigation feasibility study(ies) and subsequently to the final records of decision for the relevant operable units responsible for site closure in the 200 West Area of the Hanford Site.

  5. Organic Separation Test Results

    SciTech Connect (OSTI)

    Russell, Renee L.; Rinehart, Donald E.; Peterson, Reid A.

    2014-09-22T23:59:59.000Z

    Separable organics have been defined as “those organic compounds of very limited solubility in the bulk waste and that can form a separate liquid phase or layer” (Smalley and Nguyen 2013), and result from three main solvent extraction processes: U Plant Uranium Recovery Process, B Plant Waste Fractionation Process, and Plutonium Uranium Extraction (PUREX) Process. The primary organic solvents associated with tank solids are TBP, D2EHPA, and NPH. There is concern that, while this organic material is bound to the sludge particles as it is stored in the tanks, waste feed delivery activities, specifically transfer pump and mixer pump operations, could cause the organics to form a separated layer in the tank farms feed tank. Therefore, Washington River Protection Solutions (WRPS) is experimentally evaluating the potential of organic solvents separating from the tank solids (sludge) during waste feed delivery activities, specifically the waste mixing and transfer processes. Given the Hanford Tank Waste Treatment and Immobilization Plant (WTP) waste acceptance criteria per the Waste Feed Acceptance Criteria document (24590-WTP-RPT-MGT-11-014) that there is to be “no visible layer” of separable organics in the waste feed, this would result in the batch being unacceptable to transfer to WTP. This study is of particular importance to WRPS because of these WTP requirements.

  6. Spent fuel drying system test results (second dry-run)

    SciTech Connect (OSTI)

    Klinger, G.S.; Oliver, B.M.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J.; Ritter, G.A.

    1998-07-01T23:59:59.000Z

    The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks have been detected in the basins and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 7.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the second dry-run test, which was conducted without a fuel element. With the concurrence of project management, the test protocol for this run, and subsequent drying test runs, was modified. These modifications were made to allow for improved data correlation with drying procedures proposed under the IPS. Details of these modifications are discussed in Section 3.0.

  7. Diesel Emission Control -- Sulfur Effects (DECSE) Program; Phase I Interim Data Report No. 4: Diesel Particulate Filters -- Final Report

    SciTech Connect (OSTI)

    DOE; ORNL; NREL; EMA; MECA

    2000-01-15T23:59:59.000Z

    The Diesel Emission Control-Sulfur Effects (DECSE) is a joint government/industry program to determine the impact of diesel fuel sulfur levels on emission control systems whose use could lower emissions of nitrogen oxides (NOx) and particulate matter (PM) from on-highway trucks in the 2002--2004 model years. Phase 1 of the program was developed with the following objectives in mind: (1) evaluate the effects of varying the level of sulfur content in the fuel on the emission reduction performance of four emission control technologies; and (2) measure and compare the effects of up to 250 hours of aging on selected devices for multiple levels of fuel sulfur content. This is the fourth and final report for the DPF test program and covers the effect of diesel sulfur level on: a catalyzed diesel particulate filter (CDPF), and a continuously regenerating diesel particulate filter (CR-DPF).

  8. In-Plant Reliability Data base for nuclear plant components. Interim report: diesel generators, batteries, chargers and inverters

    SciTech Connect (OSTI)

    Kahl, W.K.; Borkowski, R.J.

    1985-01-01T23:59:59.000Z

    The objective of the In-Plant Reliability Data (IPRD) program is to develop a comprehensive, component-specific reliability data base for probabilistic risk assessment and for other statistical analyses relevant to component reliability evaluations. This document is the product of a pilot study that was undertaken to demonstrate the methodology and feasibility of applying IPRDS techniques to develop and analyze the reliability characteristics of key electrical components in five nuclear power plants. These electrical components include diesel generators, batteries, battery chargers and inverters. The sources used to develop the data base and produce the component failure rates and mean repair times were the plant equipment lists, plant drawings, maintenance work requests, Final Safety Analysis Reports (FSARs), and interviews with plant personnel. The data spanned approximately 33 reactor-years of commercial operation.

  9. Interim measure conceptual design for remediation at the former CCC/USDA grain storage facility at Centralia, Kansas : pilot test and remedy implementation.

    SciTech Connect (OSTI)

    LaFreniere, L. M.; Environmental Science Division

    2007-11-09T23:59:59.000Z

    This document presents an Interim Measure Work Plan/Design for the short-term, field-scale pilot testing and subsequent implementation of a non-emergency Interim Measure (IM) at the site of the former grain storage facility operated by the Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) in Centralia, Kansas. The IM is recommended to mitigate both (1) localized carbon tetrachloride contamination in the vadose zone soils beneath the former facility and (2) present (and potentially future) carbon tetrachloride contamination identified in the shallow groundwater beneath and in the immediate vicinity of the former CCC/USDA facility. Investigations conducted on behalf of the CCC/USDA by Argonne National Laboratory have demonstrated that groundwater at the Centralia site is contaminated with carbon tetrachloride at levels that exceed the Kansas Tier 2 Risk-Based Screening Level (RBSL) and the U.S. Environmental Protection Agency's maximum contaminant level of 5.0 {micro}g/L for this compound. Groundwater sampling and analyses conducted by Argonne under a monitoring program approved by the Kansas Department of Health and Environment (KDHE) indicated that the carbon tetrachloride levels at several locations in the groundwater plume have increased since twice yearly monitoring of the site began in September 2005. The identified groundwater contamination currently poses no unacceptable health risks, in view of the absence of potential human receptors in the vicinity of the former CCC/USDA facility. Carbon tetrachloride contamination has also been identified at Centralia in subsurface soils at concentrations on the order of the Kansas Tier 2 RBSL of 200 {micro}g/kg in soil for the soil-to-groundwater protection pathway. Soils contaminated at this level might pose some risk as a potential source of carbon tetrachloride contamination to groundwater. To mitigate the existing contaminant levels and decrease the potential future concentrations of carbon tetrachloride in groundwater and soil, the CCC/USDA recommends initial short-term, field-scale pilot testing of a remedial approach that employs in situ chemical reduction (ISCR), in the form of a commercially available material marketed by Adventus Americas, Inc., Freeport, Illinois (http://www.adventusgroup.com). If the pilot test is successful, it will be followed by a request for KDHE authorization of full implementation of the ISCR approach. In the recommended ISCR approach, the Adventus EHC{reg_sign} material--a proprietary mixture of food-grade organic carbon and zero-valent iron--is introduced into the subsurface, where the components are released slowly into the formation. The compounds create highly reducing conditions in the saturated zone and the overlying vadose zone. These conditions foster chemical and biological reductive dechlorination of carbon tetrachloride. The anticipated effective lifetime of the EHC compounds following injection is 1-5 yr. Although ISCR is a relatively innovative remedial approach, the EHC technology has been demonstrated to be effective in the treatment of carbon tetrachloride contamination in groundwater and has been employed at a carbon tetrachloride contamination site elsewhere in Kansas (Cargill Flour Mill and Elevator, Wellington, Kansas; KDHE Project Code C209670158), with the approval of the KDHE. At Centralia, the CCC/USDA recommends use of the ISCR approach initially in a short-term pilot test addressing the elevated carbon tetrachloride levels identified in one of three persistently highly contaminated areas ('hot-spot areas') in the groundwater plume. In this test, a three-dimensional grid pattern of direct-push injection points will be used to distribute the EHC material (in slurry or aqueous form) throughout the volume of the contaminated aquifer and (in selected locations) the vadose zone in the selected hot-spot area. Injection of the EHC material will be conducted by a licensed contractor, under the supervision of Adventus and Argonne technical personnel. The contractor will be identified upon acceptanc

  10. Electrochemical corrosion-scoping experiments: An evaluation of the results

    SciTech Connect (OSTI)

    Smith, H.D.

    1988-09-01T23:59:59.000Z

    Prior to emplacement in a nuclear waste repository, each waste form must be well characterized with respect to its behavior in the environments expected to develop in the repository. This scoping study was designed to obtain a qualitative idea of how spent fuel cladding would respond to a hot water environment that could develop in a tuff repository at a time when temperatures have cooled to {approximately}95{degree}C and hot liquid water has infiltrated the repository horizon. That information would then be used to establish more definitive tests on cladding behavior in a tuff repository. For this study bundles of spent fuel cladding held together with a 304 stainless steel (SS) wrap were constructed which simulate the geometries and materials associations in a breached 304L SS container. They were exposed to 90{degree}C tuff-equilibrated Well J-13 water for periods of 2, 6, and 12 mo. During the experiments, the water level, temperature, conductivity, and pH were monitored on a regular basis. The water was also checked periodically for carbon (organic, inorganic, and later in the experiment Carbon-14) and zirconium. More extensive water analyses were carried out at the midpoint and completion of the experiments. 12 refs., 16 figs., 5 tabs.

  11. Initial Evaluation of Smart Irrigation Controllers: Year Two (2009) Results 

    E-Print Network [OSTI]

    Swanson, Charles; Fipps, Guy

    2010-01-01T23:59:59.000Z

    to determine their performance and reliability under Texas conditions from an “end-user” point of view. The “end-user” is considered to be the landscape or irrigation professional (such as a Licensed Irrigator in Texas) installing the controller. During...

  12. EVALUATION RESULT OF THE ALERT-2 RURAL INTERSECTION

    E-Print Network [OSTI]

    Minnesota, University of

    .8Wh Battery Capacity 67Wh 1248Wh Days of Storage Without Charge 7 days 45 days Solar Panel 14W 20W;Battery Power ALERT-1 ALERT-2 Average Daily Power Demand 26Wh 36Wh Battery Capacity 106Wh 2,688Wh Days of Storage Without Charge 7 days 25 days Solar Panel 20W 20W ALERT-1 ALERT-2 Average Daily Power Demand 8Wh 7

  13. Evaluation of Smart Irrigation Controllers: Year 2011 Results

    E-Print Network [OSTI]

    Fipps, G.; Swanson, C.

    and Extension Specialist, Biological and 2 Agricultural Engineering, 2117 TAMU, College Station, TX 77843-2117; http://itc.tamu.edu SUMMARY A smart controller testing facility was established by the Irrigation Technology Center at Texas A&M University... this water balance. The parameters most commonly used include: ? ET (actual plant evapotranspiration) ? Rainfall ? Site properties (soil texture, root zone depth, water holding capacity) ? MAD (managed allowable depletion) The IA SWAT committee has...

  14. Long-Term Results from Evaluation of Advanced New Construction...

    Office of Scientific and Technical Information (OSTI)

    (STIP) E-Link Science Research Connection DOE Science Resources - National Library of Energy Beta SciTech Connect DOE PAGESBeta DOE Data Explorer ScienceCinema DOepatents DOE...

  15. Fuel Cell Bus Evaluation Results (Presentation) | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport inEnergy0.pdf

  16. Ride and Drive Evaluation Results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin ofEnergy at Waste-to-Energy usingofRetrofittingFund WebinarsDepartment of

  17. Summary of Emergency Management Results from Pilot Evaluations | Department

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently AskedEnergyIssues DOE'sSummary Special Report:1, 2015 - June 5,May

  18. King County Metro Transit Hybrid Articulated Buses: Final Evaluation Results

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHigh SchoolIn12electron beamJoin2015JustKateKent5 B O N N EKim DavisKing

  19. BC Transit Fuel Cell Bus Project: Evaluation Results Report

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office511041cloth DocumentationProductsAlternativeOperationalAugust Nazim Ali Bharmal, Comparisons ofBBQ - Is

  20. Summary of Emergency Management Results from Pilot Evaluations | Department

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over Our InstagramStructure of All-Polymer. .Energy ConversionEnergyAugust 27of

  1. Program Course Corrections Based on Evaluation Results | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the.pdfBreakingMay 2015 < prev next > SunChallengeHydrotreating

  2. TurningPoint Evaluation Results | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium Transferon theTedRegion | Department ofAugust 14,Turning on the Fan

  3. BC Transit Fuel Cell Bus Project Evaluation Results: Second Report

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisiting the TWP TWPAlumniComplex historian ... B&WBen LarsonBBC Video LooksBC

  4. Hazard evaluation

    SciTech Connect (OSTI)

    Vervalin, C.H.

    1986-12-01T23:59:59.000Z

    Recent major disasters in the hydrocarbon processing industry (HPI) have inspired renewed interest in the fine-tuning of hazard evaluation methods. In addition to traditional risk-study methods, the computer promises eventual expert systems to vastly improve the speed of assembling and using loss-prevention information. But currently, the computerization of hazard evaluation finds the HPI taking a back seat to aerospace/nuclear industries. The complexity of creating computer databases and expert systems has not-however-kept some HPI companies from plunging in. Arabian American Oil Co. (Aramco) has used computer-generated information in working with probabilistic risk analysis. Westinghouse has used its risk-analysis experience in the nuclear field to build a computer-based program for HPI clients. An Exxon plant has a huge data bank as the basis for its Hazard Loss Information System.

  5. MODULAR CONSTRUCTION SYSTEM EVALUATION

    SciTech Connect (OSTI)

    S. Gillespie

    2002-08-08T23:59:59.000Z

    The purpose of this study is to respond to U.S. Department of Energy (DOE) Technical Direction Letter (TDL) 02-003 (Waisley 2001), which directs Bechtel SAIC Company, LLC (BSC) to complete a design study to recommend repository design options to support receipt and/or emplacement of any or all of the following: commercial spent nuclear fuel (CSNF), high-level radioactive waste (HLW), DOE-managed spent nuclear fuel (DSNF) (including naval spent nuclear fuel [SNF]), and immobilized plutonium (if available), as soon as practicable, but no later than 2010. From the possible design options, a recommended approach will be determined for further evaluation to support the preliminary design of the repository. This study integrates the results of the repository Design Evolution Study (Rowe 2002) with supporting studies concerning national transportation options (BSC 2002b) and Nevada transportation options (Gehner 2002). The repository Design Evolution Study documents the processes used to reevaluate the design, construction, operation, and cost of the repository in response to TDL 02-003 (Waisley 2001), and to determine possible repository conceptual design options. The transportation studies evaluate the national and Nevada transportation options that support the repository conceptual design options. An evaluation methodology was established, based on Program-level requirements developed for the study in reference BSC 2001a, to allow the repository and system design options to be evaluated on a consistent basis. The transportation options and the design components were integrated into system design implementation options, which were evaluated using receipt and emplacement scenarios. The scenarios tested the ability of the design concept to adapt to changes in funding, waste receipt rate, and Nevada rail transportation availability. The results of the evaluation (in terms of system throughput, cost, and schedule) were then compared to the Program-level requirements, and recommendations for design alternatives, requirements changes, or further evaluation were developed.

  6. An interim report to the manager of the Paducah Gaseous Diffusion Plant from the Paducah Environmental Advisory Committee

    SciTech Connect (OSTI)

    Jackson, G.D.

    1987-10-01T23:59:59.000Z

    The Paducah Environmental Advisory Committee was formed as: (1) an outgrowth of other Environmental Advisory Committees already in existence at Oak Ridge and other Martin Marietta Energy Systems plants; (2) a result of public concern following significant nuclear incidents at Bhopal and Chernobyl; (3) a result of the new direction and commitment of the management of the Paducah Gaseous Diffusion Plant following contract acquisition by Martin Marietta Energy Systems; and (4) a means of reducing and/or preventing local and/or public concern regarding the activities of and potential risks created by PGDP. This report discusses the following issues and concerns of the Committee arrived at through a series of meetings: (1) groundwater monitoring; (2) long-range tails storage; C-404, scrap yrads, and PCB and TCE cleanup; nuclear criticality plan and alarm systems; documentation of historical data regarding hazardous waste burial grounds; dosimeter badges; and asbestos handling and removal.

  7. A comprehensive program to develop correlations for the physical properties of Kraft black liquor. Interim report No. 2

    SciTech Connect (OSTI)

    Fricke, A.L.

    1990-12-01T23:59:59.000Z

    Experimental effort for the program to evaluate physical properties of kraft black liquors is now proceeding well. Experimental work includes pulping, liquor analysis, lignin purification and characterization, vapor-liquid equilibria, heat capacity, heats of solution and combustion, and viscosity measurements. Measurement of thermal conductivity has not yet begun. Collection of the data necessary for development of generalized correlations is proceeding, but will require about two more years. The digester is operating very well. It is now possible to operate the digester as a closed, rotating reactor or as a batch reactor with liquor circulation. When operated with liquor circulation, temperatures within the chip bed can be monitored during cooking. Cooking is reproducible, and cooks are being performed to produce liquors for experimental studies. The digester could be further modified to permit us to conduct rapid exchange batch pulping or to permit us to simulate continuous pulping. Liquors to be used in experimental studies are concentrated in our large scale evaporator or in our small scale evaporator. The large scale evaporator is used to concentrate liquors to about 50% solids for storage and for use in studies requiring high solids liquors. The small scale evaporator is used for preparing final samples to as high as 85% solids and for measuring vapor-liquid equilibria. Liquors are now routinely analyzed to determine all components, except higher molecular weight organic acids and extractives. Lignin determination by uv-visible means has been improved. Lignin purification from black liquor has been improved and lignin molecular weights are determined routinely. Work on lignin molecular weight distribution is still not satisfactory, but recent developments holds promise.

  8. Electromagnetic interference impact of the proposed emitters for the High Frequency Active Auroral Research Program (HAARP). Interim report

    SciTech Connect (OSTI)

    Robertshaw, G.A.; Snyder, A.L.; Weiner, M.M.

    1993-05-14T23:59:59.000Z

    The proposed HAARP emitters at the Gakona (Alaska) preferred site and at the Clear AFS (Alaska) alternative site are the Ionospheric Research Instrument (IRI), the Incoherent Scatter Radar (ISR), and the Vertical Incidence Sounder(VIS). The electromagnetic interference (EMI) impact of those emitters on receiving systems in the vicinity of the sites is estimated in this study. The results are intended for use as an input to the Air Force Environmental Impact Statement as part of the Environmental Impact Analysis Process.

  9. Liquid honing evaluation

    SciTech Connect (OSTI)

    Slanina, J.T.

    1991-07-01T23:59:59.000Z

    The conveyorized wetblast machine was characterized for epoxy/glass and polyimide/glass multilayers using a 12-run Plackett-Burman screening experiment and a four-variable factorial experiment. Test panels were processed using slurry and water mixtures and water only. Plated-through-holes were evaluated after wetblasting and copper plating for plating characteristics. Test panels were wetblasted and processed through photolithography operations. Photoresist adhesion characteristics were evaluated. As a result of this study, the optimum production conditions were determined for slurry concentration, blast pressure, oscillator speed, conveyor speed, and blast gun distance. 2 figs., 18 tabs.

  10. Development of test acceptance standards for qualification of the glass-bonded zeolite waste form. Interim annual report, October 1995--September 1996

    SciTech Connect (OSTI)

    Simpson, L.J.; Wronkiewicz, D.J.; Fortner, J.A.

    1997-09-01T23:59:59.000Z

    Glass-bonded zeolite is being developed at Argonne National Laboratory in the Electrometallurgical Treatment Program as a potential ceramic waste form for the disposition of radionuclides associated with the US Department of Energy`s (DOE`s) spent nuclear fuel conditioning activities. The utility of standard durability tests [e.g. Materials Characterization Center Test No. 1 (MCC-1), Product Consistency Test (PCT), and Vapor Hydration Test (VHT)] are being evaluated as an initial step in developing test methods that can be used in the process of qualifying this material for acceptance into the Civilian Radioactive Waste Management System. A broad range of potential repository conditions are being evaluated to determine the bounding parameters appropriate for the corrosion testing of the ceramic waste form, and its behavior under accelerated testing conditions. In this report we provide specific characterization information and discuss how the durability test results are affected by changes in pH, leachant composition, and sample surface area to leachant volume ratios. We investigate the release mechanisms and other physical and chemical parameters that are important for establishing acceptance parameters, including the development of appropriate test methodologies required to measure product consistency.

  11. Turbine fuels from tar-sands bitumen and heavy oil. Part 2. Phase II. Laboratory sample production. Interim report, 1 October 1983-31 October 1985

    SciTech Connect (OSTI)

    Talbot, A.F.; Elanchenny, V.; Schwedock, J.P.; Swesey, J.R.

    1986-05-01T23:59:59.000Z

    The conversion of domestic tar-sands bitumens or heavy crude oils into aviation turbine fuels was studied in small scale equipment to demonstrate the process scheme consisting of hydrovisbreaking the bitumen or crude residuum follwed by catalytic hydrotreating or hydrocracking of the resultant naphtha or distillate fractions. Four different feedstocks were employed; two were bitumens (from Kentucky or Utah) and two were heavy crudes from California. Significant operating parameters were examined for each process step. Prototype naphtha and kerosene-type fuel samples compared well with JP-4 and JP-8 specifications, although fuels prepared from Utah bitumen (Sunnyside deposit) were deficient in freeze point. Initiation of Phase III, pilot-plant-scale evaluation of the process is recommended.

  12. Evaluation Returns

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,OfficeEnd of Year 2010Salt | Department ofEvaluation Report:Returns Most popular

  13. DETERMINATION OF CORROSION INHIBITOR CRITERIA FOR TYPE III/IIIA TANKS DURING SALT DISSOLUTION OPERATIONS INTERIM REPORT

    SciTech Connect (OSTI)

    Counts, K; Bruce Wiersma, B; John Mickalonis, J

    2007-12-31T23:59:59.000Z

    Preparation of high level waste for vitrification involves in part the dissolution of salt cake from the carbon steel storage tanks. During dissolution, a point is reached in which the corrosion inhibitors, hydroxide and nitrite, are diluted below established guidelines, and nitrate stress corrosion cracking (SCC) is possible. Because the addition of inhibitors may be counterproductive to process efficiency and waste minimization, corrosion testing was initiated to revisit and possibly revise the guidelines for inhibitor limits. The bases for the work summarized in this status report are results from previously-completed phases of study. In the first two phases of study, several reduced-inhibitor levels were tested in HLW simulants with nitrate concentrations ranging from 4.5 M to 8.5 M. The first two phases of work determined, among other things, the reduced-inhibitor levels and solution chemistries in which heat-treated and non-heat-treated A537 carbon steel is susceptible to SCC, crevice corrosion, and pitting. The work covered in this current task both builds on and verifies the conclusions of the previous work. The current work involves testing of low levels of inhibitors in HLW simulants with 5.5 M to 8.5 M nitrate concentrations. Stressed U-bend specimens, both polarized and non-polarized, were tested. Non-polarized U-bend testing is ongoing, with the U-bends currently in test for 100 days. The purpose of the testing is to determine SCC susceptibility in the vapor space (VS) and liquid air interface (LAI) regions of the HLW tanks under conditions expected during salt dissolution, and also to verify previous accelerated testing. The simulated wastes being tested have nitrate concentrations of 5.5 M and 8.5 M and inhibitor levels of 0.01 M/0.01 M hydroxide/nitrite and 0.1 M/ 0.1 M hydroxide/nitrite. The open circuit potential measurements being monitored and the corrosion morphology of the U-bends are in agreement with results and observations of previous phases of work. No SCC has occurred in the first 100 days of testing. The LAI specimens experienced minor corrosion at the liquid line with corrosion products visible on the weld material and in the heat-affected zones on either side of the welds. The VS specimens are more evenly and slightly more corroded. Polarized U-bend testing is complete after approximately 80 days of testing. No SCC occurred, but the results are inconclusive due to a competing, unexpected galvanic corrosion mechanism that interfered in the last 50 days of testing. No cracking was indicated during the first month. The tests will be repeated in order to satisfy the original objective which was to determine the effect of grinding HLW tank welds and heat treating the tanks had on corrosion. Both the non-polarized and polarized U-bend tests will continue. Additionally, cyclic polarization (CP) testing will be performed to examine the effects of surface oxides on corrosion and the differences in corrosion susceptibility between welded and un-welded areas.

  14. STACE: Source Term Analyses for Containment Evaluations of transport casks

    SciTech Connect (OSTI)

    Seager, K. D.; Gianoulakis, S. E. [Sandia National Labs., Albuquerque, NM (United States); Barrett, P. R.; Rashid, Y. R. [ANATECH Research Corp., La Jolla, CA (United States); Reardon, P. C. [GRAM, Inc., Albuquerque, NM (United States)

    1992-01-01T23:59:59.000Z

    Following the guidance of ANSI N14.5, the STACE methodology provides a technically defensible means for estimating maximum permissible leakage rates. These containment criteria attempt to reflect the true radiological hazard by performing a detailed examination of the spent fuel, CRUD, and residual contamination contributions to the releasable source term. The evaluation of the spent fuel contribution to the source term has been modeled fairly accurately using the STACE methodology. The structural model predicts the cask drop load history, the mechanical response of the fuel assembly, and the probability of cladding breach. These data are then used to predict the amount of fission gas, volatile species, and fuel fines that are releasable from the cask. There are some areas where data are sparse or lacking (e.g., the quantity and size distribution of fuel rod breaches) in which experimental validation is planned. The CRUD spallation fraction is the major area where no quantitative data has been found; therefore, this also requires experimental validation. In the interim, STACE conservatively assumes a 100% spallation fraction for computing the releasable activity. The source term methodology also conservatively assumes that there is 1 Ci of residual contamination available for release in the transport cask. However, residual contamination is still by far the smallest contributor to the source term activity.

  15. Environmental audit of the Maywood Site: Formerly Utilized Sites Remedial Action Program, Maywood Interim Storage Site vicinity properties

    SciTech Connect (OSTI)

    Not Available

    1990-12-01T23:59:59.000Z

    This report presents the results of the Environmental Audit of the Maywood Site managed by the Formerly Utilized Sites Remedial Action Program (FUSRAP). The Audit was carried out from November 7 through 16, 1990. The Audit Team found overall technical competence and knowledge of management and staff to be excellent. This applies to DOE as well as to Bechtel National, Incorporated (BNI). In particular, there was excellent knowledge of federal, state, and local environmental regulations, as well as analysis for applicability of these regulations to FUSRAP. Project management of the Maywood Site is also excellent. BNI and DOE project staff have made frequent contact with members of the community, and all removal actions and remedial investigation activities have been planned, scheduled, and accomplished with competence and attention to total quality principles. To date, all actions taken for the Maywood Site cleanup have been completed ahead of schedule and on or under budget. Weakness noted include self-assessment efforts by DOE, failure to fully implement DOE Order requirements throughout the program, and some discrepancies in formally documenting and reviewing procedures. 7 figs., 10 tabs.

  16. A comprehensive program to develop correlations for the physical properties of kraft black liquors. Interim report No.3

    SciTech Connect (OSTI)

    Fricke, A.L.; Dong, D.J.; Schmidl, G.W.; Stoy, M.A.; Zaman, A.A.

    1993-09-01T23:59:59.000Z

    The black liquor properties program has conducted a systematic collection data of properties, liquor composition, and lignin characteristics. Complete data, except for some density data, has been collected for Slash Pine black liquors made by experimental pulping at a total of 25 different pulping conditions that cover the entire range used for commercial pulping. In addition, complete data has been collected for some mill liquors and partial properties or composition data has been collected on Slash Pine black liquors made at 16 different pulping conditions and some mill liquors. Data reduction methods have been developed or extended for correlation of viscosity, heat capacity, heat of dilution, and density. Correlation of properties to pulping conditions and of composition to pulping conditions has begun. In most cases, data reduction methods have been developed that are fundamentally based and that have been shown to be generally applicable to all black liquors. While it has not proven to be possible to include research for comprehensive correlations for properties for liquors from other species, we have shown that the behavior of liquors made from other species is similar to that which has been explored extensively for Slash Pine liquors. This report reviews the methods used, describes examples of data reduction methods that have been developed, and presents some preliminary results for correlation of liquor composition and properties to pulping conditions for Slash Pine black liquors.

  17. Long-term assessment of the oil spill at Bahia Las Minas, Panama. Interim report. Volume 1: Executive summary

    SciTech Connect (OSTI)

    Keller, B.D.; Jackson, J.B.C.

    1991-10-01T23:59:59.000Z

    On April 27, 1986, at least 8 million liters of medium-weight crude oil spilled from a ruptured storage tank into the Bahia Las Minas on the Caribbean Coast of Panama. Coral reefs, seagrass communities, and mangroves were affected. The area of the spill was also the location of the Smithsonian Tropical Research Institute's Galeta Laboratory where resident and visiting scientists have been studying the ecology of the Bahia Las Minas and the adjacent areas for over 15 years. Because this was a unique opportunity to assess the immediate biological effects following a major spill in the Caribbean region and to monitor the subsequent recovery, the U.S. Department of the Interior Minerals Management Service supported a 5-year environmental study. The objectives of the study are to identify any long-term changes in the marine environment that may have resulted from the spill and to understand the ecological processes causing such changes. This is the first report from the study and addresses the effects observed during the first two years of the effort.

  18. Long-term assessment of the oil spill at Bahia Las Minas, Panama. Interim report. Volume 2: Technical report

    SciTech Connect (OSTI)

    Keller, B.D.; Jackson, J.B.C.

    1991-10-01T23:59:59.000Z

    On April 27, 1986, at least 8 million liters of medium-weight crude oil spilled from a ruptured storage tank into the Bahia Las Minas on the Caribbean Coast of Panama. Coral reefs, seagrass communities, and mangroves were affected. The area of the spill was also the location of the Smithsonian Tropical Research Institute's Galeta Laboratory where resident and visiting scientists have been studying the ecology of the Bahia Las Minas and the adjacent areas for over 15 years. Because this was a unique opportunity to assess the immediate biological effects following a major spill in the Caribbean region and to monitor the subsequent recovery, the U.S. Department of the Interior Minerals Management Service supported a 5-year environmental study. The objectives of the study are to identify any long-term changes in the marine environment that may have resulted from the spill and to understand the ecological processes causing such changes. This is the first report from the study and addresses the effects observed during the first two years of the effort.

  19. Tennessee Valley Authority atmospheric fluidized-bed combustor simulation interim annual report, January 1-December 31, 1980

    SciTech Connect (OSTI)

    Wells, J.W.; Culver, M.H.; Krishnan, R.P.

    1981-09-01T23:59:59.000Z

    A detailed description of the work performed during 1980 for the Tennessee Valley Authority (TVA) in support of the TVA Fluidized-Bed Combustion (FBC) Demonstration Plant Program is presented. The work was carried out under Task 4, modeling and simulation of atmospheric fluidized-bed combustion (AFBC) systems. The overall objective of this task is to develop a steady-state mathematical model with the capability of predicting trends in bed performance under various feed and operating conditions. Previously during 1979, three predictive subcodes (subprograms) were developed: bubble growth subcode, elutriation-attrition subcode, and coal combustion subcode. During 1980, three additional predictive subcodes were developed: the SO/sub 2/ capture subcode, the NO/sub x/ emissions subcode, and the freeboard subcode. Also, during this period, the following subcodes were combined to form an overall simulation code of the AFBC bed: (1) bubble growth subcode, (2) elutriation-attrition subcode, (3) coal combustion subcode, (4) SO/sub 2/ capture subcode, and (5) NO/sub x/ emissions subcode. In addition, an energy balance routine was added to the combined code. The resulting overall bed simulation, which is currently being tested with experimental data, is capable of predicting how some of the important operating variables affect AFBC's performance. The freeboard model has been combined with the overall bed simulation and is currently being debugged. Once the overall AFBC simulation is operational, it will be tested against field data from operating AFBCs and used to simulate the TVA/Electric Power Research Institute (EPRI) 20-MW(e) AFBC pilot plant. (WHK)

  20. Interim Management of Nuclear Materials

    Broader source: Energy.gov (indexed) [DOE]

    by the appropriate agency (DOE, the Department of Transportation, the Nuclear Regulatory Commission, or the International Atomic Energy Agency) for full containment of the...

  1. Hanford Generic Interim Safety Basis

    SciTech Connect (OSTI)

    Lavender, J.C.

    1994-09-09T23:59:59.000Z

    The purpose of this document is to identify WHC programs and requirements that are an integral part of the authorization basis for nuclear facilities that are generic to all WHC-managed facilities. The purpose of these programs is to implement the DOE Orders, as WHC becomes contractually obligated to implement them. The Hanford Generic ISB focuses on the institutional controls and safety requirements identified in DOE Order 5480.23, Nuclear Safety Analysis Reports.

  2. MPHYS Interim Report Alex Colvill

    E-Print Network [OSTI]

    Gilfoyle, Jerry

    ) subsystem of the upgraded Continuous Electron Beam Accelerator Facility Large Acceptance Spectrometer (CLAS called CEBAF, or Continuous Electron Beam Accelerator Facility, which supplies high quality, optionally owned facility, the centerpiece of which is a 7/8 of a mile long racetrack-shaped electron accelerator

  3. Administration & Finance Vice President (Interim)

    E-Print Network [OSTI]

    Dyer, Bill

    /Investment Monitoring Plant Fund Set-up/Monitoring Endowment Fund Set-up System Support Group Banner Production Control President Bob Lashaway Division Planning & Information Systems Director Vacant Financial Services Assistant Policing Parking Services Facilities Planning, Design & Construction Planning Campus Master Planning

  4. Interim Management of Nuclear Materials

    Broader source: Energy.gov (indexed) [DOE]

    and irradiated reactor components and control rods 420 items C-, K-, L-, and P-Reactors Depleted uranium oxide 36,000 drums R-Reactor, Buildings 221-1F, 221-12F, 221-21F,...

  5. EMAB Risk Subcommittee Interim Report

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:RevisedAdvisory Board Contributions EMEM RecoveryManagement'sJuneApril

  6. Fact Sheet: Interim Response Actions.

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling CorpNewCF INDUSTRIES,L ELIMINATION

  7. Plans, Implementation, and Results

    Broader source: Energy.gov [DOE]

    About the Weatherization and Intergovernmental Programs Office (WIPO) including information on plans, implementations, and results.

  8. Quality assurance plan for the Molten Salt Reactor Experiment Remediation Project at the Oak Ridge National Laboratory. Phase 1 -- Interim corrective measures and Phase 2 -- Purge and trap reactive gases

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    This Quality Assurance Plan (QAP) identifies and describes the systems utilized by the Molten Salt Reactor Experiment Remediation Project (MSRERP) personnel to implement the requirements and associated applicable guidance contained in the Quality Program Description Y/QD-15 Rev. 2 (Energy Systems 1995f). This QAP defines the quality assurance (QA) requirements applicable to all activities and operations in and directly pertinent to the MSRERP Phase 1--Interim Corrective Measures and Phase 2--Purge and Trap objectives. This QAP will be reviewed, revised, and approved as necessary for Phase 3 and Phase 4 activities. This QAP identifies and describes the QA activities and procedures implemented by the various Oak Ridge National Laboratory support organizations and personnel to provide confidence that these activities meet the requirements of this project. Specific support organization (Division) quality requirements, including the degree of implementation of each, are contained in the appendixes of this plan.

  9. Hazard analysis results report

    SciTech Connect (OSTI)

    Niemi, B.J., Westinghouse Hanford

    1996-09-30T23:59:59.000Z

    This document describes and defines the Hazard Analysis Results for the Tank Waste Remediation System Final Safety Analysis Report.

  10. Geothermal: Search Results

    Office of Scientific and Technical Information (OSTI)

    Search Results Geothermal Technologies Legacy Collection HelpFAQ | Site Map | Contact Us HomeBasic Search About Publications Advanced Search New Hot Docs News Related Links The...

  11. User Survey Results | EMSL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    have accessed computing resources during the prior year. The results of the most recent survey are posted here with management responses to concerns or issues identified by our...

  12. Accelerometer and strain gage evaluation

    SciTech Connect (OSTI)

    Ammerman, D.J.; Madsen, M.M.; Uncapher, W.L.; Stenberg, D.R.; Bronowski, D.R.

    1991-06-19T23:59:59.000Z

    This document describes the method developed by Sandia National Laboratories (SNL) to evaluate transducer used in the design certification testing of nuclear material shipping packages. This testing project was performed by SNL for the Office of Civilian Radioactive Waste Management (OCRWM). This evaluation is based on the results of tests conducted to measure ruggedness, failure frequency, repeatability, and manufacturers' calibration data under both field and laboratory conditions. The results of these tests are provided and discussed. The transducer were selected for testing by surveying cask contractors and testing facilities. Important insights relating to operational characteristics of accelerometer types were gained during field testing. 11 refs., 105 figs., 16 tabs.

  13. Overview of ALICE results

    E-Print Network [OSTI]

    Kryshen, E L

    2013-01-01T23:59:59.000Z

    Selected ALICE results on the global event properties, particle spectra, azimuthal anisotropy, heavy flavour and quarkonium production in Pb-Pb collisions at sqrt(s_NN) = 2.76 TeV are presented. First results on p-Pb collisions at sqrt(s_NN) = 5.02 TeV are briefly reviewed.

  14. Diffraction Results from CDF

    SciTech Connect (OSTI)

    Goulianos, Konstantin

    2012-04-01T23:59:59.000Z

    We present final results by the CDF II collaboration on diffractive W and Z production, report on the status of ongoing analyses on diffractive dijet production and on rapidity gaps between jets, and briefly summarize results obtained on exclusive production pointing to their relevance to calibrating theoretical models used to predict exclusive Higgs-boson production at the LHC.

  15. Recent results from TRISTAN

    SciTech Connect (OSTI)

    Enomoto, Ryoji [National Laboratory for High Energy Physics, Ibaraki (Japan)

    1997-01-01T23:59:59.000Z

    TRISTAN results on {gamma}{gamma} physics from 1994 to 1995 are reviewed in this report. We have systematically investigated jet production, the {gamma}-structure function, and charm pair production in {gamma}{gamma} processes. The results are discussed, and future prospects are presented.

  16. Radiological survey results at 1 Shady Lane, Lodi, New Jersey (LJ095)

    SciTech Connect (OSTI)

    Foley, R.D.; Johnson, C.A.

    1995-07-01T23:59:59.000Z

    The US Department of Energy (DOE) conducted remedial action at the Stepan property in Maywood, New Jersey and several vicinity properties in Lodi, New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Maywood Interim Storage Site (MISS), adjacent to the former Maywood Chemical Works facility. The property at One Shady Lane, Lodi, New Jersey was not one of these vicinity properties but was surveyed by DOE at the request of the owner. At the request of DOE, a team from Oak Ridge National Laboratory conducted a radiological survey at this property. The purpose of the survey, conducted in November 1994, was to confirm whether remedial actions were to be performed on the property in order to be in compliance with the identified Guidelines. The radiological survey included surface gamma scans and gamma readings at 1 meter, and the collection of soil samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at One Shady Lane, Lodi, New Jersey, were comparable to background levels in the area, and well within the limits prescribed by DOE radiological guidelines. Based on the results of the radiological survey data, this property does not meet guidelines for inclusion under FUSRAP.

  17. Radiological verification survey results at 14 Peck Ave., Pequannock, New Jersey (PJ001V)

    SciTech Connect (OSTI)

    Rodriguez, R.E.; Johnson, C.A.

    1995-05-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) conducted remedial action during 1993 at the Pompton Plains Railroad Spur and eight vicinity properties in the Wayne and Pequannock Townships in New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Wayne Interim Storage Site (WISS), formerly the W. R. Grace facility. The property at 14 Peck Ave., Pequannock, New Jersey is one of these vicinity properties. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey at this property. The purpose of the survey, conducted between September and December 1993, was to confirm the success of the remedial actions performed to remove any radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at 1 meter, beta-gamma scans, and the collection of soil and debris samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at 14 Peck Ave. were within applicable DOE guidelines. Based on the results of the remedial action data and confirmed by the verification survey data, the portions of the site that had been remediated during this action successfully meet the DOE remedial action objectives.

  18. Radiological verification survey results at 7 Peck Ave., Pequannock, New Jersey (PJ003V)

    SciTech Connect (OSTI)

    Rodriguez, R.E.; Johnson, C.A.

    1995-05-01T23:59:59.000Z

    The US Department of Energy (DOE) conducted remedial action during 1993 at the Pompton Plains Railroad Spur and eight vicinity properties in the Wayne and Pequannock Townships in New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Wayne Interim Storage Site (WISS), formerly the W.R. Grace facility. The property at 7 Peck Ave., Pequannock, New Jersey is one of these vicinity properties. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey at this property. The purpose of the survey, conducted between September and December 1993, was to confirm the success of the remedial actions performed to remove any radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at 1 meter, beta-gamma scans, and the collection of soil samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at 7 Peck Ave. were within applicable DOE guidelines. Based on the results of the remedial action data and confirmed by the verification survey data, the portions of the site that had been remediated during this action successfully meet the DOE remedial action objectives.

  19. Spent fuel drying system test results (first dry-run)

    SciTech Connect (OSTI)

    Klinger, G.S.; Oliver, B.M.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J.; Ritter, G.A.

    1998-07-01T23:59:59.000Z

    The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site. Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 7.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the first dry-run test, which was conducted without a fuel element. The empty test apparatus was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The data from this dry-run test can serve as a baseline for the first two fuel element tests, 1990 (Run 1) and 3128W (Run 2). The purpose of this dry-run was to establish the background levels of hydrogen in the system, and the hydrogen generation and release characteristics attributable to the test system without a fuel element present. This test also serves to establish the background levels of water in the system and the water release characteristics. The system used for the drying test series was the Whole Element Furnace Testing System, described in Section 2.0, which is located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodology are given in section 3.0, and the experimental results provided in Section 4.0. These results are further discussed in Section 5.0.

  20. Sensitivity and Scenario Results

    E-Print Network [OSTI]

    Yu, Winston

    Presents the results of various scenarios using models used to study water, climate, agriculture and the economy in Pakistan's Indus Basin, and discusses the policy and investment implications. The water allocations per ...

  1. Electroweak results from CDF

    SciTech Connect (OSTI)

    D. S. Waters

    2004-06-02T23:59:59.000Z

    Inclusive W and Z production cross-sections have been measured by CDF and certain electroweak parameters extracted with high precision from these measurements. New results on diboson production at the Tevatron are also presented.

  2. Recent MEG results

    E-Print Network [OSTI]

    G. Cavoto

    2010-12-09T23:59:59.000Z

    New results of a search for the ultra-rare decay $\\mu \\to e \\gamma$ by the MEG collaboration are reported in this contribution. The data were taken during 2009 and correspond to approximately 6.5 10$^{13}$ muon stopped on target. A maximum likelihood analysis sets an upper limit at 90\\% C.L. on the branching ratio, BF($\\mu \\to e \\gamma$) $< $1.5 10$^{-11}$. The results presented here are preliminary.

  3. Evaluation of the DHCE Experiment

    SciTech Connect (OSTI)

    Greenwood, Lawrence R.; Baldwin, David L.; Hollenberg, Glenn W.; Kurtz, Richard J.

    2002-03-31T23:59:59.000Z

    The Dynamic Helium Charging Experiment (DHCE) experiment was conducted in the Fast Flux Test Facility (FFTF) during cycle 12, which was completed in 1992. The purpose of the experiment was to enhance helium generation in vanadium alloys to simulate fusion reactor helium-to-dpa ratios with a target goal of 4-5 appm He/dpa. The Fusion Materials Science Program is considering mounting another experiment in hopes of gathering additional data on the effect of helium on the mechanical and physical properties of vanadium structural materials. Pacific Northwest National Laboratory was assigned the task of evaluating the feasibility of conducting another DHCE experiment by carefully evaluating the results obtained of the first DHCE experiment. This report summarizes the results of our evaluation and presents recommendations for consideration by the Materials Science Coordinators Organization.

  4. ACTINIDE REMOVAL PROCESS SAMPLE ANALYSIS, CHEMICAL MODELING, AND FILTRATION EVALUATION

    SciTech Connect (OSTI)

    Martino, C.; Herman, D.; Pike, J.; Peters, T.

    2014-06-05T23:59:59.000Z

    Filtration within the Actinide Removal Process (ARP) currently limits the throughput in interim salt processing at the Savannah River Site. In this process, batches of salt solution with Monosodium Titanate (MST) sorbent are concentrated by crossflow filtration. The filtrate is subsequently processed to remove cesium in the Modular Caustic Side Solvent Extraction Unit (MCU) followed by disposal in saltstone grout. The concentrated MST slurry is washed and sent to the Defense Waste Processing Facility (DWPF) for vitrification. During recent ARP processing, there has been a degradation of filter performance manifested as the inability to maintain high filtrate flux throughout a multi-batch cycle. The objectives of this effort were to characterize the feed streams, to determine if solids (in addition to MST) are precipitating and causing the degraded performance of the filters, and to assess the particle size and rheological data to address potential filtration impacts. Equilibrium modelling with OLI Analyzer{sup TM} and OLI ESP{sup TM} was performed to determine chemical components at risk of precipitation and to simulate the ARP process. The performance of ARP filtration was evaluated to review potential causes of the observed filter behavior. Task activities for this study included extensive physical and chemical analysis of samples from the Late Wash Pump Tank (LWPT) and the Late Wash Hold Tank (LWHT) within ARP as well as samples of the tank farm feed from Tank 49H. The samples from the LWPT and LWHT were obtained from several stages of processing of Salt Batch 6D, Cycle 6, Batch 16.

  5. Evaluation Consultant RFP

    Broader source: Energy.gov [DOE]

    Evaluation Consultant RFP, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  6. Bottleneckology: evaluating supercomputers

    SciTech Connect (OSTI)

    Worlton, J.

    1985-01-01T23:59:59.000Z

    Evaluating supercomputer performance is more difficult than evaluating performance for other types of computers because of the wide range of performances encountered. Depending on the purpose of the evaluation, methods of evaluation can be used that trade off level of effort and accuracy, including rules of thumb, analytical models, testing, and simulation.

  7. Who's Evaluating What? Planned Program Evaluations | Department...

    Energy Savers [EERE]

    Neighborhood Program Final Report Appendices: Preliminary Process and Market Evaluation: Better Buildings Neighborhood Program Getting Useful Real-Time Feedback About Your Program...

  8. Evaluation and enhancement of Texas ramp metering strategies, compliance, and alternative enforcement techniques: Go with the flow Houston. Public outreach plan (revised); Interim research report, September 1995--October 1996

    SciTech Connect (OSTI)

    Lancaster, S.; Fette, B.; Busler, L.; Miller, K.; Messer, C.

    1997-12-01T23:59:59.000Z

    This report describes the public outreach plan on the implementation of ramp meters along the Katy Freeway in Houston, Generally, ramp metering is neither beloved nor understood by the public. To gain public awareness, acceptance, compliance and continued support, ramp metering operations should be reinforced by a strong, ongoing public information and outreach campaign that communicates the need for and benefits of the program. Because the term `ramp metering` exhibits restrictions on the public, the phrase `Flow Signals` was developed to better describe the benefits of ramp metering; enhanced flow of traffic, fewer bottlenecks, and fewer trip delays. The logo, `Go with the Flow Houston,` and a graphic identity were developed to help communicate the theme throughout the various media where both the primary and secondary messages are intended to reach 15 different audiences. These media will include: a PSA, both static and changeable message signs, a brochure, Internet web site information, letters to specific audience and media relations efforts.

  9. Interim Response Action for the Ash Pond Isolation System. Letter transmits the revised Engineering Evaluation / Cost Analysis (EE/CA) for the construction of the Ash Pond Isolation System.

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling CorpNewCF INDUSTRIES,L? .-I I ,Is II:c*1r'* aIn

  10. Plans, Implementation, and Results

    Broader source: Energy.gov [DOE]

    The Bioenergy Technologies Office carries out technology research, development, and deployment through an ongoing process of planning and analysis, implementation, and review. This Web page includes links to documents that support and document the program management process, and the results and public benefits that derive from it.

  11. Recent results from MAC

    SciTech Connect (OSTI)

    MAC Collaboration

    1982-05-01T23:59:59.000Z

    Some preliminary results from the MAC detector at PEP are presented. These include measurements of the angular distribution of ..gamma gamma.., ..mu mu.. and tau tau final states, a determination of the tau lifetime, a measurement of R, and a presentation of the inclusive muon p/sub perpendicular/ distribution for hadronic events.

  12. Initial evaluation of dry storage issues for spent nuclear fuels in wet storage at the Idaho Chemical Processing Plant

    SciTech Connect (OSTI)

    Guenther, R.J.; Johnson, A.B. Jr.; Lund, A.L.; Gilbert, E.R. [and others

    1996-07-01T23:59:59.000Z

    The Pacific Northwest Laboratory has evaluated the basis for moving selected spent nuclear fuels in the CPP-603 and CPP-666 storage pools at the Idaho Chemical Processing Plant from wet to dry interim storage. This work is being conducted for the Lockheed Idaho Technologies Company as part of the effort to determine appropriate conditioning and dry storage requirements for these fuels. These spent fuels are from 22 test reactors and include elements clad with aluminum or stainless steel and a wide variety of fuel materials: UAl{sub x}, UAl{sub x}-Al and U{sub 3}O{sub 8}-Al cermets, U-5% fissium, UMo, UZrH{sub x}, UErZrH, UO{sub 2}-stainless steel cermet, and U{sub 3}O{sub 8}-stainless steel cermet. The study also included declad uranium-zirconium hydride spent fuel stored in the CPP-603 storage pools. The current condition and potential failure mechanisms for these spent fuels were evaluated to determine the impact on conditioning and dry storage requirements. Initial recommendations for conditioning and dry storage requirements are made based on the potential degradation mechanisms and their impacts on moving the spent fuel from wet to dry storage. Areas needing further evaluation are identified.

  13. Advanced Vehicle Testing and Evaluation

    SciTech Connect (OSTI)

    Garetson, Thomas

    2013-03-31T23:59:59.000Z

    The objective of the United States (U.S.) Department of Energy?s (DOEs) Advanced Vehicle Testing and Evaluation (AVTE) project was to provide test and evaluation services for advanced technology vehicles, to establish a performance baseline, to determine vehicle reliability, and to evaluate vehicle operating costs in fleet operations. Vehicles tested include light and medium-duty vehicles in conventional, hybrid, and all-electric configurations using conventional and alternative fuels, including hydrogen in internal combustion engines. Vehicles were tested on closed tracks and chassis dynamometers, as well as operated on public roads, in fleet operations, and over prescribed routes. All testing was controlled by procedures developed specifically to support such testing. Testing and evaluations were conducted in the following phases: ? Development of test procedures, which established testing procedures; ? Baseline performance testing, which established a performance baseline; ? Accelerated reliability testing, which determined vehicle reliability; ? Fleet testing, used to evaluate vehicle economics in fleet operation, and ? End of test performance evaluation. Test results are reported by two means and posted by Idaho National Laboratory (INL) to their website: quarterly progress reports, used to document work in progress; and final test reports. This final report documents work conducted for the entirety of the contract by the Clarity Group, Inc., doing business as ECOtality North America (ECOtality). The contract was performed from 1 October 2005 through 31 March 2013. There were 113 light-duty on-road (95), off-road (3) and low speed (15) vehicles tested.

  14. Results of the independent radiological verification survey of the lower Sheffield Brook floodplain, Wayne, New Jersey

    SciTech Connect (OSTI)

    Yalcintas, M.G.; Carrier, R.F.

    1989-05-01T23:59:59.000Z

    Prior to 1971, the W.R. Grace Company processed and stored radioactive materials at Wayne, New Jersey, under license to the Atomic Energy Commission. Decontamination of structures and storage of waste materials on the property at the Wayne Interim Storage Site (WISS) took place in 1974. Surveys by the State of New Jersey Department of Environmental Protection and by Oak Ridge Associated Universities for the NRC in 1982 indicated that properties adjacent to the WISS contained surface contamination by radioactive residuals in amounts exceeding those acceptable under US Department of Energy (DOE) remedial action guidelines. At the request of DOE, remedial actions have been conducted by Bechtel National, Inc., to remove radioactive residuals from properties adjacent to the site. It is the policy of DOE to assign an independent verification contractor to ensure the effectiveness of remedial actions performed within the Formerly Utilized Sites Remedial Action Program. This report describes the methods and results of those studies that were conducted by the Measurement Applications and Development Group of the Oak Ridge National Laboratory for the lower Sheffield Brook floodplain west of the WISS. Based upon post-remedial action and verification survey data, it was concluded that residual soil concentrations and gamma levels following excavation and backfilling of the area are within the limits prescribed by DOE radiological guidelines. 12 refs., 6 figs., 8 tabs.

  15. Results of RCRA groundwater quality assessment program at the 216-U-12 crib

    SciTech Connect (OSTI)

    Williams, B.A.; Chou, C.J.

    1997-05-01T23:59:59.000Z

    The 216-U-12 crib has been in a Resource Conservation and Recovery Act of 1976 (RCRA) interim-status groundwater quality assessment program since the first quarter of 1993. Specific conductance measured in downgradient wells 299-W22-41 and 299-W22-42 exceeds its critical mean. This report presents the results and findings of Phases I and II of the assessment monitoring program, as required by 40 CFR 265.93. The elevated levels of specific conductance in the downgradient {open_quotes}triggering{close_quotes} wells are attributed to nitrate, the mobile anion released when nitric acid is diluted in water, and calcium which is released from the sediments as acid is neutralized. Technetium-99 levels have been elevated in these same downgradient wells since 1991. The source of these constituents is the 216-U-12 crib. Downward migration of nitrate and technetium-99 from the vadose zone (and continued elevated specific conductance in the two downgradient wells) is still occurring because the driving force is still present.

  16. Evaluation report 2006 Evaluation of Research on

    E-Print Network [OSTI]

    , 2001 and 2004. The quality of Swedish research within organic farming has not been properly evaluated. The evaluation comprised projects that had funding during 1997­2004. In total, nearly one hundred projects, with one expert panel each. The first panel analysed the scientific quality and the second panel

  17. Research, Monitoring and Evaluation Lower Snake River tributaries Prepared by: Washington Department of Fish and Wildlife

    E-Print Network [OSTI]

    is inadequate. This plan will therefore, serve as an interim set of guidelines that will assure a systematic of known quality (accuracy and precision) #12;- Validate EDT model as a reliable measure of habitat

  18. Results Of Routine Strip Effluent Hold Tank, Decontaminated Salt Solution Hold Tank, Caustic Wash Tank And Caustic Storage Tank Samples From Modular Caustic-Side Solvent Extraction Unit During Macrobatch 6 Operations

    SciTech Connect (OSTI)

    Peters, T. B.

    2014-01-02T23:59:59.000Z

    Strip Effluent Hold Tank (SEHT), Decontaminated Salt Solution Hold Tank (DSSHT), Caustic Wash Tank (CWT) and Caustic Storage Tank (CST) samples from the Interim Salt Disposition Project (ISDP) Salt Batch (“Macrobatch”) 6 have been analyzed for 238Pu, 90Sr, 137Cs, and by Inductively Coupled Plasma Emission Spectroscopy (ICPES). The Pu, Sr, and Cs results from the current Macrobatch 6 samples are similar to those from comparable samples in previous Macrobatch 5. In addition the SEHT and DSSHT heel samples (i.e. ‘preliminary’) have been analyzed and reported to meet NGS Demonstration Plan requirements. From a bulk chemical point of view, the ICPES results do not vary considerably between this and the previous samples. The titanium results in the DSSHT samples continue to indicate the presence of Ti, when the feed material does not have detectable levels. This most likely indicates that leaching of Ti from MST has increased in ARP at the higher free hydroxide concentrations in the current feed.

  19. RESULTS OF SLICE MEASUREMENTS

    E-Print Network [OSTI]

    Rudolph, J

    2011-01-01T23:59:59.000Z

    The linear accelerator ELBE delivers high-brightness electron bunches to multiple user stations, including two IR-FEL oscillators [1], [2]. In the framework of an upgrade program the current thermionic injector is being replaced by a SRF-photoinjector [3], [4]. The SRF injector promises higher beam quality, especially required for future experiments with high power laser radiation. During the commissioning phase, the SRF-injector was running in parallel to the thermionic gun. After installation of a injection beamline (dogleg), beam from the SRF-injector can now be injected into the ELBE linac. Detailed characterization of the electron beam quality delivered by the new electron injector includes vertical slice emittance measurements in addition to measurements of projected emittance values. This report gives an overview of the status of the project and summarizes first measurement results as well as results of simulations performed with measurement settings.

  20. Evaluated teletherapy source library

    DOE Patents [OSTI]

    Cox, Lawrence J. (Los Alamos, NM); Schach Von Wittenau, Alexis E. (Livermore, CA)

    2000-01-01T23:59:59.000Z

    The Evaluated Teletherapy Source Library (ETSL) is a system of hardware and software that provides for maintenance of a library of useful phase space descriptions (PSDs) of teletherapy sources used in radiation therapy for cancer treatment. The PSDs are designed to be used by PEREGRINE, the all-particle Monte Carlo dose calculation system. ETSL also stores other relevant information such as monitor unit factors (MUFs) for use with the PSDs, results of PEREGRINE calculations using the PSDs, clinical calibration measurements, and geometry descriptions sufficient for calculational purposes. Not all of this information is directly needed by PEREGRINE. It also is capable of acting as a repository for the Monte Carlo simulation history files from which the generic PSDs are derived.

  1. Tevatron Top Results

    E-Print Network [OSTI]

    Christophe Clement

    2006-05-28T23:59:59.000Z

    I present the latest results from the CDF and D0 collaborations on top quark production (single top and top quark pair production) at the Tevatron proton-antiproton collider at sqrt(s) =1.96 TeV, measurements of the top quark decay properties such as the branching ratio B(t -> Wb), the W helicity in t -> Wb decays, and measurements of fundamental parameters such as the top quark charge and mass.

  2. Double Chooz: Latest results

    E-Print Network [OSTI]

    J. I. Crespo-Anadón; for the Double Chooz collaboration

    2014-12-11T23:59:59.000Z

    The latest results from the Double Chooz experiment on the neutrino mixing angle $\\theta_{13}$ are presented. A detector located at an average distance of 1050 m from the two reactor cores of the Chooz nuclear power plant has accumulated a live time of 467.90 days, corresponding to an exposure of 66.5 GW-ton-year (reactor power $\\times$ detector mass $\\times$ live time). A revised analysis has boosted the signal efficiency and reduced the backgrounds and systematic uncertainties compared to previous publications, paving the way for the two detector phase. The measured $\\sin^2 2\\theta_{13} = 0.090^{+0.032}_{-0.029}$ is extracted from a fit to the energy spectrum. A deviation from the prediction above a visible energy of 4 MeV is found, being consistent with an unaccounted reactor flux effect, which does not affect the $\\theta_{13}$ result. A consistent value of $\\theta_{13}$ is measured in a rate-only fit to the number of observed candidates as a function of the reactor power, confirming the robustness of the result.

  3. International decay data evaluation project

    SciTech Connect (OSTI)

    Helmer, R.G.

    1996-10-01T23:59:59.000Z

    Basic concepts of, and information from, radionuclide decay are used in many applications. The author limits this discussion to the data needed for applied {gamma}-ray spectrometry; this includes applications such as nuclide identification and quantitative assay. Many of these applications require a knowledge of half-lives and radiation energies and emission probabilities. For over 50 years, people have compiled and evaluated measured data with the goal of obtaining the best values of these quantities. This has resulted in numerous sets of recommended values, many of which still have scientific, historical, or national reasons for existing. These sets show varying degrees of agreement and disagreement in the quoted values and varying time lags in incorporating new and improved experimental results. A new informational international group has been formed to carry out evaluations for radionuclides of importance in applications; it is expected that the results will become an authoritative and widely accepted set of decay data.

  4. Recent Results from HAPPEX

    SciTech Connect (OSTI)

    Robert Michaels

    2006-09-18T23:59:59.000Z

    New measurements of the parity-violating asymmetry in elastic scattering of 3GeV electrons off hydrogen and helium-4 targets at theta{sub lab} = 6 degrees are reported. The helium-4 result is A = (+6.40 {+-} 0.23 (stat) {+-} 0.12 (syst)) * 10{sup -6}. The hydrogen result is A = (-1.58 {+-} 0.12 (stat) {+-} 0.04 (syst)) * 10{sup -6}. The asymmetry for hydrogen is a function of a linear combination of G{sub E}{sup s} and G{sub M}{sup s}, the strange quark contributions to the electric and magnetic form factors of the nucleon respectively, and that for helium-4 is a function solely of G{sub E}{sup s}. The combination of the two measurements separates G{sub E}{sup s} and G{sub M}{sup s} and provide new limits on the role of strange quarks in the nucleon charge and magnetization distributions. We extract G{sub E}{sup s} = 0.002 {+-} 0.014 {+-} 0.007 at Q{sup 2} = 0.077 GeV{sup 2} and G{sub E}{sup s} + 0.09 G{sub M}{sup s} = 0.007 {+-} 0.011 {+-} 0.006 at Q{sup 2} = 0.109 GeV{sup 2}.

  5. DREDGED MATERIAL EVALUATION AND

    E-Print Network [OSTI]

    DREDGED MATERIAL EVALUATION AND DISPOSAL PROCEDURES (USERS' MANUAL) Dredged Material Management 2009) Prepared by: Dredged Material Management Office US Army Corps of Engineers Seattle District #12........................................................................................2-1 2.2 The Dredged Material Evaluation Process

  6. Evaluation of Physics Research

    E-Print Network [OSTI]

    Franssen, Michael

    1 Evaluation of Physics Research Eindhoven University of Technology 1996-2003 April 2006 #12;2 3........................................................................................................................................................... 11 Individual Programme Evaluation Eindhoven University of Technology (RU) in September 2004 ­ and Technische Universiteit Eindhoven (TUE) decided to have their physics

  7. Windows Server Evaluation Guide

    E-Print Network [OSTI]

    Hunt, Galen

    Windows Server 2012 R2 Evaluation Guide #12;Copyright Information © 2013 Microsoft Corporation. All .......................................................................................................................1 Introduction to Windows Server 2012 R2 ..................................................................................................7 Windows Server: Architecture of the Evaluation Environment

  8. The Partnership Evaluation Framework

    Broader source: Energy.gov [DOE]

    U.S. Department of Energy Better Buildings Neighborhood Program: The Partnership Evaluation Framework: How to evaluate a potential partner’s business model and identify areas for collaboration.

  9. Evaluation of commercially available exterior digital VMDs

    SciTech Connect (OSTI)

    Ringler, C.E.; Hoover, C.E.

    1995-06-01T23:59:59.000Z

    This report discusses the testing and evaluation of thirteen commercially available exterior digital video motion detection (VMD) systems. The systems were evaluated for use in a specific outdoor application. The report focuses primarily on the testing parameters, each system`s advertised features, and the nuisance alarm and detection test results.

  10. AQUIFER STORAGE SITE EVALUATION AND MONITORING

    E-Print Network [OSTI]

    Edwards, Mike

    CO2 AQUIFER STORAGE SITE EVALUATION AND MONITORING Edited and compiled by Martin Smith, David Campbell, Eric Mackay and Debbie Polson Understanding the challenges of CO2 storage: results of the CASSEM Project Im agecopyrightofNERC #12;#12;CO2 Aquifer storage site evaluation and monitoring EDITED

  11. Evaluation of ATP's Intramural Research Awards Program

    E-Print Network [OSTI]

    an assessment of the performance of the intramural program and a template for ongoing evaluation of performance. To accomplish the evaluation, the report uses survey, benchmarking, and case study approaches. In a survey been undertaken if ATP funding had not occurred. Survey results, adjusted for response bias, found

  12. Results from NEMO 3

    E-Print Network [OSTI]

    R. L. Flack; for the NEMO 3 collaboration

    2008-10-30T23:59:59.000Z

    The NEMO 3 experiment is located in the Modane Underground Laboratory and has been taking data since 2003 with seven isotopes. It is searching for the double beta decay process with two or zero neutrinos emitted in the final state. Precision measurements of the half-life of the isotopes due to two neutrino double beta decay have been performed and new results for 96Zr, 48Ca and 150Nd are presented here. Measurements of this process are important for reducing the uncertainties on the nuclear matrix elements. No evidence for zero neutrino double beta decay has been found and a 90% Confidence Level lower limit on the half-life of this process is derived. From this an upper limit can be set on the effective Majorana neutrino mass using the most recent nuclear matrix elements calculations.

  13. MELCOR validation results

    SciTech Connect (OSTI)

    Leigh, C.D.; Byers, R.K.; Shaffer, C.J.

    1986-01-01T23:59:59.000Z

    Recent comparisons of MELCOR predictions to three sets of experiments, the ABCOVE Aerosol Experiments, the HDR-V44 Steam Blowdown Experiments, and the Battelle-Frankfurt Gas Mixing Experiments are presentd. All three comparisons involve conditions that are of concern in an LWR containment during a severe accident. MELCOR results are compared to the experimental data and the predictions of at least one other state-of-the-art code for each test. In the ABCOVE comparisons, the MELCOR aerosol modeling is demonstrated. In comparisons to the HDR-V44 Steam Blowdown Experiments, MELCOR predictions of the response of the containment to the release of steam from the primary system are shown, and in the Battelle-Frankfurt comparisons, MELCOR predictions of the diffusion in a containment of an injected hydrogen-nitrogen gas are studied. These comparisons provide critical testing of the MELCOR control volume hydrodynamics package, the radionuclide package, and the flow path package.

  14. Results from NA49

    E-Print Network [OSTI]

    C. Hoehne

    2005-10-17T23:59:59.000Z

    An overview of results from the CERN experiment NA49 is presented with emphasis on most recent measurements. NA49 has systematically studied the dependence of hadron production on energy and system size or centrality. At top-SPS energy the detailed investigation of hadron production, now also extending to elliptic flow of Lambda-baryons and to identified particle yields at high p_t, shows that the created matter behaves in a similar manner as at RHIC energies. In the lower SPS energy range a distinct structure is observed in the energy dependence of the rate of strangeness production and in the slopes of p_t-spectra suggesting the onset of the creation of a deconfined phase of matter.

  15. AN EVALUATION OF HANFORD SITE TANK FARM SUBSURFACE CONTAMINATION FY2007

    SciTech Connect (OSTI)

    MANN, F.M.

    2007-07-10T23:59:59.000Z

    The Tank Farm Vadose Zone (TFVZ) Project conducts activities to characterize and analyze the long-term environmental and human health impacts from tank waste releases to the vadose zone. The project also implements interim measures to mitigate impacts, and plans the remediation of waste releases from tank farms and associated facilities. The scope of this document is to report data needs that are important to estimating long-term human health and environmental risks. The scope does not include technologies needed to remediate contaminated soils and facilities, technologies needed to close tank farms, or management and regulatory decisions that will impact remediation and closure. This document is an update of ''A Summary and Evaluation of Hanford Site Tank Farm Subsurface Contamination''. That 1998 document summarized knowledge of subsurface contamination beneath the tank farms at the time. It included a preliminary conceptual model for migration of tank wastes through the vadose zone and an assessment of data and analysis gaps needed to update the conceptual model. This document provides a status of the data and analysis gaps previously defined and discussion of the gaps and needs that currently exist to support the stated mission of the TFVZ Project. The first data-gaps document provided the basis for TFVZ Project activities over the previous eight years. Fourteen of the nineteen knowledge gaps identified in the previous document have been investigated to the point that the project defines the current status as acceptable. In the process of filling these gaps, significant accomplishments were made in field work and characterization, laboratory investigations, modeling, and implementation of interim measures. The current data gaps are organized in groups that reflect Components of the tank farm vadose zone conceptual model: inventory, release, recharge, geohydrology, geochemistry, and modeling. The inventory and release components address residual wastes that will remain in the tanks and tank-farm infrastructure after closure and potential losses from leaks during waste retrieval. Recharge addresses the impacts of current conditions in the tank farms (i.e. gravel covers that affect infiltration and recharge) as well as the impacts of surface barriers. The geohydrology and geochemistry components address the extent of the existing subsurface contaminant inventory and drivers and pathways for contaminants to be transported through the vadose zone and groundwater. Geochemistry addresses the mobility of key reactive contaminants such as uranium. Modeling addresses conceptual models and how they are simulated in computers. The data gaps will be used to provide input to planning (including the upcoming C Farm Data Quality Objective meetings scheduled this year).

  16. Economic Evaluation of Radiopharmaceutical

    E-Print Network [OSTI]

    97-2 Planning Report Economic Evaluation of Radiopharmaceutical Research at NIST U.S Department Radiation Division Physics Laboratory National Institute of Standards and Technology #12;Economic Evaluation in this report. #12;Economic Evaluation of Radiopharmaceutical Research at NIST I. Introduction Nuclear medicine

  17. Search results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    usage is counted and priced. They measure and evaluate energy use and cost of representative household and school electrical items. http:energy.goveereeducationdownloads...

  18. Search results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    information on transportation fuels to help your students learn about conventional and alternative transportation fuels by evaluating their advantages and disadvantages. http:...

  19. Composite Load Model Evaluation

    SciTech Connect (OSTI)

    Lu, Ning; Qiao, Hong (Amy)

    2007-09-30T23:59:59.000Z

    The WECC load modeling task force has dedicated its effort in the past few years to develop a composite load model that can represent behaviors of different end-user components. The modeling structure of the composite load model is recommended by the WECC load modeling task force. GE Energy has implemented this composite load model with a new function CMPLDW in its power system simulation software package, PSLF. For the last several years, Bonneville Power Administration (BPA) has taken the lead and collaborated with GE Energy to develop the new composite load model. Pacific Northwest National Laboratory (PNNL) and BPA joint force and conducted the evaluation of the CMPLDW and test its parameter settings to make sure that: • the model initializes properly, • all the parameter settings are functioning, and • the simulation results are as expected. The PNNL effort focused on testing the CMPLDW in a 4-bus system. An exhaustive testing on each parameter setting has been performed to guarantee each setting works. This report is a summary of the PNNL testing results and conclusions.

  20. Residential-energy-demand modeling and the NIECS data base: an evaluation

    SciTech Connect (OSTI)

    Cowing, T.G.; Dubin, J.A.; McFadden, D.

    1982-01-01T23:59:59.000Z

    The purpose of this report is to evaluate the 1978-1979 National Interim Energy Consumption Survey (NIECS) data base in terms of its usefulness for estimating residential energy demand models based on household appliance choice and utilization decisions. The NIECS contains detailed energy usage information at the household level for 4081 households during the April 1978 to March 1979 period. Among the data included are information on the structural and thermal characteristics of the housing unit, demographic characteristics of the household, fuel usage, appliance characteristics, and actual energy consumption. The survey covers the four primary residential fuels-electricity, natural gas, fuel oil, and liquefied petroleum gas - and includes detailed information on recent household conservation and retrofit activities. Section II contains brief descriptions of the major components of the NIECS data set. Discussions are included on the sample frame and the imputation procedures used in NIECS. There are also two extensive tables, giving detailed statistical and other information on most of the non-vehicle NIECS variables. Section III contains an assessment of the NIECS data, focusing on four areas: measurement error, sample design, imputation problems, and additional data needed to estimate appliance choice/use models. Section IV summarizes and concludes the report.

  1. Energy Efficiency Program Impact Evaluation Guide

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Energy Efficiency Program Impact Evaluation Guide describes and provides guidance on approaches for determining and documenting energy and non-energy benefits resulting from end-use energy efficiency programs and portfolios of programs.

  2. LSND neutrino oscillation results

    SciTech Connect (OSTI)

    Louis, W.C.; LSND Collaboration

    1996-10-01T23:59:59.000Z

    The LSND (Liquid Scintillator Neutrino Detector) experiment at Los Alamos has conducted a search for muon antineutrino {r_arrow} electron antineutrino oscillations using muon neutrinos from antimuon decay at rest. The electron antineutrinos are detected via the reaction electron antineutrino + proton {r_arrow} positron + neutron, correlated with the 2.2-MeV gamma from neutron + proton {r_arrow} deuteron + gamma. The use of tight cuts to identify positron events with correlated gamma rays yields 22 events with positron energy between 36 and 60 MeV and only 4.6 {+-} 0.6 background events. The probability that this excess is due entirely to a statistical fluctuation is 4.1 {times} 10{sup -8}. A chi-squared fit to the entire positron sample results in a total excess of 51.8 {sup +18.7}{sub -16.9} {+-} 8.0 events with positron energy between 20 and 60 MeV. If attributed to muon antineutrino {r_arrow} electron antineutrino oscillations, this corresponds to an oscillation probability (averaged over the experimental energy and spatial acceptance) of (0.31 {+-} 0.12 {+-} 0.05){percent}. 10 refs., 7 figs., 1 tab.

  3. LSND neutrino oscillation results

    SciTech Connect (OSTI)

    White, D.H.; LSND Collaboration

    1997-11-01T23:59:59.000Z

    The LSND experiment at Los Alamos has conducted a search for {anti v}{sub {mu}} {yields} {anti v}{sub e} oscillations using {anti v}{sub {mu}} from {mu}{sup +} decay at rest. The {anti v}{sub e} are detected via the reaction {anti v}{sub e} p {yields} e{sup +}n, correlated with the 2.2 MeV {gamma} from n p {yields} d {gamma}. The use of tight cuts to identify e{sup +} events with correlated {gamma} rays yielded 22 events with e{sup +} energy between 36 and 60 MeV and only 4.6 {+-} 0.6 background events. The probability that this excess is due entirely to a statistical fluctuation is 4.1 {times} 10{sup {minus}8}. A {chi}{sup 2} fit to the entire e{sup +} sample results in a total excess of 51.8{sub {minus}16.9}{sup +18.7} {+-} 8.0 events with e{sup +} energy between 20 and 60 MeV. If attributed to {anti v}{sub {mu}} {yields} {anti v}{sub e} oscillations, this corresponds to an oscillation probability (averaged over the experimental energy and spatial acceptance) of 0.31 {+-} 0.12 {+-} 0.05%.

  4. Methodology for flammable gas evaluations

    SciTech Connect (OSTI)

    Hopkins, J.D., Westinghouse Hanford

    1996-06-12T23:59:59.000Z

    There are 177 radioactive waste storage tanks at the Hanford Site. The waste generates flammable gases. The waste releases gas continuously, but in some tanks the waste has shown a tendency to trap these flammable gases. When enough gas is trapped in a tank`s waste matrix, it may be released in a way that renders part or all of the tank atmosphere flammable for a period of time. Tanks must be evaluated against previously defined criteria to determine whether they can present a flammable gas hazard. This document presents the methodology for evaluating tanks in two areas of concern in the tank headspace:steady-state flammable-gas concentration resulting from continuous release, and concentration resulting from an episodic gas release.

  5. An Operator Perspective from a Facility Evaluation of an RFID-Based UF6 Cylinder Accounting and Tracking System

    SciTech Connect (OSTI)

    Martyn, Rose [Global Nuclear Fuels; Fitzgerald, Peter [Global Nuclear Fuels; Stehle, Nicholas D [ORNL; Rowe, Nathan C [ORNL; Younkin, James R [ORNL

    2011-01-01T23:59:59.000Z

    An operational field test of a Radio-Frequency Identification (RFID) system for tracking and accounting UF6 cylinders was conducted at the Global Nuclear Fuel Americas (GNF) fuel fabrication plant in 2009. The Cylinder Accountability and Tracking System (CATS) was designed and deployed by Oak Ridge National Laboratory (ORNL) and evaluated in cooperation with GNF. The system required that passive RFID be attached to several UF6 30B cylinders as they were received at the site; then the cylinders were tracked as they proceeded to interim storage, to processing in an autoclave, and eventually to disposition from the site. This CATS deployment also provided a direct integration of scale data from the site accountability scales. The integration of this information into the tracking data provided an attribute for additional safeguards for evaluation. The field test provided insight into the advantages and challenges of using RFID at an operating nuclear facility. The RFID system allowed operators to interact with the technology and demonstrated the survivability of the tags and reader equipment in the process environment. This paper will provide the operator perspective on utilizing RFID technology for locating cylinders within the facility, thereby tracking the cylinders for process and for Material Control & Accounting functions. The paper also will present the operator viewpoint on RFID implemented as an independent safeguards system.

  6. Drying results of K-Basin fuel element 1990 (Run 1)

    SciTech Connect (OSTI)

    Marschman, S.C.; Abrefah, J.; Klinger, G.S.; Oliver, B.M.; MacFarlan, P.J.; Ritter, G.A.

    1998-06-01T23:59:59.000Z

    The water-filled K-Basins in the Hanford 100-Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basins have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuels in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 8.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the first of those tests (Run 1), which was conducted on an N-Reactor inner fuel element (1990) that had been stored underwater in the K-West Basin (see Section 2.0). This fuel element was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The testing was conducted in the Whole Element Furnace Testing System, described in Section 3.0, located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodology are given in Section 4.0, and the experimental results provided in Section 5.0. These results are further discussed in Section 6.0.

  7. Aviation turbine fuels from tar-sands bitumen and heavy oils. Part 3. Laboratory sample production. Interim technical report, 1 July 1983-30 September 1986

    SciTech Connect (OSTI)

    Moore, H.F.; Johnson, C.A.; Benslay, R.M.; Sutton, W.A.

    1987-12-01T23:59:59.000Z

    The purpose of this research and development project is to provide sample quantities of aviation turbine fuel derived from tar sands and heavy oil feedstocks for testing and evaluation in programs sponsored by the Air Force Wright Aeronautical Laboratories (AFWAL). Samples of specification JP-4 Mil-T-5624L, JP-8 Mil-T-83133A, and variable quality JP-4 samples were produced via pilot plant operations. Data generated from Phases I, II, and III, were used to 1) optimize the processing scheme, 2) generate process material and energy balances for a commercial-sized plant, and 3) provide a detailed final flow diagram of the processing scheme. A final economic analysis was performed based on all contract data available.

  8. Results of Laboratory Testing of Advanced Power Strips: Preprint

    SciTech Connect (OSTI)

    Earle, L.; Sparn, B.

    2012-08-01T23:59:59.000Z

    This paper describes the results of a laboratory investigation to evaluate the technical performance of advanced power strip (APS) devices when subjected to a range of home entertainment center and home office usage scenarios.

  9. Corral Monitoring System assessment results

    SciTech Connect (OSTI)

    Filby, E.E.; Haskel, K.J.

    1998-03-01T23:59:59.000Z

    This report describes the results of a functional and operational assessment of the Corral Monitoring Systems (CMS), which was designed to detect and document accountable items entering or leaving a monitored site. Its development was motivated by the possibility that multiple sites in the nuclear weapons states of the former Soviet Union might be opened to such monitoring under the provisions of the Strategic Arms Reduction Treaty. The assessment was performed at three levels. One level evaluated how well the planned approach addressed the target application, and which involved tracking sensitive items moving into and around a site being monitored as part of an international treaty or other agreement. The second level examined the overall design and development approach, while the third focused on individual subsystems within the total package. Unfortunately, the system was delivered as disassembled parts and pieces, with very poor documentation. Thus, the assessment was based on fragmentary operating data coupled with an analysis of what documents were provided with the system. The system design seemed to be a reasonable match to the requirements of the target application; however, important questions about site manning and top level administrative control were left unanswered. Four weaknesses in the overall design and development approach were detected: (1) poor configuration control and management, (2) inadequate adherence to a well defined architectural standard, (3) no apparent provision for improving top level error tolerance, and (4) weaknesses in the object oriented programming approach. The individual subsystems were found to offer few features or capabilities that were new or unique, even at the conceptual level. The CMS might possibly have offered a unique combination of features, but this level of integration was never realized, and it had no unique capabilities that could be readily extracted for use in another system.

  10. Search results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    1 Search results Search results Enter terms Search Showing 1 - 4 of 4 results. Download Green Fuel This activity allows students the opportunity to explore different methods for...

  11. Search results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    1 Search results Search results Enter terms Search Showing 1 - 5 of 5 results. Download Alternative Fuels Used in Transportation (5 Activities) Gasoline is the most commonly...

  12. Search results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    1 Search results Search results Enter terms Search Showing 1 - 6 of 6 results. Download Alternative Fuels Used in Transportation (5 Activities) Gasoline is the most commonly...

  13. Search results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Elementary (K-5) Teachers Search results Search results Enter terms Search Showing 1 - 1 of 1 result. Article Energy Literacy in Action: Nevada Teachers Helping Students Learn...

  14. Search results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Elementary (K-5) Teachers Search results Search results Enter terms Search Showing 1 - 1 of 1 result. Page Advantages and Challenges of Wind Energy Wind energy offers many...

  15. Search results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Elementary (K-5) Teachers Download Search results Search results Enter terms Search Showing 1 - 3 of 3 results. Download Monitoring and Mentoring These activities explore...

  16. Search results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Elementary (K-5) Teachers Search results Search results Enter terms Search Showing 1 - 3 of 3 results. Download Monitoring and Mentoring These activities explore energy use and...

  17. Search results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    K-8 Grade Teachers Search results Search results Enter terms Search Showing 1 - 1 of 1 result. Page How Distributed Wind Works Wind generator http:energy.goveerewind...

  18. Search results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    K-8 Grade Teachers Search results Search results Enter terms Search Showing 1 - 1 of 1 result. Article Energy Literacy in Action: Nevada Teachers Helping Students Learn About...

  19. Search results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Elementary (K-5) Teachers Search results Search results Enter terms Search Showing 1 - 1 of 1 result. Page How Distributed Wind Works Wind generator http:energy.goveerewind...

  20. Search results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Elementary (K-5) Teachers Search results Search results Enter terms Search Showing 1 - 2 of 2 results. Download Energy Management Students will review energy basics and what...