National Library of Energy BETA

Sample records for interim measures work

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

    SciTech Connect (OSTI)

    LaFreniere, L. M.; Environmental Science Division

    2008-11-18

    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.

  2. EA-2005: Chromium Plume Control Interim Measure And Plume-Center...

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

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

  3. Hanford Advisory Board Fiscal Year 2015 Interim Work Plan

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

    5 Interim Work Plan Adopted by consensus September 5, 2014; comments from October committee discussions 1 Proposed additions from October TWC and RAP committee discussions in RED Topic Quarter 1 10/ 2014 - 12/2014 Quarter 2 01/2015- 03/2015 Quarter 3 04/2015 - 06/2015 Quarter 4 07/2015 - 09 2015 Committee Assignment (lead in Bold) Deferred Maintenance Plan Agency Lead: Kyle Rankin, DOE-RL Chief Engineer Action: Policy discussion Potential HAB Action: _____ Context: The status of structures on

  4. Northeast Site Non-Aqueous Phase Liquids Interim Measures Progress Report April through June 2003

    Office of Legacy Management (LM)

    7-TAC GJO-PIN 13.5.1-1 U.S. Department of Energy Work Performed Under DOE Contract No. for the U.S. Department of Energy DE-AC13-02GJ79491 Approved for public release; distribution is unlimited. Pinellas Environmental Restoration Project Northeast Site Non-Aqueous Phase Liquids Interim Measures Progress Report April Through June 2003 July 2003 N0063400 GJO- 2003- 467- TAC GJO-PIN 13.5.1-1 Pinellas Environmental Restoration Project Northeast Site Non-Aqueous Phase Liquids Interim Measures

  5. Microsoft Word - Interim Work Authorization Form rev 2-9.doc

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

    rev. 2/9/05 * Submit original form to M. Montalvo, MS 69, promptly on completion of work. INTERIM Work Authorization Process for Activities by Non-SSRL Workers at SSRL This Work Authorization Process applies to all maintenance, repair, and installation work performed at SSRL by non-SSRL workers. All work must be initiated by a technically qualified SSRL staff person (e.g. accelerator system manager, shop manager, facilities staff member, beam line engineer, etc.) who will serve as the

  6. Northeast Site Non-Aqueous Phase Liquids Interim Measures Progress Report-January through March 2003

    Office of Legacy Management (LM)

    4-TAC GJO-PIN 13.5.1-1 Pinellas Environmental Restoration Project January through March 2003 Northeast Site Non-Aqueous Phase Liquids Interim Measures Progress Report April 2003 Grand Junction Office U.S. Department of Energy Work Performed Under DOE Contract No. for the U.S. Department of Energy DE-AC13-02GJ79491 Approved for public release; distribution is unlimited. N0060900 GJO-2003-434-TAC GJO-PIN 13.5.1-1 Pinellas Environmental Restoration Project Northeast Site Non-Aqueous Phase Liquids

  7. SWSA 6 interim corrective measures environmental monitoring: FY 1990 results

    SciTech Connect (OSTI)

    Ashwood, T.L.; Spalding, B.P.

    1991-07-01

    This report presents the results and conclusions from a multifaceted monitoring effort associated with the high-density polyethylene caps installed in Solid Waste Storage Area (SWSA) 6 at Oak Ridge National Laboratory (ORNL) as an interim corrective measure (ICM). The caps were installed between November 1988 and June 1989 to meet Resource Conservation and Recovery Act (RCRA) requirements for closure of those areas of SWSA 6 that had received RCRA-regulated wastes after November 1980. Three separate activities were undertaken to evaluate the performance of the caps: (1) wells were installed in trenches to be covered by the caps, and water levels in these intratrench wells were monitored periodically; (2) samples were taken of the leachate in the intratrench wells and were analyzed for a broad range of radiological and chemical contaminants; and (3) water levels in wells outside the trenches were monitored periodically. With the exception of the trench leachate sampling, each of these activities spanned the preconstruction, construction, and postconstruction periods. Findings of this study have important implications for the ongoing remedial investigation in SWSA 6 and for the design of other ICMs. 51 figs., 2 tabs.

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

    SciTech Connect (OSTI)

    HAASS, C.C.

    1999-10-14

    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.

  9. Filling the gaps in meteorological continuous data measured at FLUXNET sites with ERA-Interim reanalysis

    SciTech Connect (OSTI)

    Vuichard, N.

    2015-07-13

    In this study, exchanges of carbon, water and energy between the land surface and the atmosphere are monitored by eddy covariance technique at the ecosystem level. Currently, the FLUXNET database contains more than 500 registered sites, and up to 250 of them share data (free fair-use data set). Many modelling groups use the FLUXNET data set for evaluating ecosystem models' performance, but this requires uninterrupted time series for the meteorological variables used as input. Because original in situ data often contain gaps, from very short (few hours) up to relatively long (some months) ones, we develop a new and robust method for filling the gaps in meteorological data measured at site level. Our approach has the benefit of making use of continuous data available globally (ERA-Interim) and a high temporal resolution spanning from 1989 to today. These data are, however, not measured at site level, and for this reason a method to downscale and correct the ERA-Interim data is needed. We apply this method to the level 4 data (L4) from the La Thuile collection, freely available after registration under a fair-use policy. The performance of the developed method varies across sites and is also function of the meteorological variable. On average over all sites, applying the bias correction method to the ERA-Interim data reduced the mismatch with the in situ data by 10 to 36 %, depending on the meteorological variable considered. In comparison to the internal variability of the in situ data, the root mean square error (RMSE) between the in situ data and the unbiased ERA-I (ERA-Interim) data remains relatively large (on average over all sites, from 27 to 76 % of the standard deviation of in situ data, depending on the meteorological variable considered). The performance of the method remains poor for the wind speed field, in particular regarding its capacity to conserve a standard deviation similar to the one measured at FLUXNET stations.

  10. Comment Period Extended: EA-2005: Chromium Plume Control Interim Measure and Plume-Center Characterization, Los Alamos National Laboratory, Los Alamos, NM

    Broader source: Energy.gov [DOE]

    The Office of Environmental Management has extended the Public Comment Period on the Draft Environmental Assessment for Chromium Plume Control Interim Measure And Plume-Center Characterization, Los...

  11. Filling the gaps in meteorological continuous data measured at FLUXNET sites with ERA-Interim reanalysis

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Vuichard, N.; Papale, D.

    2015-07-13

    In this study, exchanges of carbon, water and energy between the land surface and the atmosphere are monitored by eddy covariance technique at the ecosystem level. Currently, the FLUXNET database contains more than 500 registered sites, and up to 250 of them share data (free fair-use data set). Many modelling groups use the FLUXNET data set for evaluating ecosystem models' performance, but this requires uninterrupted time series for the meteorological variables used as input. Because original in situ data often contain gaps, from very short (few hours) up to relatively long (some months) ones, we develop a new and robustmore » method for filling the gaps in meteorological data measured at site level. Our approach has the benefit of making use of continuous data available globally (ERA-Interim) and a high temporal resolution spanning from 1989 to today. These data are, however, not measured at site level, and for this reason a method to downscale and correct the ERA-Interim data is needed. We apply this method to the level 4 data (L4) from the La Thuile collection, freely available after registration under a fair-use policy. The performance of the developed method varies across sites and is also function of the meteorological variable. On average over all sites, applying the bias correction method to the ERA-Interim data reduced the mismatch with the in situ data by 10 to 36 %, depending on the meteorological variable considered. In comparison to the internal variability of the in situ data, the root mean square error (RMSE) between the in situ data and the unbiased ERA-I (ERA-Interim) data remains relatively large (on average over all sites, from 27 to 76 % of the standard deviation of in situ data, depending on the meteorological variable considered). The performance of the method remains poor for the wind speed field, in particular regarding its capacity to conserve a standard deviation similar to the one measured at FLUXNET stations.« less

  12. 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

    1996-12-17

    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.

  13. SWSA 6 interim corrective measures environmental monitoring: FY 1990 results. Environmental Restoration Program

    SciTech Connect (OSTI)

    Ashwood, T.L.; Spalding, B.P.

    1991-07-01

    This report presents the results and conclusions from a multifaceted monitoring effort associated with the high-density polyethylene caps installed in Solid Waste Storage Area (SWSA) 6 at Oak Ridge National Laboratory (ORNL) as an interim corrective measure (ICM). The caps were installed between November 1988 and June 1989 to meet Resource Conservation and Recovery Act (RCRA) requirements for closure of those areas of SWSA 6 that had received RCRA-regulated wastes after November 1980. Three separate activities were undertaken to evaluate the performance of the caps: (1) wells were installed in trenches to be covered by the caps, and water levels in these intratrench wells were monitored periodically; (2) samples were taken of the leachate in the intratrench wells and were analyzed for a broad range of radiological and chemical contaminants; and (3) water levels in wells outside the trenches were monitored periodically. With the exception of the trench leachate sampling, each of these activities spanned the preconstruction, construction, and postconstruction periods. Findings of this study have important implications for the ongoing remedial investigation in SWSA 6 and for the design of other ICMs. 51 figs., 2 tabs.

  14. Spent Fuel Test - Climax: technical measurements. Interim report, fiscal year 1982

    SciTech Connect (OSTI)

    Patrick, W.C.; Ballou, L.B.; Butkovich, T.R.; Carlson, R.C.; Durham, W.B.; Hage, G.L.; Majer, E.L.; Montan, D.N.; Nyholm, R.A.; Rector, N.L.

    1983-02-01

    The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on the Nevada Test Site. The test is being conducted for the US Department of Energy (DOE) under the technical direction of the Lawrence Livermore National Laboratory (LLNL). Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized April to May 1980, thus initiating a test with a planned 3- to 5-year fuel storage phase. 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. Three exchanges of spent fuel between the SFT-C and a surface storage facility furthered this demonstration. Technical objectives of the test led to development of a technical measurements program, which is the subject of this and two previous interim reports. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the first 2-1/2 years of the test on more than 900 channels. Data continue to be acquired from the test. Some data are now available for analysis and are presented here. Highlights of activities this year include analysis of fracture data obtained during site characterization, laboratory studies of radiation effects and drilling damage in Climax granite, improved calculations of near-field heat transfer and thermomechanical response, a ventilation effects study, and further development of the data acquisition and management systems.

  15. 2010-05 "Interim Measure for Volatile Organic Constituent Contaminant Source Removal in MAD-L and MDA-G"

    Broader source: Energy.gov [DOE]

    Approved March 31, 2010 The intent of this recommendation is to remove large volumes of liquid waste VOCs from the ground and to prevent these contaminants from moving into the groundwater or to the atmosphere. The NNMCAB recognizes it will take additional time and studies for the NMED and DOE to develop final remedies for these MDAs. Therefore, an Interim Measure will provide immediate treatment and removal of source material to reduce further contamination of the site.

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

    Broader source: Energy.gov [DOE]

    This Environmental Assessment evaluates an interim measure to control chromium plume migration and maintain the 50 parts-per-billion (ppb) and greater chromium contamination level with the Los Alamos National Laboratory (LANL) boundary while long-term corrective action remedies are evaluated and implemented. Concentrations of chromium within the groundwater plume beneath Mortadad Canyon exceed the New Mexico groundwater standard of 50 ppb near the property boundary between LANL and the Pueblo de San Ildefonso and are as high as 1,000 ppb in the plume center.

  17. NREL: Measurements and Characterization - Working with Us

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

    Working with Us The National Renewable Energy Laboratory's (NREL's) Measurement and Characterization (M&C) division tests and analyzes thousands of photovoltaic (PV) material and...

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

    SciTech Connect (OSTI)

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

    1982-04-30

    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.

  19. CMM Interim Check (U)

    SciTech Connect (OSTI)

    Montano, Joshua Daniel

    2015-03-23

    Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length. Unfortunately, several nonconformance reports have been generated to document the discovery of a certified machine found out of tolerance during a calibration closeout. In an effort to reduce risk to product quality two solutions were proposed – shorten the calibration cycle which could be costly, or perform an interim check to monitor the machine’s performance between cycles. The CMM interim check discussed makes use of Renishaw’s Machine Checking Gauge. This off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. Data was gathered, analyzed, and simulated from seven machines in seventeen different configurations to create statistical process control run charts for on-the-floor monitoring.

  20. Interim Columbia and Snake rivers flow improvement measures for salmon: Final Supplemental Environmental Impact Statement (SEIS)

    SciTech Connect (OSTI)

    Not Available

    1993-03-01

    Public comments are sought on this final SEIS, which supplements the 1992 Columbia River Salmon Flow Measures Options Analysis (OA)/Environmental Impact Statement (EIS). The Corps of Engineers, in cooperation with the Bonneville Power Administration and the Bureau of Reclamation proposes five 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. These are: (1) Without Project (no action) Alternative, (2) the 1992 Operation, (3) the 1992 Operation with Libby/Hungry Horse Sensitivity, (4) a Modified 1992 Operation with Improvements to Salmon Flows from Dworshak, and (5) a Modified 1992 Operation with Upper Snake Sensitivity. Alternative 4, Modified 1992 Operations, has been identified as the preferred alternative.

  1. 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.

  2. Site 300 hazardous-waste-assessment project. Interim report: December 1981. Preliminary site reconnaissance and project work plan

    SciTech Connect (OSTI)

    Raber, E.; Helm, D.; Carpenter, D.; Peifer, D.; Sweeney, J.

    1982-01-20

    This document was prepared to outline the scope and objectives of the Hazardous Waste Assessment Project (HWAP) at Site 300. This project was initiated in October, 1981, to investigate the existing solid waste landfills in an effort to satisfy regulatory guidelines and assess the potential for ground-water contamination. This involves a site-specific investigation (utilizing geology, hydrology, geophysics and geochemistry) with the goal of developing an effective ground-water quality monitoring network. Initial site reconnaissance work has begun and we report the results, to date, of our geologic hydrogeologic studies. All known solid waste disposal locations are underlain by rocks of either the Late Miocene Neroly Formation or the Cierbo Formation, both of which are dominantly sandstones interbedded with shale and claystone. The existence of a regional confined (artesian) aquifer, as well as a regional water-table aquifer is postulated for Site 300. Preliminary analysis has led to an understanding of directions and depths of regional ground-water flow.

  3. WIPP Interim Ventilation System Continues to Progress

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

    22, 2015 WIPP Interim Ventilation System Continues to Progress Work on the Interim Ventilation System (IVS) being installed at the Waste Isolation Pilot Plant (WIPP) continues to move forward. Concrete pads were poured and both the power distribution center and the two-fan/filter units have now been installed in their final positions. The IVS units consist of fans that draw air out of the underground and High Efficiency Particulate Air (HEPA) filter units that filter the air before it exhausts

  4. Microsoft Word - EM-TWS Interim Report 02-21-11 final

    Office of Environmental Management (EM)

    INTERIM REPORT TO THE ENVIRONMENTAL MANAGEMENT ADVISORY BOARD Environmental Management Tank Waste Subcommittee (EM-TWS) FY 2011 Work Plan Status Modeling for Life Cycle Cost Analysis (Interim Report) February 24, 2011 Hanford Tank Farms and WTP SRS Tank Farms Presented by the EM Tank Waste Subcommittee Las Vegas, Nevada EM-TWS Interim Report, February 2011 1 Business Sensitive INTERIM REPORT TO THE ENVIRONMENTAL MANAGEMENT ADVISORY BOARD Environmental Management Tank Waste Subcommittee (EM-TWS)

  5. CMM Interim Check Design of Experiments (U)

    SciTech Connect (OSTI)

    Montano, Joshua Daniel

    2015-07-29

    Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length and include a weekly interim check to reduce risk. The CMM interim check makes use of Renishaw’s Machine Checking Gauge which is an off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. As verification on the interim check process a design of experiments investigation was proposed to test a couple of key factors (location and inspector). The results from the two-factor factorial experiment proved that location influenced results more than the inspector or interaction.

  6. Development of an EMF Measurements Database, EMF Rapid Program, Project #5, Interim Report: April 1995-December 1996

    SciTech Connect (OSTI)

    T. Dan Bracken, Inc.

    1997-04-01

    The EMF measurement data sets in existence today were compiled with varying goals and techniques. Consequently, they have different information content as well as varying logical and physical structure. Future studies will continue to pursue varying goals and utilize techniques that cannot be known in advance. Primary goals for the EMF Measurements Database developed under the Department of Energy EMF RAPID Program are to develop a database structure that can accommodate the diversity of EMF data sets, provide guidance for production of future EMF data sets, and serve as an accessible repository of EMF measurement data. Specific objectives of the EMF Measurements Database are: o to preserve study descriptions, results and data; o to provide readily accessible, well-documented data; and o to facilitate communication among researchers. In addition, the EMF Measurements Database will encourage additional analysis of existing data sets, facilitate analysis of data from multiple projects, support design of new studies, and permit future issues in EMF exposure assessment to be addressed with existing data. Preservation of study descriptions and data is accomplished with a formal, but open, structure. Specifications have been developed for the various elements of the database. Each data set in the database is formally described by a metadata file. The structured metadata file describes the origin, development, logical and physical structure and distribution mechanism for each data set. The metadata for each data set is generated according to a specification developed for the EMF Measurements Database. The actual measurement data is contained in data Products for each data set. The number and type of data product will vary by data set. Most of the data products in the possession of the EMF Measurements Database are available for download from an Internet site. For some data sets, the data products will be maintained by other parties who may have their own access procedures. In addition, data set contributors or users can provide reports that describe results of the study and analysis of the data with text and figures. Guidelines have been developed for preparation of reports. Access to the EMF Measurements Database is provided via an Internet site (http://www.emf-data. erg). The site provides descriptive information in a home page, . . access to data products with a file transfer protocol (ftp) address, and links to other EMF-related sites.

  7. Interim Action Determination

    Energy Savers [EERE]

    Interim Action Determination Processing of Plutonium Materials from the DOE Standard 3013 Surveillance Program in H-Canyon at the Savannah River Site The Department of Energy (DOE) is preparing the Surplus Plutonium Disposition Supplemental Environmental Impact Statement (SPD SEIS, DOE/EIS-0283-S2). DOE is evaluating alternatives for disposition of non-pit plutonium that is surplus to the national security needs of the United States. Although the Deputy Secretary of Energy approved Critical

  8. K basins interim remedial action health and safety plan

    SciTech Connect (OSTI)

    DAY, P.T.

    1999-09-14

    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.

  9. Note: Work function change measurement via improved Anderson method

    SciTech Connect (OSTI)

    Sabik, A. Gołek, F.; Antczak, G.

    2015-05-15

    We propose the modification to the Anderson method of work function change (Δϕ) measurements. In this technique, the kinetic energy of the probing electrons is already low enough for non-destructive investigation of delicate molecular systems. However, in our implementation, all electrodes including filament of the electron gun are polarized positively. As a consequence, electron bombardment of any elements of experimental system is eliminated. Our modification improves cleanliness of the ultra-high vacuum system. As an illustration of the solution capabilities, we present Δϕ of the Ag(100) surface induced by cobalt phthalocyanine layers.

  10. Interim storage study report

    SciTech Connect (OSTI)

    Rawlins, J.K.

    1998-02-01

    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.

  11. Methods Data Qualification Interim Report

    SciTech Connect (OSTI)

    R. Sam Alessi; Tami Grimmett; Leng Vang; Dave McGrath

    2010-09-01

    The overall goal of the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) is to maintain data provenance for all NGNP data including the Methods component of NGNP data. Multiple means are available to access data stored in NDMAS. A web portal environment allows users to access data, view the results of qualification tests and view graphs and charts of various attributes of the data. NDMAS also has methods for the management of the data output from VHTR simulation models and data generated from experiments designed to verify and validate the simulation codes. These simulation models represent the outcome of mathematical representation of VHTR components and systems. The methods data management approaches described herein will handle data that arise from experiment, simulation, and external sources for the main purpose of facilitating parameter estimation and model verification and validation (V&V). A model integration environment entitled ModelCenter is used to automate the storing of data from simulation model runs to the NDMAS repository. This approach does not adversely change the why computational scientists conduct their work. The method is to be used mainly to store the results of model runs that need to be preserved for auditing purposes or for display to the NDMAS web portal. This interim report demonstrates the currently development of NDMAS for Methods data and discusses data and its qualification that is currently part of NDMAS.

  12. ANALYSIS OF DOSE RATES DURING REPLACEMENT OF MANIPULATORS IN THE FFTF INTERIM EXAMINATION & MAINTENANCE (IEM) CELL

    SciTech Connect (OSTI)

    NELSON, J.V.

    2002-01-23

    Replacement of a master-slave manipulator in the Interim Examination and Maintenance Cell at the Fast Flux Test Facility was carried out in August 2001. This operation created a 178-mm opening in the thick concrete wall of the hot cell. To aid in radiological work planning, dose rates outside the penetration in the wall were predicted using MCNP{trademark} photon transport calculations. The predicted dose rate was 7.7 mrem/h, which was reasonably close to the value of 10.4 mrem/h inferred from measurements.

  13. Report of the working group on precision measurements - measurements of the W boson mass and width.

    SciTech Connect (OSTI)

    Brock, R.; Erler, J.; Kim, Y.-K.; Marciano, W.; Ashmanskas, W.; Baur, U.; Ellison, J.; Lancaster, M.; Nodulman, L.; Rha, J.; Waters, D.; Womersley, J.

    2000-11-29

    We discuss the prospects for measuring the W mass and width in Run II. The basic techniques used to measure M{sub W} are described and the statistical, theoretical and detector-related uncertainties are discussed in detail. Alternative methods of measuring the W mass at the Tevatron and the prospects for M{sub W} measurements at other colliders are also described.

  14. Memorandum, Interim Procedures During Temporary Suspension of...

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

    hiring, credentialing and eligibility determinations during the period of e-QIP suspension. Memorandum, Interim Procedures During Temporary Suspension of Electronic...

  15. Interim Guidance Regarding Limitations on CERCLA Liability |...

    Open Energy Info (EERE)

    search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - Inner-Office Memorandum: Interim Guidance Regarding Limitations on CERCLA LiabilityPermitting...

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

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

    Kathleen Carlson Appointed Interim Acting Deputy Administrator for Defense Programs | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission...

  17. Memorandum on the Interim Report of the Commission to Review...

    Office of Environmental Management (EM)

    the Interim Report of the Commission to Review the Effectiveness of the National Energy Laboratories Memorandum on the Interim Report of the Commission to Review the Effectiveness...

  18. VTA Prototype Fuel Cell Bus Evaluation: Interim Results (Presentation...

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

    VTA Prototype Fuel Cell Bus Evaluation: Interim Results (Presentation) VTA Prototype Fuel Cell Bus Evaluation: Interim Results (Presentation) Details hydrogen fuel cell buses being ...

  19. Interim Report of the Commission to Review the Effectiveness...

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

    Interim Report of the Commission to Review the Effectiveness of the National Energy Laboratories Interim Report of the Commission to Review the Effectiveness of the National Energy ...

  20. BLM Interim Competitive Procedures for SEZs | Open Energy Information

    Open Energy Info (EERE)

    Not Provided DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for BLM Interim Competitive Procedures for SEZs Citation BLM Interim Competitive...

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

    SciTech Connect (OSTI)

    E.G. Ison

    2008-11-08

    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. Solid waste burial grounds interim safety analysis

    SciTech Connect (OSTI)

    Saito, G.H.

    1994-10-01

    This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment.

  3. Interim Report of the Task Force on Nuclear Nonproliferation

    Broader source: Energy.gov [DOE]

    SEAB interim findings and recommendations on future areas of emphasis for DOE's nuclear nonproliferation activities.

  4. Interim Approach to the MRS facility design

    SciTech Connect (OSTI)

    Not Available

    1992-01-01

    The purpose is to present the proposed Interim Approach to the Monitored Retrievable Storage (MRS) facility design development. This Interim Approach document fulfills the function allocated to the OCRWM-SEMP (DOE/RW-0051REVlP, March 1990, Section 5.2 Approach to the MRS Design) until the MRS section of the OCRWM-SEMP is approved. Until completion of the OCRWM-SEMP, this Interim Approach document will be approved and controlled according to the Program Change Control Procedure (DOE/RW-0223REV3P). This document discusses the general approach to Conceptual Design (CD), Title I Design, and Title II Design activities.

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

    Energy Savers [EERE]

    Interim Final Rule and Proposed Rule Interim Final Rule and Proposed Rule Extracted Pages from the Interim Final Rule and Proposed Rule, September 19, 2008 PDF icon Interim Final Rule and Proposed Rule More Documents & Publications Comments of the Staff of the public utilities commission of the state of California on the interim final rule Comments on Notice of Proposed Rulemaking for Coordination of Federal Authorizations for Electric Transmission Facilities Changes recommended by OIRA

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

    SciTech Connect (OSTI)

    Ayers, C.W.

    2004-11-23

    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. 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 ...

  8. Pre-Interim Final Rulemaking Industry Comment Meeting Attendees |

    Office of Environmental Management (EM)

    Department of Energy Pre-Interim Final Rulemaking Industry Comment Meeting Attendees Pre-Interim Final Rulemaking Industry Comment Meeting Attendees Pre-Interim Final Rulemaking Industry Comment Meeting Attendees PDF icon pre-interim-final-rule-attendees-icm.pdf More Documents & Publications State Energy Advisory Board 2016 Monthly Teleconferences State Energy Advisory Board 2015 Monthly Teleconferences State Energy Advisory Board 2013 Monthly Teleconferences

  9. Design review report FFTF interim storage cask

    SciTech Connect (OSTI)

    Scott, P.L.

    1995-01-03

    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.

  10. Guidance For Preparatioon of Basis For Interim Operation (BIO) Documents

    Energy Savers [EERE]

    3011-2002 December 2002 Superceding DOE-STD-3011-94 November 1994 DOE STANDARD GUIDANCE FOR PREPARATION OF BASIS FOR INTERIM OPERATION (BIO) DOCUMENTS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-3011-2002 ii This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S.

  11. Interim Ventilation System Tie-in Completed

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

    , 2016 Interim Ventilation System Tie-in Completed Early this week sub-contractors at the Waste Isolation Pilot Plant (WIPP) completed the "tie in" of the new interim ventilation system (IVS) to the ductwork for the existing underground ventilation system. Following a series of operational tests, the IVS is expected to increase airflow in the WIPP underground by approximately 54,000 cubic feet per minute. The tie-in operation consisted of removal of sections of the existing ductwork

  12. NEXT GENERATION MELTER OPTIONEERING STUDY - INTERIM REPORT

    SciTech Connect (OSTI)

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

    2010-10-19

    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.

  13. Solvent Refined Coal (SRC) process: trace elements. Research and development report No. 53, interim report No. 31, August 1976-July 1977. Volume III. Pilot plant development work. Part 6. [Fate of 36 trace elements

    SciTech Connect (OSTI)

    1980-03-01

    Results are presented on a study of the distribution and fate of 34 trace elements in the Solvent Refined Coal Process at the pilot plant located at Fort Lewis, Washington, and operated by The Pittsburg and Midway Coal Mining Co. under contract with the US Department of Energy. Neutron activation analysis was used to determine Ti, V, Ca, Mg, Al, Cl, Mn, As, Sb, Se, Hg, Br, Co, Ni, Cr, Fe, Na, Rb, Cs, K, Sc, Tb, Eu, Sm, Ce, La, Sr, Ba, Th, Hf, Ta, Ga, Zr, and Cu in feed coals, process solvent, Solvent Refined Coal (SRC), mineral residues, wet filter cake, by-product solvents, process and effluent waters and by-product sulfur. The sample points were chosen such that the major process streams were adequately described and that the major input and output materials were included. Atomic absorption spectrophotometry was used to measure the toxic elements Pb, Cd, Be in plant-derived solvents, effluent water and Hamer Marsh water. Specific methods were developed for analysis of a wide range of material compositions. The neutron activation analysis procedures were divided into short and long irradiation procedures for elements with short half lives (less than 3 hours) and intermediate to long half lives ( 8 hours to 5.2 years). Data are presented for a third equilibrium set of samples from the SRC-I process and compared to two similar sets analyzed previously. A material balance (or budget) was calculated for each element from the concentration data and the yields of each process fraction. Data are also presented on a study of carbon monoxide addition to the hydrogen stream and its effect on trace elements, and trace element data on a study of thirty-six plant effluent water samples taken during an SRC-I production run.

  14. Solvent Refined Coal (SRC) process: trace elements. Research and development report No. 53, interim report No. 30. Volume III. Pilot plant development work. Part 6. The fate of trace elements in the SRC process. [111 references

    SciTech Connect (OSTI)

    Khalil, S. R.

    1980-02-01

    Instrumental neutron activation analysis was used to study the distribution and fate of up to 36 elements in the Solvent Refined Coal Process Pilot Plant located at Fort Lewis, Washington. The elements Ti, V, Mg, Ca, Al, Cl, Mn, As, Br, Na, K, Sm, La, Ga, Cu, Sb, Se, Hg, Ni, Co, Cr, Fe, Rb, Cs, Sc, Tb, Eu, Ce, Sr, Ba, Th, U, Hf, Ta, Zr and Zn were measured in feed coal, insoluble residues, process solvent, process and effluent waters, by-product sulfur, SRC-I solid product, liquid-liquid separator oils and SRC-II liquid products. The material balance was calculated for each element from the concentration data and yields of each process fraction for both the SRC-I and SRC-II processes. Except for Ti, Cl and Br in the SRC-I mode and Hg in the SRC-II mode, each element was substantially lower in the SRC products than in the original feed coal. Residues from the process contained more than 80% of the trace element content found in the coal, except for Hg. More than 98.5% of the total contents of K and Fe in coal were retained in the insoluble residues. Elements such as Hg, Se, As and Sb can form volatile compounds (such as Hg/sup 0/, H/sub 2/Se, AsH/sub 3/ and SbH/sub 3/) stable under the process conditions. The high enhancement factors of Se (957), As (202) and Sb (27.4) in the aqueous phase of the separator water compared to that of the oil are evidence for the formation of volatile species which are more soluble in water than in the oil phase.

  15. Effectiveness of interim remedial actions at a radioactive waste facility

    SciTech Connect (OSTI)

    Devgun, J.S.; Beskid, N.J.; Peterson, J.M.; Seay, W.M.; McNamee, E.; USDOE Oak Ridge Operations Office, TN; Bechtel National, Inc., Oak Ridge, TN )

    1989-01-01

    Over the past eight years, several interim remedial actions have been taken at the Niagara Falls Storage Site (NFSS), primarily to reduce radon and gamma radiation exposures and to consolidate radioactive waste into a waste containment facility. Interim remedial actions have included capping of vents, sealing of pipes, relocation of the perimeter fence (to limit radon risk), transfer and consolidation of waste, upgrading of storage buildings, construction of a clay cutoff wall (to limit the potential groundwater transport of contaminants), treatment and release of contaminated water, interim use of a synthetic liner, and emplacement of an interim clay cap. An interim waste containment facility was completed in 1986. 6 refs., 3 figs.

  16. High Temperature Materials Interim Data Qualification Report

    SciTech Connect (OSTI)

    Nancy Lybeck

    2010-08-01

    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.

  17. Interim UFD Storage and Transportation - Transportation Working Group Report

    SciTech Connect (OSTI)

    Maheras, Steven J.; Ross, Steven B.

    2011-03-30

    The Used Fuel Disposition (UFD) Transportation Task commenced in October 2010. As its first task, Pacific Northwest National Laboratory (PNNL) compiled a draft list of structures, systems, and components (SSCs) of transportation systems and their possible degradation mechanisms during very long term storage (VLTS). The list of SSCs and the associated degradation mechanisms [known as features, events, and processes (FEPs)] were based on the list of SSCs and degradation mechanisms developed by the UFD Storage Task (Stockman et al. 2010)

  18. Hanford Advisory Board Fiscal Year 2015 Interim Work Plan

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

    Alternate cesium removal strategies could entail capturing cesium on materials (such as those used in Japan following the Fukushima releases), which would then need to be stored ...

  19. Interim report cyanide safety studies

    SciTech Connect (OSTI)

    Burger, L.L.; Scheele, R.D.

    1988-09-30

    Over the past few years several proposals have been prepared to investigate the potential hazard of ferrocyanide-nitrate reactions that may occur in some Hanford waste tanks. In 1988 Westinghouse Hanford Company (WHC) decided to perform some of the suggested experimental work. Based on the proposal submitted in July, 1988, it was agreed to do a portion of the work during FY 1988. This report summarizes the results of that work, provides a preliminary analysis of the results, and includes recommendations for further study. The work completed consists of a brief literature search, preparation and analysis of several cesium nickel ferrocyanide, Cs{sub 2}NiFe(CN){sub 6}, oxdiation studies using Differential Scanning Calorimetry (DSC) and Thermogravimetry (TG), and small scale explosion tests.

  20. Expedited approach to a carbon tetrachloride spill interim remedial action

    SciTech Connect (OSTI)

    Cowdery, C.; Primrose, A.; Uhland, J.; Castaneda, N.

    1998-07-01

    Monitored natural attenuation was selected as an interim measure for a carbon tetrachloride spill site where source removal or in situ treatment cannot currently be implemented due to the surrounding infrastructure. Rather than delay action until the site is more accessible to an interim action, this more expedited approach would support a final action. Individual Hazard Substance Site (IHSS) 118.1 is a former underground storage tank at Rocky Flats Environmental Technology Site (RFETS) that stored carbon tetrachloride for process use. Inadvertent releases associated with filling and failure of the tank system resulted in an accumulation of carbon tetrachloride in a bedrock depression around a group of former process waste tanks. Access to the source of contamination is obstructed by numerous utilities, the process waste tanks, and other components of the site infrastructure that limit the ability to conduct an effective remedial action. A preremedial field investigation was conducted in September 1997 to identify and delineate the extent of the dense nonaqueous phase liquid (DNAPL) in the subsurface. Data collected from the investigation revealed that natural processes might be limiting the migration of contaminants from the source area.

  1. Interim Management of Nuclear Materials

    Office of Environmental Management (EM)

    Integrated Safety Management (ISM) Integrated Safety Management (ISM) The objective of ISM is to perform work in a safe and environmentally sound manner. More specifically, as described in DOE P 450.4, Safety Management System Policy: "The Department and Contractors must systematically integrate safety into management and work practices at all levels so that missions are accomplished while protecting the public, the worker, and the environment. This is to be accomplished through effective

  2. Interim site characterization report and ground-water monitoring program for the Hanford site solid waste landfill

    SciTech Connect (OSTI)

    Fruland, R.M.; Hagan, R.A.; Cline, C.S.; Bates, D.J.; Evans, J.C.; Aaberg, R.L.

    1989-07-01

    Federal and state regulations governing the operation of landfills require utilization of ground-water monitoring systems to determine whether or not landfill operations impact ground water at the point of compliance (ground water beneath the perimeter of the facility). A detection-level ground-water monitoring system was designed, installed, and initiated at the Hanford Site Solid Waste Landfill (SWL). Chlorinated hydrocarbons were detected at the beginning of the ground-water monitoring program and continue to be detected more than 1 year later. The most probable source of the chlorinated hydrocarbons is washwater discharged to the SWL between 1985 and 1987. This is an interim report and includes data from the characterization work that was performed during well installation in 1987, such as field observations, sediment studies, and geophysical logging results, and data from analyses of ground-water samples collected in 1987 and 1988, such as field parameter measurements and chemical analyses. 38 refs., 27 figs., 8 tabs.

  3. Evaluation of Hose in Hose Transfer Line Service Life for Hanford's Interim Stabilization Program

    SciTech Connect (OSTI)

    TORRES, T.D.

    2000-08-24

    RPP-6153, Engineering Task Plan for Hose-in-Hose Transfer System for the Interim Stabilization Program, defines the programmatic goals, functional requirements, and technical criteria for the development and subsequent installation of transfer line equipment to support Hanford's Interim Stabilization Program. RPP-6028, Specification for Hose in Hose Transfer Lines for Hanford's Interim Stabilization Program, has been issued to define the specific requirements for the design, manufacture, and verification of transfer line assemblies for specific waste transfer applications. Included in RPP-6028 are tables defining the chemical constituents of concern to which transfer lines will be exposed. Current Interim Stabilization Program planning forecasts that the at-grade transfer lines will be required to convey pumpable waste for as much as three years after commissioning. Prudent engineering dictates that the equipment placed in service have a working life in excess of this forecasted time period, with some margin to allow for future adjustments to the planned schedule. This document evaluates the effective service life of the Hose-in-Hose Transfer Lines, based on information submitted by the manufacturer and published literature. The effective service life of transfer line assemblies is a function of several factors. Foremost among these are process fluid characteristics, ambient environmental conditions, and the manufacturer's stated shelf life. This evaluation examines the manufacturer's certification of shelf life, the manufacturer's certifications of chemical compatibility with waste, and published literature on the effects of exposure to ionizing radiation on the mechanical properties of elastomeric materials to evaluate transfer line service life.

  4. SNF Interim Storage Canister Corrosion and Surface Environment Investigations

    SciTech Connect (OSTI)

    Bryan, Charles R.; Enos, David G.

    2015-09-01

    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 spent nuclear fuel (SNF). Of particular concern is stress corrosion cracking (SCC), by which a through-wall crack could potentially form in a canister outer wall over time intervals that are shorter than possible dry storage times. In order for SCC to occur, three criteria must be met. A corrosive environment must be present on the canister surface, the metal must susceptible to SCC, and sufficient tensile stress to support SCC must be present through the entire thickness of the canister wall. SNL is currently evaluating the potential for each of these criteria to be met.

  5. Final Environmental Impact Statement Safe Interim Storage Of...

    Office of Environmental Management (EM)

    Summary-1995.html6272011 12:58:00 PM FINAL ENVIRONMENTAL IMPACT STATEMENT SAFE INTERIM STORAGE ... in their purpose, intent, and procedures, the Washington State Department of ...

  6. Interim Final Rule and Request for Comments, Federal Register...

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

    Document displays the interim final rule and request for comments for Energy Conservation Standards for New Federal Commercial and Multi-Family High-Rise Residential Buildings and ...

  7. ATVM Interim Final Rule Correction | Department of Energy

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

    A few corrections to the final rule regarding fuel economy numbers. ATVM Interim Final Rule Correction More Documents & Publications Updated Guidance For Applicants To Advanced...

  8. EIS-0283-S2: Amended Interim Action Determination | Department...

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

    Plutonium Materials from the Department of Energy Standard 3013 Surveillance Program at the Savannah River Site (Amending Interim Action Determination of 12082008) DOE is ...

  9. 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 ...

  10. Letter on the Interim Report of the Commission to Review the...

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

    Interim Report of the Commission to Review the Effectiveness of the National Energy Laboratories Letter on the Interim Report of the Commission to Review the Effectiveness of the ...

  11. Cost and schedule control systems criteria for contract performance measurement: work breakdown structure guide

    SciTech Connect (OSTI)

    Not Available

    1981-10-01

    This document provides guidance on development and use of the Work Breakdown Structure (WBS) technique. It describes the types of work breakdown structures, their preparation, and their effective use for organizing, planning, and controlling projects and contracts managed by the Department of Energy (DOE). The WBS technique is the preferred management tool for identifying and defining work. It provides an ordered framework for planning and controlling the work efforts to be performed in achieving technical objectives and for summarizing data, and the quantitative and narrative reports used for monitoring cost, schedule and technical performance. A WBS is developed for first identifying the major end items or systems to be produced, followed by their successive subdivision into increasingly detailed and manageable subsidiary products. Most of these subsidiary products are the direct result of work, while others are simply the aggregation of selected products into a logical set for management control purposes. In either case, detailed tasks are eventually identified for each product on the WBS at the level where work will be performed. As a minimum, these detailed tasks or work packages identify the product, describe the effort to be performed, identify the resources to be applied, specify the budget and schedule constraints, and the technical requirements, and identify the organizational element responsible for work accomplishment.

  12. Direct measurement of the work of fracture for grain boundaries of twist misorientation about (100) in tungsten

    SciTech Connect (OSTI)

    Liu, J.M.; Shen, B.W.

    1984-06-01

    The authors report results on the direct measurement of the work of fracture in twist boundaries in electron beam zone refined bicrystals of tungsten. The work of fracture is referred to as the energy required for crack extension. This approach may be used to advantage when the effects of impurities are present, for example, in problems related to grain boundary embrittlement in steels, copper and nickel.

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

    SciTech Connect (OSTI)

    MAY TH

    2008-08-12

    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.

  14. 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.

    2006-04-01

    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.

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

    SciTech Connect (OSTI)

    HOLM MJ

    2009-06-25

    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.

  16. Technical bases for interim storage of spent nuclear fuel

    SciTech Connect (OSTI)

    Johnson, A.B. Jr.

    1981-06-01

    The experience base for water storage of spent nuclear fuel has evolved since 1943. The technology base includes licensing documentation, standards, technology studies, pool operator experience, and documentation from public hearings. That base reflects a technology which is largely successful and mundane. It projects probable satisfactory water storage of spent water reactor fuel for several decades. Interim dry storage of spent water reactor fuel is not yet licensed in the US, but a data base and documentation have developed. There do not appear to be technological barriers to interim dry storage, based on demonstrations with irradiated fuel. Water storage will continue to be a part of spent fuel management at reactors. Whether dry storage becomes a prominent interim fuel management option depends on licensing and economic considerations. National policies will strongly influence how long the spent fuel remains in interim storage and what its final disposition will be.

  17. EIS-0283-S2: Interim Action Determination | Department of Energy

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

    in H-Canyon at the Savannah River Site For more information on this project, see the project webpage: http:energy.govnode299815. Download Document PDF icon EIS-0283-S2: Interim ...

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

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

    and Response to Time-Based Rates from the Consumer Behavior Studies (June 2015) Interim Report on Customer Acceptance, Retention, and Response to Time-Based Rates from the ...

  19. Now Available: Interim Report on Customer Acceptance, Retention...

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

    and Response to Time-Based Rates from the Consumer Behavior Studies Now Available: Interim Report on Customer Acceptance, Retention, and Response to Time-Based Rates from the ...

  20. Canister Storage Building and Interim Storage Area - Hanford...

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

    300 Area 324 Building 325 Building 400 AreaFast Flux Test Facility 618-10 and 618-11 Burial Grounds 700 Area B Plant B Reactor C Reactor Canister Storage Building and Interim ...

  1. DOE Names Interim Manager for Idaho Operations Office

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

    DOE Names Interim Manager for Idaho Operations Office Dennis Miotla, the Office of Nuclear Energy's Deputy Assistant Secretary Dennis Miotla for Nuclear Power Deployment, has been named the interim manager of the U.S. Department of Energy's Idaho Operations Office, while the Department recruits a permanent manager. Mr. Miotla will succeed Elizabeth Sellers, who has served as Idaho Operations Office Manager from April, 2003. Sellers plans to retire from federal service in February. "Under

  2. Interim Safety Basis for Fuel Supply Shutdown Facility

    SciTech Connect (OSTI)

    BENECKE, M.W.

    2000-09-07

    This ISB, in conjunction with the IOSR, provides 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 or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines.

  3. Probabilistic Performance Assessment: SCC of SNF Interim Storage Canisters.

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect Probabilistic Performance Assessment: SCC of SNF Interim Storage Canisters. Citation Details In-Document Search Title: Probabilistic Performance Assessment: SCC of SNF Interim Storage Canisters. Abstract not provided. Authors: Bryan, Charles R. ; Sallaberry, Cedric Jean-Marie ; Dingreville, Remi Philippe Michel ; Stockman, Christine T. ; Adkins, Harold ; Sutton, Mark Publication Date: 2015-04-01 OSTI Identifier: 1248697 Report Number(s): SAND2015-2776C 582053

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

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

    King County Metro Transit Hybrid Articulated Buses: Interim Evaluation Results K. Chandler Battelle K. Walkowicz National Renewable Energy Laboratory Technical Report NREL/TP-540-39742 April 2006 King County Metro Transit Hybrid Articulated Buses: Interim Evaluation Results K. Chandler Battelle K. Walkowicz National Renewable Energy Laboratory Prepared under Task No. FC06.3000 Technical Report NREL/TP-540-39742 April 2006 National Renewable Energy Laboratory 1617 Cole Boulevard, Golden, Colorado

  5. TWRS HLW interim storage facility search and evaluation

    SciTech Connect (OSTI)

    Calmus, R.B., Westinghouse Hanford

    1996-05-16

    The purpose of this study was to identify and provide an evaluation of interim storage facilities and potential facility locations for the vitrified high-level waste (HLW) from the Phase I demonstration plant and Phase II production plant. In addition, interim storage facilities for solidified separated radionuclides (Cesium and Technetium) generated during pretreatment of Phase I Low-Level Waste Vitrification Plant feed was evaluated.

  6. Situational Awareness as a Measure of Performance in Cyber Security Collaborative Work

    SciTech Connect (OSTI)

    Malviya, Ashish; Fink, Glenn A.; Sego, Landon H.; Endicott-Popovsky, Barbara E.

    2011-04-11

    Cyber defense competitions arising from U.S. service academy exercises, offer a platform for collecting data that can inform research that ranges from characterizing the ideal cyber warrior to describing behaviors during certain challenging cyber defense situations. This knowledge in turn could lead to better preparation of cyber defenders in both military and civilian settings. We conducted proof of concept experimentation to collect data during the Pacific-rim Regional Collegiate Cyber Defense Competition (PRCCDC) and analyzed it to study the behavior of cyber defenders. We propose that situational awareness predicts performance of cyber security professionals, and in this paper we focus on our collection and analysis of competition data to determine whether it supports our hypothesis. In addition to normal cyber data, we collected situational awareness and workload data and compared it against the performance of cyber defenders as indicated by their competition score. We conclude that there is a weak correlation between our measure of situational awareness and performance that we hope to exploit in further studies.

  7. Interim Basis for PCB Sampling and Analyses

    SciTech Connect (OSTI)

    BANNING, D.L.

    2001-03-20

    This document was developed as an interim basis for sampling and analysis of polychlorinated biphenyls (PCBs) and will be used until a formal data quality objective (DQO) document is prepared and approved. On August 31, 2000, the Framework Agreement for Management of Polychlorinated Biphenyls (PCBs) in Hanford Tank Waste was signed by the U.S. Department of Energy (DOE), the Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) (Ecology et al. 2000). This agreement outlines the management of double shell tank (DST) waste as Toxic Substance Control Act (TSCA) PCB remediation waste based on a risk-based disposal approval option per Title 40 of the Code of Federal Regulations 761.61 (c). The agreement calls for ''Quantification of PCBs in DSTs, single shell tanks (SSTs), and incoming waste to ensure that the vitrification plant and other ancillary facilities PCB waste acceptance limits and the requirements of the anticipated risk-based disposal approval are met.'' Waste samples will be analyzed for PCBs to satisfy this requirement. This document describes the DQO process undertaken to assure appropriate data will be collected to support management of PCBs and is presented in a DQO format. The DQO process was implemented in accordance with the U.S. Environmental Protection Agency EPA QA/G4, Guidance for the Data Quality Objectives Process (EPA 1994) and the Data Quality Objectives for Sampling and Analyses, HNF-IP-0842, Rev. 1A, Vol. IV, Section 4.16 (Banning 1999).

  8. Interim Basis for PCB Sampling and Analyses

    SciTech Connect (OSTI)

    BANNING, D.L.

    2001-01-18

    This document was developed as an interim basis for sampling and analysis of polychlorinated biphenyls (PCBs) and will be used until a formal data quality objective (DQO) document is prepared and approved. On August 31, 2000, the Framework Agreement for Management of Polychlorinated Biphenyls (PCBs) in Hanford Tank Waste was signed by the US. Department of Energy (DOE), the Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) (Ecology et al. 2000). This agreement outlines the management of double shell tank (DST) waste as Toxic Substance Control Act (TSCA) PCB remediation waste based on a risk-based disposal approval option per Title 40 of the Code of Federal Regulations 761.61 (c). The agreement calls for ''Quantification of PCBs in DSTs, single shell tanks (SSTs), and incoming waste to ensure that the vitrification plant and other ancillary facilities PCB waste acceptance limits and the requirements of the anticipated risk-based disposal approval are met.'' Waste samples will be analyzed for PCBs to satisfy this requirement. This document describes the DQO process undertaken to assure appropriate data will be collected to support management of PCBs and is presented in a DQO format. The DQO process was implemented in accordance with the U.S. Environmental Protection Agency EPA QAlG4, Guidance for the Data Quality Objectives Process (EPA 1994) and the Data Quality Objectives for Sampling and Analyses, HNF-IP-0842, Rev. 1 A, Vol. IV, Section 4.16 (Banning 1999).

  9. 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.

    1980-12-01

    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.

  10. Carbonyl sulfide/carbon chemistry: Interim report, July 1, 1985-February 28, 1986

    SciTech Connect (OSTI)

    Hinckley, C.C.; Shiley, R.H.

    1986-05-01

    This interim report describes work performed during the first eight months of a continuing project, including descriptions of sample preparations and analyses. The objective of the study is to determine the effects of carbonyl sulfide, a product of the carbon monoxide/ethanol desulfurization process, on coal. A coal is first treated with carbon monoxide to reduce pyrite, and is then reacted with OCS and N/sub 2/ under various conditions. OCS is a potent resulfurization agent and appears to affect the formation of mesophase in chars derived from the coal. 8 refs., 1 fig., 8 tabs.

  11. Emulytics for Cyber-Enabled Physical Attack Scenarios: Interim LDRD Report of Year One Results.

    SciTech Connect (OSTI)

    Clem, John; Urias, Vincent; Atkins, William Dee; Symonds, Christopher J.

    2015-12-08

    Sandia National Laboratories has funded the research and development of a new capability to interactively explore the effects of cyber exploits on the performance of physical protection systems. This informal, interim report of progress summarizes the project’s basis and year one (of two) accomplishments. It includes descriptions of confirmed cyber exploits against a representative testbed protection system and details the development of an emulytics capability to support live, virtual, and constructive experiments. This work will support stakeholders to better engineer, operate, and maintain reliable protection systems.

  12. Hazelwood Interim Storage Site annual environmental report for calendar year 1991, Hazelwood, Missouri. [Hazelwood Interim Storage Site

    SciTech Connect (OSTI)

    Not Available

    1992-09-01

    This document describes the environmental monitoring program at the Hazelwood Interim Storage Site (HISS) and surrounding area, implementation of the program, and monitoring results for 1991. 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), a DOE program to 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 monitoring program at HISS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and radium-226, thorium-230, and total uranium concentrations in surface water, sediment, and groundwater. Additionally, several nonradiological parameters are measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE orders. Environmental standards and DCGs are established to protect public health and the environment.

  13. Chromium Interim Measures Project and Ongoing Plume Investigation...

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

    Topic: Danny Katzman LANL, Provided Information on the Ongoing Characterization of the Chromium Plume in Mortandad Canyon and the Pump and Treat Pilot Test. Chromium Update - March...

  14. Northeast Site Non-Aqueous Phase Liquids Interim Measures Progress...

    Office of Legacy Management (LM)

    ... The initial activities for remediation of Area B will start in Spring 2003. These activities will involve evaluation of the permitting and environmental compliance requirements and ...

  15. Chromium Interim Measures Project and Ongoing Plume Investigation

    Broader source: Energy.gov [DOE]

    At the March 12, 2015 Committee meeting Danny Katzman LANL, Provided Information on the Ongoing Characterization of the Chromium Plume in Mortandad Canyon and the Pump and Treat Pilot Test.

  16. Permitting plan for the high-level waste interim storage

    SciTech Connect (OSTI)

    Deffenbaugh, M.L.

    1997-04-23

    This document addresses the environmental permitting requirements for the transportation and interim storage of solidified high-level waste (HLW) produced during Phase 1 of the Hanford Site privatization effort. Solidified HLW consists of canisters containing vitrified HLW (glass) and containers that hold cesium separated during low-level waste pretreatment. The glass canisters and cesium containers will be transported to the Canister Storage Building (CSB) in a U.S. Department of Energy (DOE)-provided transportation cask via diesel-powered tractor trailer. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage of Tank Waste Remediation Systems (TWRS) immobilized HLW (IHLW) and other canistered high-level waste forms; and (2) interim storage and disposal of TWRS immobilized low-activity tank waste (ILAW). An environmental requirements checklist and narrative was developed to identify the permitting path forward for the HLW interim storage (HLWIS) project (See Appendix B). This permitting plan will follow the permitting logic developed in that checklist.

  17. ATVM Loan Program Interim Final Rule (November 12, 2008) | Department of

    Energy Savers [EERE]

    Energy Loan Program Interim Final Rule (November 12, 2008) ATVM Loan Program Interim Final Rule (November 12, 2008) Advanced Technology Vehicles Manufacturing Incentive Program PDF icon ATVM Loan Program Interim Final Rule More Documents & Publications Automotive Trade Policy Council: Proposed Interim Final Rule Updated Guidance For Applicants To Advanced Technology Vehicles Manufacturing Loan Program ATVM Guidance for Applicants 11.4.14

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

    SciTech Connect (OSTI)

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

    1992-04-01

    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.

  19. Single-shell tank interim stabilization project plan

    SciTech Connect (OSTI)

    Ross, W.E.

    1998-03-27

    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.

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

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

    RTD Biodiesel (B20) Transit Bus Evaluation: Interim Review Summary K. Proc, R. Barnitt, and R.L. McCormick Technical Report NREL/TP-540-38364 August 2005 RTD Biodiesel (B20) Transit Bus Evaluation: Interim Review Summary K. Proc, R. Barnitt, and R.L. McCormick Prepared under Task No. FC05.9400 Technical Report NREL/TP-540-38364 August 2005 National Renewable Energy Laboratory 1617 Cole Boulevard, Golden, Colorado 80401-3393 303-275-3000 * www.nrel.gov Operated for the U.S. Department of Energy

  1. Measurement and Basic Physics Committee of the US cross-section evaluation working group. Annual report 1996

    SciTech Connect (OSTI)

    Smith, D.L.; McLane, V.

    1996-11-01

    The Cross-Section Evaluation Working Group (CSEWG) is a long-standing committee charged with the responsibility for organizing and overseeing the U.S. cross-section evaluation effort. It`s main product is the official U.S. evaluated nuclear data file, ENDF. The current version of this file is Version VI. All evaluations included in ENDF are reviewed and approved by CSEWG and issued by the U.S. Nuclear Data Center, Brookhaven National Laboratory. CSEWG is comprised of volunteers from the U.S. nuclear data community who possess expertise in evaluation methodologies and who collectively have been responsible for producing most of the evaluations included in ENDF. In 1992 CSEWG added the Measurements Committee to its list of standing committees and subcommittees. This action was based on a recognition of the importance of experimental data in the evaluation process as well as the realization that measurement activities in the U.S. were declining at an alarming rate and needed all possible encouragement to avoid the loss of this resource. The mission of the Committee is to maintain a network of experimentalists in the U.S. that would provide needed encouragement to the national nuclear data measurement effort through improved communication and facilitation of collaborative activities. In 1994, an additional charge was added to the responsibilities of this Committee, namely, to serve as an interface between the more applied interests represented in CSEWG and the basic nuclear science community. This annual report is the second such document issued by the Committee. It contains voluntary contributions from eleven laboratories in the U.S. which have been prepared by members of the Committee and submitted to the Chairman for compilation and editing. It is hoped that the information provided here on the work that is going on at the reporting laboratories will prove interesting and stimulating to the readers.

  2. High Temperature Materials Interim Data Qualification Report FY 2011

    SciTech Connect (OSTI)

    Nancy Lybeck

    2011-08-01

    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.

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

    SciTech Connect (OSTI)

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

    2000-05-22

    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.

  4. Single-shell tank interim stabilization project plan

    SciTech Connect (OSTI)

    Ross, W.E.

    1998-05-11

    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.

  5. SLIGHTLY IRRADIATED FUEL (SIF) INTERIM DISPOSITION PROJECT

    SciTech Connect (OSTI)

    NORTON SH

    2010-02-23

    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.

  6. First interim examination of defected BWR and PWR rods tested in unlimited air at 229/sup 0/C

    SciTech Connect (OSTI)

    Einziger, R.E.; Cook, J.A.

    1983-01-01

    A five-year whole rod test was initiated to investigate the long-term stability of spent fuel rods under a variety of possible dry storage conditions. Both PWR and BWR rods were included in the test. The first interim examination was conducted after three months of testing to determine if there was any degradation in those defected rods stored in an unlimited air atmosphere. Visual observations, diametral measurements and radiographic smears were used to assess the degree of cladding deformation and particulate dispersal. The PWR rod showed no measurable change from the pre-test condition. The two original artificial defects had not changed in appearance and there was no diametral growth of the cladding. One of the defects in BWR rod showed significant deformation. There was approximately 10% cladding strain at the defect site and a small axial crack had formed. The fuel in the defect did not appear to be friable. The second defect showed no visible change and no cladding strain. Following examination, the test was continued at 230/sup 0/C. Another interim examination is planned during the summer of 1983. This paper discusses the details and meaning of the data from the first interim examination.

  7. 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.

    2003-02-27

    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.

  8. Hazelwood Interim Storage Site environmental monitoring summary, Hazelwood, Missouri, calendar year 1984

    SciTech Connect (OSTI)

    Not Available

    1985-07-01

    The Hazelwood Interim Storage Site (HISS) is located at 9200 Latty Avenue, Hazelwood, Missouri. The property on which the HISS is situated is owned by the Jarboe Realty and Investment Company and is leased to Futura Coatings, Inc. Radiological surveys in 1977 and 1982 indicated uranium and thorium contamination and elevated radiation levels in the soil on this property and several others in the immediate vicinity. As part of the research and development program authorized by Congress under the 1984 Energy and Water Appropriations Act, Bechtel National, Inc. (BNI) is conducting remedial action on-site and at the vicinity properties. The work is being performed as part of the US Department of Energy (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). Jarboe Realty and Investment Company has agreed to permit DOE to store contaminated material from the FY 1984 and 1985 Latty Avenue cleanup on its property. The contaminated material will be added to the existing pile created during the earlier site cleanup. The pile will then be covered to prevent erosion or migration of contamination. The property will be maintained as the HISS by DOE until final disposition for these materials is determined. BNI is conducting a surveillance monitoring program at the HISS during the interim storage period to detect potential migration of contaminants from the storage pile via air, water, and sediment. This summary provides these monitoring data for calendar year 1984. 6 refs., 4 tabs.

  9. Caustic-Side Solvent-Extraction Modeling for Hanford Interim Pretreatment System

    SciTech Connect (OSTI)

    Moyer, B.A.; Birdwell, J.F.; Delmau, L. H.; McFarlane, J.

    2008-06-01

    The purpose of this work is to examine the applicability of the Caustic-Side Solvent Extraction (CSSX) process for the removal of cesium from Hanford tank-waste supernatant solutions in support of the Hanford Interim Pretreatment System (IPS). The Hanford waste types are more challenging than those at the Savannah River Site (SRS) in that they contain significantly higher levels of potassium, the chief competing ion in the extraction of cesium. It was confirmed by use of the CSSX model that the higher levels of potassium depress the cesium distribution ratio (DCs), as validated by measurement of DCs values for four of eight specified Hanford waste-simulant compositions. The model predictions were good to an apparent standard error of 11%. It is concluded from batch distribution experiments, physical-property measurements, equilibrium modeling, flowsheet calculations, and contactor sizing that the CSSX process as currently employed for cesium removal from alkaline salt waste at the SRS is capable of treating similar Hanford tank feeds. For the most challenging waste composition, 41 stages would be required to provide a cesium decontamination factor (DF) of 5000 and a concentration factor (CF) of 5. Commercial contacting equipment with rotor diameters of 10 in. for extraction and 5 in. for stripping should have the capacity to meet throughput requirements, but testing will be required to confirm that the needed efficiency and hydraulic performance are actually obtainable. Markedly improved flowsheet performance was calculated for a new solvent formulation employing the more soluble cesium extractant BEHBCalixC6 used with alternative scrub and strip solutions, respectively 0.1 M NaOH and 10 mM boric acid. The improved system can meet minimum requirements (DF = 5000 and CF = 5) with 17 stages or more ambitious goals (DF = 40,000 and CF = 15) with 19 stages. Potential benefits of further research and development are identified that would lead to reduced costs, greater adaptability of the process to DOE alkaline salt wastes, and greater readiness for implementation. Such benefits accrue from optimal sizing of centrifugal contactors for application of the CSSX process for the IPS; more accurate modeling of cesium extraction with greater flexibility and applicability to a variety of feeds and flowsheet conditions; and further improving and optimizing the alternative CSSX solvent and scrub/strip system.

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

    SciTech Connect (OSTI)

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

    2007-04-01

    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.

  11. 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.

    2009-02-01

    DOEs 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.

  12. Interim Storage of Plutonium in Existing Facilities

    SciTech Connect (OSTI)

    Woodsmall, T.D.

    1999-05-10

    'In this era of nuclear weapons disarmament and nonproliferation treaties, among many problems being faced by the Department of Energy is the safe disposal of plutonium. There is a large stockpile of plutonium at the Rocky Flats Environmental Technology Center and it remains politically and environmentally strategic to relocate the inventory closer to a processing facility. Savannah River Site has been chosen as the final storage location, and the Actinide Packaging and Storage Facility (APSF) is currently under construction for this purpose. With the ability of APSF to receive Rocky Flats material an estimated ten years away, DOE has decided to use the existing reactor building in K-Area of SRS as temporary storage to accelerate the removal of plutonium from Rocky Flats. There are enormous cost savings to the government that serve as incentive to start this removal as soon as possible, and the KAMS project is scheduled to receive the first shipment of plutonium in January 2000. The reactor building in K-Area was chosen for its hardened structure and upgraded seismic qualification, both resulting from an effort to restart the reactor in 1991. The KAMS project has faced unique challenges from Authorization Basis and Safety Analysis perspectives. Although modifying a reactor building from a production facility to a storage shelter is not technically difficult, the nature of plutonium has caused design and safety analysis engineers to make certain that the design of systems, structures and components included will protect the public, SRS workers, and the environment. A basic overview of the KAMS project follows. Plutonium will be measured and loaded into DOT Type-B shipping packages at Rocky Flats. The packages are 35-gallon stainless steel drums with multiple internal containment boundaries. DOE transportation vehicles will be used to ship the drums to the KAMS facility at SRS. They will then be unloaded, stacked and stored in specific locations throughout the reactor building. The storage life is projected to be ten years to allow the preparation of APSF. DOE has stipulated that there be no credible release during storage, since there are no design features in place to mitigate a release of plutonium (i.e. HEPA filters, facility containment boundaries, etc.). This mandate has presented most of the significant challenges to the safety analysis team. The shipping packages are designed to withstand certain accidents and conditions, but in order to take credit for these the storage environment must be strictly controlled. Damages to the packages from exposure to fire, dropping, crushing and other impact accidents have been analyzed, and appropriate preventative design features have been incorporated. Other efforts include the extension of the shipping life (roughly two years) to a suitable storage life of ten years. These issues include the effects of internal pressure increases, seal degradation and the presence of impurities. A process known as the Container Qualification Program has been conducted to address these issues. The KAMS project will be ready to receive the first shipment from Rocky Flats in January 2000. No credible design basis scenarios resulting in the release of plutonium exist. This work has been useful in the effort to provide a safer disposition of plutonium, but also the lessons learned and techniques established by the team will help with the analysis of future facility modifications.'

  13. 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.; Nass, R.

    1995-08-01

    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.

  14. FRACTIONAL CRYSTALLIZATION LABORATORY TESTING WITH INTERIM PRETREATMENT SYSTEM FEEDS

    SciTech Connect (OSTI)

    HERTING DL

    2008-09-17

    The fractional crystallization process was developed as a pretreatment method for saltcake waste retrieved from Hanford single-shell tanks (SST). The process separates the retrieved SST waste into a high-level waste stream containing the bulk of the radionuclides and a low-activity waste stream containing the bulk of the nonradioactive sodium salts. The Interim Pretreatment System project shifted the focus on pretreatment planning from SST waste to double-shell tank waste.

  15. Probabilistic Performance Assessment: SCC of SNF Interim Storage Canisters

    Office of Scientific and Technical Information (OSTI)

    Probabilistic Performance Assessment: SCC of SNF Interim Storage Canisters C. Bryan1, C. Sallaberry1, R. Dingreville1, C. Stockman1, H. Adkins2, and M. Sutton3 1SNL, 2PNNL, 3LLNL Presentation for IHLRWM, April 12-16, 2015 Charleston, SC Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract

  16. Interim Stabilization Equipment Essential and Support Drawing Plan

    SciTech Connect (OSTI)

    KOCH, M.R.

    1999-10-22

    The purpose of this document is to list the Interim Stabilization equipment drawings that are classified as Essential or Support drawings. Essential Drawings: Those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment. Support Drawings: Those drawings identified by the facility staff that further describe the design details of structures, systems or components shown on essential drawings.

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

    DOE Patents [OSTI]

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

    1984-01-01

    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.

  18. Report on interim storage of spent nuclear fuel

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    The report on interim storage of spent nuclear fuel discusses the technical, regulatory, and economic aspects of spent-fuel storage at nuclear reactors. The report is intended to provide legislators state officials and citizens in the Midwest with information on spent-fuel inventories, current and projected additional storage requirements, licensing, storage technologies, and actions taken by various utilities in the Midwest to augment their capacity to store spent nuclear fuel on site.

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

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

    of Energy Interim Report of the Task Force on Nuclear Nonproliferation Interim Report of the Task Force on Nuclear Nonproliferation The SEAB Task Force on Nuclear Nonproliferation (TFNN) was established by the Secretary of Energy on December 20, 2014 to advise the Department of Energy (DOE) on future areas of emphasis for its nuclear nonproliferation activities. This interim report of the Task Force sets forth its findings and recommendations to date in five timely and important areas: (I)

  20. Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from

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

    Decommissioned Reactors | Department of Energy Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from Decommissioned Reactors Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from Decommissioned Reactors PDF icon 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 AND THE CONGRESS BY THE SECRETARY OF ENERGY ON THE NEED

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

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

    Nuclear Fuel from Decommissioned Reactors Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from Decommissioned Reactors PDF icon Report to Congress on Plan ...

  2. Interim Report of the Commission to Review the Effectiveness of the National Energy Laboratories

    Broader source: Energy.gov [DOE]

    This Interim Report presents the preliminary observations and recommendations gleaned from Phase I of the study by the Commission to Review the Effectiveness of the National Energy Laboratories ...

  3. Definition of the base analysis case of the interim performance assessment

    SciTech Connect (OSTI)

    Mann, F.M.

    1995-12-01

    The base analysis case for the ``Hanford Low-Level Tank Waste Interim Performance Assessment`` is defined. Also given are brief description of the sensitivity cases.

  4. RCRA facility investigation/corrective measures study work plan for the 200-UP-2 Operable Unit, Hanford Site, Richland, Washington

    SciTech Connect (OSTI)

    Not Available

    1993-06-01

    The 200-UP-2 Operable Unit is one of two source operable units at the U Plant Aggregate Area at the Hanford Site. Source operable units include waste management units and unplanned release sites that are potential sources of radioactive and/or hazardous substance contamination. This work plan, while maintaining the title RFI/CMS, presents the background and direction for conducting a limited field investigation in the 200-UP-2 Operable Unit, which is the first part of the process leading to final remedy selection. This report discusses the background, prior recommendations, goals, organization, and quality assurance for the 200-UP-2 Operable Unit Work Plan. The discussion begins with a summary of the regulatory framework and the role of the work plan. The specific recommendations leading into the work plan are then addressed. Next, the goals and organization of the report are discussed. Finally, the quality assurance and supporting documentation are presented.

  5. Phase 1 RCRA Facility Investigation & Corrective Measures Study Work Plan for Single Shell Tank (SST) Waste Management Areas

    SciTech Connect (OSTI)

    MCCARTHY, M.M.

    1999-08-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) Corrective Action Program (RCAP) for single-shell tank (SST) farms at the US. Department of Energy's (DOE'S) Hanford Site. The DOE Office of River Protection (ORP) initiated the RCAP to address the impacts of past and potential future tank waste releases to the environment. This work plan defines RCAP activities for the four SST waste management areas (WMAs) at which releases have contaminated groundwater. Recognizing the potential need for future RCAP activities beyond those specified in this master work plan, DOE has designated the currently planned activities as ''Phase 1.'' If a second phase of activities is needed for the WMAs addressed in Phase 1, or if releases are detected at other SST WMAs, this master work plan will be updated accordingly.

  6. Phase 1 RCRA Facility Investigation and Corrective Measures Study Work Plan for Single Shell Tank Waste Management Areas

    SciTech Connect (OSTI)

    ROGERS, P.M.

    2000-06-01

    This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) for single-shell tank (SST) farms at the Hanford Site. Evidence indicates that releases at four of the seven SST waste management areas have impacted.

  7. 244-AR Vault Interim Stabilization Project Plan

    SciTech Connect (OSTI)

    LANEY, T.

    2000-03-24

    The 244-AR Vault Facility, constructed between 1966 and 1968, was designed to provide lag storage and treatment for the Plutonium-Uranium Extraction Facility (PUREX) tank farm sludges. Tank farm personnel transferred the waste from the 244-AR Vault Facility to B Plant for recovery of cesium and strontium. B Plant personnel then transferred the treatment residuals back to the tank farms for storage of the sludge and liquids. The last process operations, which transferred waste supporting the cesium/strontium recovery mission, occurred in April 1978. After the final transfer in 1978, the 244-AR facility underwent a cleanout. However, 2,271 L (600 gal) of sludge were left in Tank 004AR from an earlier transfer from Tank 241-AX-104. When the cleanout was completed, the facility was placed in a standby status. The sludge had been transferred to Tank 004AR to support Pacific Northwest National Laboratory [PNNL] vitrification work. Documentation of waste transfers suggests that a portion of the sludge may have been moved from Tank 004AR to Tank 002AR in preparation for transfer back to the AX Tank Farm; however, quantities of the sludge that were moved to Tank 002AR from that transfer must be estimated.

  8. Guidance Regarding Actions That May Proceed During the NEPA Process: Interim Actions

    Broader source: Energy.gov [DOE]

    DOE guidance to provide assistance in determining whether an action within the scope of an EIS may be taken before a record of decision is issued. The guidance reviews applicable requirements, gives examples of the types of actions that may proceed as interim actions, describes case studies, and outlines the steps in the EIS process for interim actions.

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

    SciTech Connect (OSTI)

    CONRAD EA

    2008-08-12

    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.

  10. Interim Guidance on DOE Personal Property Foreign Transactions

    Broader source: Energy.gov [DOE]

    The attached Acquisition Letter provides interim direction and procedural guidance to DOE and NNSA on proper protocol for personal property transactions executed with foreign entities, to include property title transfers, loans and abandonments and pertains to personal property in the hand of the Federal government, contractor or a third party. Direction and guidance is specific to accountable personal property, as defined in DOE Order 580.1. Guidance in this Acquisition Letter shall be followed until DOE Order 580.1 is updated to include foreign transactions.

  11. Solvent refined coal (SRC) process: trace elements research and development report no. 53, interim report no. 34. Volume III. Pilot plant development work part 6: the fate of trace elements in the SRC process for the period, August 1, 1977 - February 28, 1979. [36 elements

    SciTech Connect (OSTI)

    Filby, R.H.; Khalil, S.R.; Grimm, C.A.; Ekabaram, V.; Hunt, M.L.

    1980-12-01

    This work reports the results of neutron activation analysis determination of the fate of trace elements in the SRC II process. Six coals were studied for their behavior in material balance runs carried out at the Fort Lewis Pilot Plant. The distribution of trace elements among products and input streams was determined by thermal neutron activation analysis using thermal neutron flux of 8 x 10/sup 12/ neutrons cm/sup -2/ sec/sup -1/ followed by Ge(Li) gamma ray spectroscopy. National Bureau of Standards Standard Reference Materials (SRM) were used to evaluate the analytical precision and accuracy of the methods used. For each material balance study the trace element input stream was taken as ground coal and the output streams were vacuum bottoms, SRC II product oil, and process water. In addition to these major components, oils, sludges and waters from liquid-liquid separators, effluent waters, biosludges, and by-product sulfur were also analyzed. Concerning the distribution of trace elements in the SRC II process, it was found that the vacuum bottoms was the major sink for all trace element studied, with the exception of Hg. Much lower trace element concentrations (except for Hg) were found in the SRC II product oil relative to the vacuum bottoms or the feed coal, irrespective of coal type. The results indicate excellent balances for the elements studied, except for Hg. Except for Hg, Se, and C1, the SRC II product and process waters contributed less than 1% of the elemental balances for light oil fractions and process waters indicates that Hg, and to a lesser degree As, Se, and Sb, exhibited volatile behavior in the SRC II process but that the degree of volatility is strongly dependent on conditions or coal type.

  12. Machine plumbness criteria: Interim technology release

    SciTech Connect (OSTI)

    Not Available

    1987-06-01

    The objective of this technology release is to define the maximum allowable deviation from plumb of the centrifuge machine and to recommend machine installation techniques to achieve the specified criteria. The centrifuge feature used as a reference for plumbness is the casing centerline as defined by a line drawn between the theoretical centers of the top and bottom flange faces. In practice, this measurement is accomplished by using specified casing flange diameters or bolt patterns as the reference points. The criterion adopted for GCEP is that each machine shall be plumb within 0.5 in. over the length of the casing as initially installed. Over a long period of time the plumbness is allowed to degrade to 1.0 in. This standard should be achievable using the currently planned installation techniques and within a time limit consistent with GCEP operational objectives. For development testing, centrifuge machines are meticulously adjusted using a plumb bob to achieve a plumbness with 1/8 in. About one to two days are required to complete the installation. This level of effort is justified for a development machine especially where baseline data is being gathered. A more reasonable standard with a corresponding reduction in installation time is required for GCEP. The specified criteria of 0.5 in. maximum out-of-plumb at time of installation and 1.0 in., ultimate, are believed to be a reasonable compromise. Machine design features or operating modes that are dependent on vertical alignment were examined to assess the impact of the selected plumbness criteria. Machine performance and design requirements are defined in the applicable technology release documents.

  13. DOE Announces Availability of Four Interim Response Action Work Plans. I-1600-1603-1.05.

    Office of Legacy Management (LM)

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

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

    10 CFR Part 433, 434, and 435, December 4, 2006 | Department of Energy Interim Final Rule and Request for Comments, Federal Register, 71 FR 70275, 10 CFR Part 433, 434, and 435, December 4, 2006 Interim Final Rule and Request for Comments, Federal Register, 71 FR 70275, 10 CFR Part 433, 434, and 435, December 4, 2006 Document displays the interim final rule and request for comments for Energy Conservation Standards for New Federal Commercial and Multi-Family High-Rise Residential Buildings

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

    SciTech Connect (OSTI)

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

    2007-03-01

    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.

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

    SciTech Connect (OSTI)

    Not Available

    1994-06-01

    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.

  17. Advanced nuclear reactor public opinion project. Interim report

    SciTech Connect (OSTI)

    Benson, B.

    1991-07-25

    This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.

  18. Methane conversion for highway fuel (Methanol Plantship Project), interim report. Resource materials. Report for November 1991-May 1992

    SciTech Connect (OSTI)

    Fink, C.; Jackson, I.; Wright, S.; Booras, P.; Linaweaver, P.

    1997-01-01

    The report presents partial results of a study undertaken to respond to PL 101-516; that law provided funding for `phase II of the development/design work on a floating methanol production plantship to advance work already completed under phase I of the project, which was authorized by section 152 of the Surface Transportation Act of 1982.` Phase I determined the feasibility of producing large volumes of low-cost methanol aboard a plantship. The interim report includes: an examination of the impact of recent permitting, licensing, and environmental regulations on methanol plantship (MPS) design and operation; analysis of other recent MPS design studies and updating of the process technology; and revision and updating of an economic analysis which continues to demonstrate the project`s viability.

  19. 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.

    2011-01-24

    The U.S. Department of Energys 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 (OctoberMarch), and they discharged during the summer period (AprilSeptember). 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.

  20. Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

    SciTech Connect (OSTI)

    Pickett, W.W.

    1998-03-02

    This report outlines the design and total estimated cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW).

  1. Sample results from the interim salt disposition program macrobatch 9 tank 21H qualification samples

    SciTech Connect (OSTI)

    Peters, T. B.

    2015-11-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 9 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H.

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

    SciTech Connect (OSTI)

    Chandler, K.; Walkowicz, K.

    2006-04-01

    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. DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

    SciTech Connect (OSTI)

    T. A. Lee

    2005-09-15

    The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

  4. Interim Transmittal Letter dated July 27 2005 | U.S. DOE Office of Science

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

    (SC) Interim Transmittal Letter dated July 27 2005 High Energy Physics Advisory Panel (HEPAP) HEPAP Home Meetings 2016 HEPAP Membership Charges/Reports Charter .pdf file (44KB) HEP Committees of Visitors Federal Advisory Committees HEP Home Charges/Reports Interim Transmittal Letter dated July 27 2005 Print Text Size: A A A FeedbackShare Page July 27, 2005 Harold T. Shapiro, Chair Sally Dawson, Vice Chair Elementary Particle Physics 2010 Committee The National Academies 500 Fifth Street, NW

  5. Interim Report of the Task Force on DOE National Laboratories | Department

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

    of Energy Interim Report of the Task Force on DOE National Laboratories Interim Report of the Task Force on DOE National Laboratories The SEAB Task Force on DOE National Laboratories was established by the Secretary of Energy on June 16, 2014, to provide advice, guidance, and recommendations on important issues related to improving the health and management of the labs. The Task Force has been charged to review past studies, Congressional reports and direction, and Departmental deliberations

  6. Letter on the Interim Report of the Commission to Review the Effectiveness

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

    of the National Energy Laboratories | Department of Energy Interim Report of the Commission to Review the Effectiveness of the National Energy Laboratories Letter on the Interim Report of the Commission to Review the Effectiveness of the National Energy Laboratories The SEAB Task Force on DOE National Laboratories was established by the Secretary of Energy on June 16, 2014, to provide advice, guidance, and recommendations on important issues related to improving the health and management of

  7. Request for Rehearing and Request for Interim Clarification by David K.

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

    Paylor, Director of the Virginia Department of Environmental Quality | Department of Energy Rehearing and Request for Interim Clarification by David K. Paylor, Director of the Virginia Department of Environmental Quality Request for Rehearing and Request for Interim Clarification by David K. Paylor, Director of the Virginia Department of Environmental Quality Docket No. EO-05-01: Pursuant to Federal Power Act § 313, David K. Paylor, Director of the Virginia Department of Environmental

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

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

    New York City Transit Hybrid and CNG Transit Buses: Interim Evaluation Results K. Chandler and E. Eberts Battelle L. Eudy National Renewable Energy Laboratory Technical Report NREL/TP-540-38843 January 2006 New York City Transit Hybrid and CNG Transit Buses: Interim Evaluation Results K. Chandler and E. Eberts Battelle L. Eudy National Renewable Energy Laboratory Prepared under Task No. FC06.3000 Technical Report NREL/TP-540-38843 January 2006 National Renewable Energy Laboratory 1617 Cole

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

    Energy Savers [EERE]

    Conservation for New Federal Commercial and Multi-Family High-Rise Residential Buildings and New Federal Low-Rise Residential Buildings | Department of Energy NRDC on Department of Energy Interim Final Rule: Energy Conservation for New Federal Commercial and Multi-Family High-Rise Residential Buildings and New Federal Low-Rise Residential Buildings Comments of NRDC on Department of Energy Interim Final Rule: Energy Conservation for New Federal Commercial and Multi-Family High-Rise

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

    SciTech Connect (OSTI)

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

    1997-10-01

    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.

  11. Hazelwood Interim Storage Site environmental report for calendar year 1989, Hazelwood, Missouri

    SciTech Connect (OSTI)

    Not Available

    1990-05-01

    The environmental monitoring program, begun in 1984, was continued during 1989 at the Hazelwood Interim Storage Site (HISS), a US Department of Energy (DOE) facility located in the City of Hazelwood, Missouri. HISS is currently used for storage of soils contaminated with residual radioactive material. HISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where residual radioactive material remains 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 monitoring program at HISS measures radon concentrations in air; external gamma radiation levels; and uranium, radium, and thorium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. To verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and assess its potential effect on public health, the radiation dose was calculated for a hypothetical maximally exposed individual. This report presents the findings of the environmental monitoring conducted at HISS during calendar year 1989. 19 refs., 14 figs., 13 tabs.

  12. Environmental surveillance results for 1995 for the Hazelwood Interim Storage Site

    SciTech Connect (OSTI)

    McCague, J.C.

    1996-06-01

    This memorandum presents and interprets analytical results and measurements obtained as part of the 1995 environmental surveillance program for the Hazelwood Interim Storage Site (HISS) under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The discussion provides a comparative analysis of average historical background conditions and applicable regulatory criteria to the 1995 results reported for external gamma radiation and for samples from the media investigated (air, surface water, sediment, groundwater, and stormwater). Results from the 1995 environmental surveillance program at HISS indicate that, with the exception of thorium-230 in streambed sediment, applicable US Department of Energy (DOE) guidelines were not exceeded for any measured parameter or for any dose calculated for potentially exposed members of the general public. In the absence of sediment guidelines, DOE soil guidelines serve as a standard of comparison for data obtained from stream bed sediment; two samples from downstream locations contained concentrations of thorium-230 that exceeded DOE soil guidelines. All stormwater sample results were in compliance with permit-specified limits. Other radioactive materials include radium 226 and natural uranium.

  13. 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

    2012-12-01

    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.

  14. 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

    2012-09-01

    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.

  15. 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.

    1982-09-01

    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.

  16. 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.

    2013-09-19

    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.

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

    SciTech Connect (OSTI)

    1995-06-01

    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.

  18. Uranium exploration of the Colorado Plateau: interim staff report

    SciTech Connect (OSTI)

    Not Available

    1980-10-01

    This report is an issue of the original draft copy of the Interim Staff Report on Uranium Exploration on the Colorado Plateau, dated June 1951. The original draft copy was only recently located and is being published at this time because of the interest in the contained historical content. The table of contents of this report lists: history of uranium mining; geology; proposed program for the geologic investigations section; general activities of industry and government; and future exploration of sedimentary uranium deposits and anticipated results. Under the proposed program section are: future of the copper-uranium deposits as a source of uranium; uraniferous asphaltite deposits; and commission exploration and future possibilities. The section on general activities of industry and government includes: exploratory and development drilling; field investigations and mapping; early geologic investigations and investigations by the US geological survey; and geophysical exploration. Tables are also presented on: uranium production by districts; US Geological survey drilling statistics; Colorado Exploration Branch drilling statistics; summary of drilling projects; and comparative yearly core-drill statistics on the Colorado Plateau.

  19. Process safety management and interim or remedial action plans

    SciTech Connect (OSTI)

    Boss, M.J.; Henney, D.A.; Heitzman, V.K. [HWS Consulting Group, Inc., Omaha, NE (United States); Day, D.W. [Army Corps of Engineers, Omaha, NE (United States)

    1996-12-31

    Remedial Actions, including Interim Remedial Activities, often require the use of treatment facilities or stabilization techniques using on-site chemical processes. As such, the 29 CFR 1910.119 Process Safety Management (PSM) of Highly Hazardous Chemicals (PSM Standard) and the USEPA regulations for Risk Management Planning require that these chemicals and their attendant potential hazards be identified. A Hazard and Operation (HAZOP) study, Failure Mode and Effect Analysis (FMEA), Fault Tree Analysis, or equivalent graphic presentation of processes must be completed. These studies form a segment of the Process Hazard Analysis (PHA). HAZOP addresses each system and each element of a system that could deviate from normal operations and thus cause a hazard. A full assessment of each process is produced by looking at the hazards, consequences, causes and personnel protection needed. Many variables must be considered when choosing the appropriate PHA technique including the size of the plant, the number of processes, the types of processes, and the types of chemicals used. A mixture of these techniques may be required to adequately transmit information about the process being evaluated.

  20. Safe Advantage on Dry Interim Spent Nuclear Fuel Storage

    SciTech Connect (OSTI)

    Romanato, L.S.

    2008-07-01

    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)

  1. DOUBLE TRACKS Test Site interim corrective action plan

    SciTech Connect (OSTI)

    1996-06-01

    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.

  2. Hazelwood Interim Storage Site annual environmental report for calendar year 1991, Hazelwood, Missouri

    SciTech Connect (OSTI)

    Not Available

    1992-09-01

    This document describes the environmental monitoring program at the Hazelwood Interim Storage Site (HISS) and surrounding area, implementation of the program, and monitoring results for 1991. 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), a DOE program to 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 monitoring program at HISS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and radium-226, thorium-230, and total uranium concentrations in surface water, sediment, and groundwater. Additionally, several nonradiological parameters are measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE orders. Environmental standards and DCGs are established to protect public health and the environment.

  3. Hazelwood interim storage site: Annual site environmental report, Hazelwood, Missouri, Calendar Year 1988

    SciTech Connect (OSTI)

    Not Available

    1989-04-01

    The monitoring program at Hazelwood Interim Storage Site (HISS) measures radon concentrations in air; external gamma radiation levels; and uranium, radium, and thorium, concentrations in surface water, groundwater and sediment. To verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and assess its potential effect or public health, the radiation dose was calculated for a hypothetical maximally exposed individual. Based on the scenario described in this report, this hypothetical individual at HISS would receive an annual external exposure approximately equivalent to 1 percent of the DOE radiation protection standard. This exposure is less than the exposure a person receives during a flight from New York to Los Angeles (because of the greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of HISS that results from radioactive materials present at the site is indistinguishable from the dose that the same population receives from naturally occurring radioactive sources. The results of 1988 monitoring show that HISS is in compliance with the DOE radiation protection standard. 15 refs., 16 figs., 13 tabs.

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

    SciTech Connect (OSTI)

    Not Available

    1994-07-01

    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.

  5. Development of a National M and O Contractor Work Prioritisation Process and its Use as a Progress Measure for Nuclear Clean Up in the United Kingdom

    SciTech Connect (OSTI)

    Waite, R.; Hudson, I.D.; Wareing, M.I.

    2006-07-01

    In July 2004, Her Majesty's Government established a Nuclear Decommissioning Authority (NDA) to assume responsibility for the discharge of the vast majority of the United Kingdom's public sector civil nuclear liabilities. The Energy Act of 2004 outlines in greater detail how the NDA functions, what its responsibilities are, and how these fit into the overall structure of the UK programme for managing and disposing of the liabilities created by a significant element of the UK's early commercial and nuclear weapons activities. The amount of Government funding provided to the NDA will be a key factor in determining what can be achieved. In agreeing how the funds are distributed to the licensed sites, the NDA will need to keep in mind the 'guiding principles' stated in 'Managing the Nuclear Legacy - A Strategy for Action': - Focus on getting the job done to high safety, security and environmental standards; - Best value for money consistent with safety, security and environmental performance; - Openness and transparency. To satisfy these requirements there is a need for a transparent process for justifying and prioritising work that aids decisions about what should be done and when, is straightforward to understand and can be applied by a wide range of stakeholders. To develop such a process, a multi-stakeholder group (the 'Prioritisation Working Group') produced a report published in April 2005 that examined how the process would align with the NDA's overall management processes. It also identified six criteria or 'attributes' that should be taken into account, and a variety of measures, or 'metrics' that could be used to assess each attribute. The report formed the basis of preliminary guidance from NDA to the site licensees that was used to guide their submissions on plans and programmes of work in 2005. Since this report the NDA has been working, with stakeholder input, to develop a prioritisation process to be used during the production of future Life Cycle Baseline (LCBL) and Near Term Work Plan (NTWP) submissions. This paper describes: - The key attributes chosen to address the selection criteria important to various stakeholder groups; - The methodology selected for ranking and weighing the relative importance of each proposed activity; - The linkage between the decision-making processes at the national and site-specific levels with the NDA's annual planning cycles; - The stakeholder engagement activities undertaken to ensure that the process will operate in an open and transparent manner; - The proposed methods by which this process will not only assist in the early selection of the highest priority work, but also will facilitate the annual management of the portfolio of activities being performed at each site; and - The status of actions to institutionalise these processes into the formal procedures for future NDA work planning and progress measurement. Further information can be obtained from the NDA web site www.nda.gov.uk. (authors)

  6. Measurement

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

    ... We created a small library to record the current state of the energy and time counters and then inserted calls ... MiniDFT energy usage was measured separately for the ...

  7. Measurements

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

    Nonlinear Hall-Driven Reconnection in the Reversed Field Pinch by Timothy D. Tharp A dissertation submitted in partial fulfillment of the requirements for the degree of Doctor of Philosophy (Physics) at the University of Wisconsin - Madison 2010 c 2010 Timothy D. Tharp All Rights Reserved i Acknowledgements I would like to acknowledge the many great people in my life who have made this thesis possible. This work was built on the contributions of many previous individuals, including professors,

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

    SciTech Connect (OSTI)

    Bonnema, Bruce Edward

    2001-09-01

    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 Energys Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

  9. 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

    2013-10-24

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

  10. Work Plan

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

    Work Plan NSSAB Members Vote on Work Plan Tasks; The Nevada Site Specific Advisory Board operates on a fiscal year basis and conducts work according to a NSSAB generated and U.S. Department of Energy (DOE) approved work plan. FY 2016 Work Plan Work plan items focus on providing recommendations to the DOE regarding the following subjects: soil contamination from historic atmospheric nuclear testing, remediation of contaminated facilities used to support historic testing, groundwater studies

  11. Hazelwood Interim Storage Site: Annual site environment report, Calendar year 1985

    SciTech Connect (OSTI)

    Not Available

    1986-11-01

    The Hazelwood Interim Storage Site (HISS) is presently used for the storage of low-level radioactively contaminated soils. Monitoring results show that the HISS is in compliance with DOE Derived Concentration Guides (DCGs) and radiation protection standards. During 1985, annual average radon concentrations ranged from 10 to 23% of the DCG. The highest external dose rate at the HISS was 287 mrem/yr. The measured background dose rate for the HISS area is 99 mrem/yr. The highest average annual concentration of uranium in surface water monitored in the vicinity of the HISS was 0.7% of the DOE DCG; for /sup 226/Ra it was 0.3% of the applicable DCG, and for /sup 230/Th it was 1.7%. In groundwater, the highest annual average concentration of uranium was 12% of the DCG; for /sup 226/Ra it was 3.6% of the applicable DCG, and for /sup 230/Th it was 1.8%. While there are no concentration guides for stream sediments, the highest concentration of total uranium was 19 pCi/g, the highest concentration of /sup 226/Ra was 4 pCi/g, and the highest concentration of /sup 230/Th was 300 pCi/g. Radon concentrations, external gamma dose rates, and radionuclide concentrations in groundwater at the site were lower than those measured in 1984; radionuclide concentrations in surface water were roughly equivalent to 1984 levels. For sediments, a meaningful comparison with 1984 concentrations cannot be made since samples were obtained at only two locations and were only analyzed for /sup 230/Th. The calculated radiation dose to the maximally exposed individual at the HISS, considering several exposure pathways, was 5.4 mrem, which is 5% of the radiation protection standard.

  12. Measurement

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

    core velocity fluctuations and the dynamo in a reversed-field pinch * D. J. Den Hartog, †,a) J. T. Chapman, b) D. Craig, G. Fiksel, P. W. Fontana, S. C. Prager, and J. S. Sarff Department of Physics, University of Wisconsin-Madison, 1150 University Avenue, Madison, Wisconsin 53706 ͑Received 16 November 1998; accepted 20 January 1999͒ Plasma flow velocity fluctuations have been directly measured in the high-temperature magnetically confined plasma in the Madison Symmetric Torus ͑MST͒

  13. Final Environmental Impact Statement Safe Interim Storage Of Hanford Tank Wastes

    Office of Environmental Management (EM)

    1995/01eis0212_cl.html[6/27/2011 1:02:59 PM] Final Environmental Impact Statement Safe Interim Storage Of Hanford Tank Wastes DOE/EIS-0212 VOLUME 1 OF 2 VOLUME 1 FINAL ENVIRONMENTAL IMPACT STATEMENT SAFE INTERIM STORAGE OF HANFORD TANK WASTES Hanford Site Richland, Washington October, 1995 WASHINGTON STATE DEPARTMENT OF ECOLOGY NUCLEAR WASTE PROGRAM LACEY, WASHINGTON 98503 U.S. DEPARTMENT OF ENERGY RICHLAND OPERATIONS OFFICE RICHLAND, WASHINGTON 99352 Department of Energy Richland, WA 99352

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

    SciTech Connect (OSTI)

    Harrison, M.

    2011-04-30

    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.

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

    SciTech Connect (OSTI)

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

    2013-08-08

    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.

  16. Remedial Investigation/Feasibility Study Work Plan for the 200-UP-1 Groundwater Operable Unit, Hanford Site, Richland, Washington. Revision

    SciTech Connect (OSTI)

    Not Available

    1994-01-01

    This work plan identifies the objectives, tasks, and schedule for conducting a Remedial Investigation/Feasibility Study for the 200-UP-1 Groundwater Operable Unit in the southern portion of the 200 West Groundwater Aggregate Area of the Hanford Site. The 200-UP-1 Groundwater Operable Unit addresses contamination identified in the aquifer soils and groundwater within its boundary, as determined in the 200 West Groundwater Aggregate Area Management Study Report (AAMSR) (DOE/RL 1992b). The objectives of this work plan are to develop a program to investigate groundwater contaminants in the southern portion of the 200 West Groundwater Aggregate Area that were designated for Limited Field Investigations (LFIs) and to implement Interim Remedial Measures (IRMs) recommended in the 200 West Groundwater AAMSR. The purpose of an LFI is to evaluate high priority groundwater contaminants where existing data are insufficient to determine whether an IRM is warranted and collect sufficient data to justify and implement an IRM, if needed. A Qualitative Risk Assessment (QRA) will be performed as part of the LFI. The purpose of an IRM is to develop and implement activities, such as contaminant source removal and groundwater treatment, that will ameliorate some of the more severe potential risks of groundwater contaminants prior to the RI and baseline Risk Assessment (RA) to be conducted under the Final Remedy Selection (FRS) at a later date. This work plan addresses needs of a Treatability Study to support the design and implementation of an interim remedial action for the Uranium-{sup 99}{Tc}-Nitrate multi-contaminant IRM plume identified beneath U Plant.

  17. Remedial investigation work plan for Bear Creek Valley Operable Unit 1 (S-3 Ponds, Boneyard/Burnyard, Oil Landfarm, Sanitary Landfill 1, and the Burial Grounds, including Oil Retention Ponds 1 and 2) at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 1, Main text

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

    The intent and scope of the work plan are to assemble all data necessary to facilitate selection of remediation alternatives for the sites in Bear Creek Valley Operable Unit 1 (BCV OU 1) such that the risk to human health and the environment is reduced to acceptable levels based on agreements with regulators. The ultimate goal is to develop a final Record Of Decision (ROD) for all of the OUs in BCV, including the integrator OU. However, the initial aim of the source OUs is to develop a ROD for interim measures. For source OUs such as BCV OU 1, data acquisition will not be carried out in a single event, but will be carried out in three stages that accommodate the schedule for developing a ROD for interim measures and the final site-wide ROD. The three stages are as follows: Stage 1, Assemble sufficient data to support decisions such as the need for removal actions, whether to continue with the remedial investigation (RI) process, or whether no further action is required. If the decision is made to continue the RI/FS process, then: Stage 2, Assemble sufficient data to allow for a ROD for interim measures that reduce risks to the human health and the environment. Stage 3, Provide input from the source OU that allows a final ROD to be issued for all OUs in the BCV hydrologic regime. One goal of the RI work plan will be to ensure that sampling operations required for the initial stage are not repeated at later stages. The overall goals of this RI are to define the nature and extent of contamination so that the impact of leachate, surface water runoff, and sediment from the OU I sites on the integrator OU can be evaluated, the risk to human health and the environment can be defined, and the general physical characteristics of the subsurface can be determined such that remedial alternatives can be screened.

  18. Description of work for 200-UP-1 characterization of monitoring wells

    SciTech Connect (OSTI)

    Innis, B.E.; Kelty, G.G.

    1994-02-01

    This description of work (DOW) details the field activities associated with the drilling, soil sampling, and construction of groundwater monitoring and dual-use wells in the 200-UP-1 Operable Unit (Tasks 2, 3, and 5 in the 200-UP-1 RI/FS Work Plan DOE/RL 1993a) and will serve as a field guide for those performing the work. It will be used in conjunction with the Remedial Investigation/Feasibility Study Work Plan for the 200-UP-1 Groundwater operable Unit (DOE-RL 1993a, [LFI]) and Site Characterization Manual (WHC 1988a). Groundwater wells are being constructed to characterize the vertical and horizontal extent of the Uranium and {sup 99}{Tc} plumes and to define aquifer properties such as hydraulic communication between aquifers and hydrostratigraphy. Some of these wells may be utilized for extraction purposes during the IRM phase anticipated at this operable unit and are being designed with a dual use in mind. These data will be used to optimize the Interim Remedial Measures (IRM) for the cleanup of these two plumes. The data will also be used with later Limited Field Investigation (LFI) data to perform a Qualitative Risk Assessment (QRA) for the operable unit. The locations for the proposed groundwater wells are presented in Figure 1. The contaminants of concern for the project are presented ih Table 1.

  19. Hazelwood Interim Storage Site annual site environmental report: Calendar year 1986

    SciTech Connect (OSTI)

    Not Available

    1987-06-01

    During 1986, the environmental monitoring program was continued at the Hazelwood Interim Storage Site (HISS), a US Department of Energy (DOE) facility located in the City of Hazelwood, Missouri. Originally known as the Cotter Corporation site on Latty Avenue in Hazelwood, the HISS is presently used for the storage of soils contaminated with residual radioactive material. As part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Appropriations Act, remedial action and environmental monitoring program are being conducted at the site and at vicinity properties by Bechtel National, Inc., Project Management Contractor for FUSRAP. The monitoring program at the HISS measures radon gas concentrations in air; external gamma radiation levels; and uranium, radium, and thorium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the scenario described in this report, the maximally exposed individual at the HISS would receive an annual external exposure approximately equivalent to 2% of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than the exposure a person would receive during a round-trip flight from New York to Los Angeles. The cumulative dose to the population within an 80-km (50-mi) radius of the HISS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the HISS is in compliance with the DOE radiation protection standard. 11 refs., 6 figs., 10 tabs.

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

    SciTech Connect (OSTI)

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

    2012-12-11

    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.

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

    SciTech Connect (OSTI)

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

    2012-12-20

    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.

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

    SciTech Connect (OSTI)

    CARRELL, R D

    2002-07-16

    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.

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

    SciTech Connect (OSTI)

    Not Available

    1994-05-19

    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.

  4. 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.

    2010-01-01

    DOEs 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.

  5. Working Copy

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

    At DOE Working At DOE Working At DOE Only Here...Will you Define the Future of Energy The people of DOE are engaged in a wide range of challenging and innovative work - from participating in groundbreaking international initiatives like the Global Nuclear Partnership, to solar power demonstration projects, to projects that convert captured carbon dioxide (CO2) emissions from industrial sources into fuel, plastics, and fertilizers. Only here can the diversity of activities throughout our

  6. Synthesis and characterization of metal hydride electrodes. Interim report

    SciTech Connect (OSTI)

    McBreen, J.; Reilly, J.J.

    1995-10-01

    The objective of this project is to elucidate the compositional and structural parameters that affect the thermodynamics, kinetics and stability of alloy hydride electrodes and to use this information in the development of new high capacity long life hydride electrodes for rechargeable batteries. The work focuses on the development of AB{sub 5} alloys and the application of in situ methods, at NSLS, such as x-ray absorption (XAS), to elucidate the role of the alloying elements in hydrogen storage and corrosion inhibition. The most significant results to date are: The decay of electrode capacity on cycling was directly related to alloy corrosion. The rate of corrosion depended in part on both the alloy composition and the partial molar volume of hydrogen, V{sub H}. The corrosion rate depended on the composition of the A component in AB{sub 5} (LaNi{sub 5} type) alloys. Partial substitution of La with Ce in AB{sub 5} alloys substantially inhibits electrode corrosion on cycling. Recent results indicate that Co also greatly inhibits electrode corrosion, possibly by minimizing V{sub H}. The AB{sub 5} alloys investigated included LaNi{sub 5}, ternary alloys (e.g. LaN{sub 4.8}Sn{sub 0.2} and La{sub 0.8}Ce{sub 0.2}Ni{sub 5}), alloys with various substitutions for both La and Ni (e.g. La{sub 0.8}Ce{sub 0.2}Ni{sub 4.8}Sn{sub 0.2}) and mischmetal (Mm) alloys of the type normally used in batteries, such as MmB{sub 5} (B = Ni{sub 3.55}Mn{sub 0.4}A1{sub 0.3}Co{sub 0.75}). A major effort was devoted to the effects of La substitution in the A component. Both in situ and ex situ XAS measurements are used to study the electronic effects that occur on the addition of various metal substitutions and on the ingress of hydrogen.

  7. Memorandum on the Interim Report of the Commission to Review the Effectiveness of the National Energy Laboratories

    Broader source: Energy.gov [DOE]

    SEAB's comments on the findings and recommendations in the interim report of the Congressionally mandated Commission to Review the Effectiveness of the National Energy Laboratories, chaired by T.J. Glauthier and Jared Cohon.

  8. CASL-8-2015-0095-000 L3:THM.CLS.P11.01 Interim Report:

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

    2 1 North Carolina State University 2 University of Notre Dame March 31, 2015 CASL-U-2015-0095-000 Interim Report: ITMDNS for high volume fraction bubbly flow regimes, ...

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

    SciTech Connect (OSTI)

    Daniel S. Wendt; Greg L. Mines

    2010-09-01

    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

  10. Clean Energy Works

    Broader source: Energy.gov [DOE]

    Through Clean Energy Works, homeowners can finance up to $30,000 at a fixed interest rate for home energy efficiency retrofits for a variety of measures. Customers have varying lender and loan op...

  11. 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)

    2013-07-01

    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)

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

    SciTech Connect (OSTI)

    Barnitt, R.

    2010-05-01

    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.

  13. Criticality safety evaluation for long term storage of FFTF fuel in interim storage casks

    SciTech Connect (OSTI)

    Richard, R.F.

    1995-05-11

    It has been postulated that a degradation phenomenon, referred to as ``hot cell rot``, may affect irradiated FFTF mixed plutonium-uranium oxide (MOX) fuel during dry interim storage. ``Hot cell rot`` refers to a variety of phenomena that degrade fuel pin cladding during exposure to air and inert gas environments. It is thought to be a form of caustic stress corrosion cracking or environmentally assisted cracking. Here, a criticality safety analysis was performed to address the effect of the ``hot cell rot`` phenomenon on the long term storage of irradiated FFTF fuel in core component containers. The results show that seven FFTF fuel assemblies or six Ident-69 pin containers stored in core component containers within interim storage casks will remain safely subcritical.

  14. Working Draft

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

    ... relevant crude oil property and other ... The unit is capable of performing vapor pressure measurement... The determined properties could then be utilized for thermal ...

  15. Completion of Level 4 Milestone M4AT-15OR2301039 for the Johnson Noise Thermometry for Drift-free Temperature Measurements Work Package AT-15OR230103

    SciTech Connect (OSTI)

    Britton Jr, Charles L.

    2015-09-14

    This memorandum constitutes our September 2015 level 4 milestone for the project entitled “Johnson Noise Thermometry for Drift-free Temperature Measurements” and satisfies the Milestone/Activity (Conclude HFIR field demonstration of JNT prototype). The progress summary describes the work performed to complete the subject milestone.

  16. Microsoft Word - SEAB Lab Task Force Interim Report Final.docx

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

    Report of the Secretary of Energy Task Force on DOE National Laboratories June 17, 2015 This page intentionally left blank 1 EXECUTIVE SUMMARY This interim report of the Secretary of Energy Advisory Board (SEAB) National Laboratory Task Force (TF) identifies the constraints on and evaluates the effectiveness of laboratory operations that impact the performance and efficiency of the DOE national laboratories. The TF stresses the overriding importance of two actions: clarifying the authorities and

  17. Lakeland Electric SGIG Consumer Behavior Study Interim (Year 1) Evaluation Report (February 2015)

    Broader source: Energy.gov [DOE]

    This interim evaluation report summarizes results from the first year of Lakeland Electric’s two-year 3-Period Time of Use (TOU) program called “Shift-to-Save” (STS). Lakeland Electric has undertaken this study as part of a full system-wide deployment of advanced metering infrastructure funded in part by a grant from the Department of Energy’s Smart Grid Investment Grant (SGIG) Program.

  18. Now Available: Lakeland Electric SGIG Consumer Behavior Study Interim Evaluation Report (February 2015)

    Broader source: Energy.gov [DOE]

    An interim evaluation report summarizing results from the first year of Lakeland Electric’s two-year 3-Period Time of Use (TOU) program called “Shift-to-Save” (STS) is now available. The study is part of a full system-wide deployment of advanced metering infrastructure funded in part by a grant from the Department of Energy’s Smart Grid Investment Grant (SGIG) Program.

  19. FINAL DOE/OR/21950-1016 RESPONSIVENESS SUMMARY= PRAXAIR INTERIM ACTIONS ENGINEERING

    Office of Legacy Management (LM)

    p//l/ * :P/ 142366 _ FINAL DOE/OR/21950-1016 RESPONSIVENESS SUMMARY= PRAXAIR INTERIM ACTIONS ENGINEERING EVALUATION/COST ANALYSIS (EEKA) TONAWANDA, NEW YORK MAY 1996 prepared by U.S. Department of Energy, Oak Ridge Operations Off ice, Formerly Utilized Sites Remedial Action Program with technical assistance from Science Applications International Corporation ESC-FUSRAP under Contract No. DE-AC05-91OR21950 TABLE OF CONTENTS LISTOFTABLES ........................................... iii ACRONYMS AND

  20. Report on interim storage of spent nuclear fuel. Midwestern high-level radioactive waste transportation project

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    The report on interim storage of spent nuclear fuel discusses the technical, regulatory, and economic aspects of spent-fuel storage at nuclear reactors. The report is intended to provide legislators state officials and citizens in the Midwest with information on spent-fuel inventories, current and projected additional storage requirements, licensing, storage technologies, and actions taken by various utilities in the Midwest to augment their capacity to store spent nuclear fuel on site.

  1. Evaluation of tuff as a medium for a nuclear waste repository: interim status report on the properties of tuff

    SciTech Connect (OSTI)

    Johnstone, J.K.; Wolfsberg, K.

    1980-07-01

    This report is the second in a series of summary briefings to the National Academy of Science`s (NAS) Committee on Radioactive Waste Management dealing with feasibility of disposal of heat-producing radioactive waste in silicic tuff. The interim status of studies of tuff properties determined on samples obtained from Yucca Mountain and Rainier Mesa (G-tunnel) located on the Nevada Test Site (NTS) are discussed. In particular, progress is described on resolving issues identified during the first briefing to the NAS which include behavior of water in tuff when heated, the effect of the presence or absence of water and joints on the thermal/physical properties of tuff and the detailed/complex sorptive properties of highly altered and unaltered tuff. Initial correlations of thermal/physical and sorptive properties with the highly variable porosity and mineralogy are described. Three in-situ, at-depth field experiments, one nearly completed and two just getting underway are described. In particular, the current status of mineralogy and petrology, geochemistry, thermal and mechanical, radiation effects and water behavior studies are described. The goals and initial results of a Mine Design Working Group are discussed. Regional factors such as seismicity, volcanism and hydrology are not discussed.

  2. Lessons learned from the Siting Process of an Interim Storage Facility in Spain - 12024

    SciTech Connect (OSTI)

    Lamolla, Meritxell Martell

    2012-07-01

    On 29 December 2009, the Spanish government launched a site selection process to host a centralised interim storage facility for spent fuel and high-level radioactive waste. It was an unprecedented call for voluntarism among Spanish municipalities to site a controversial facility. Two nuclear municipalities, amongst a total of thirteen municipalities from five different regions, presented their candidatures to host the facility in their territories. For two years the government did not make a decision. Only in November 30, 2011, the new government elected on 20 November 2011 officially selected a non-nuclear municipality, Villar de Canas, for hosting this facility. This paper focuses on analysing the factors facilitating and hindering the siting of controversial facilities, in particular the interim storage facility in Spain. It demonstrates that involving all stakeholders in the decision-making process should not be underestimated. In the case of Spain, all regional governments where there were candidate municipalities willing to host the centralised interim storage facility, publicly opposed to the siting of the facility. (author)

  3. Progress and interim results of the INPRO joint study on assessment of INS based on closed nuclear fuel cycle with fast reactors

    SciTech Connect (OSTI)

    Usanov, Vladimir; Raj, Baldev; Vasile, Alfredo

    2007-07-01

    The purpose of the work is to review interim results of the Joint Study on assessment of an Innovative Nuclear System based on a Closed Nuclear Fuel Cycle with Fast Reactors (INS CNFC-FR). This study is a part of the IAEA international project for innovative reactors and fuel cycle technologies (INPRO). Now it is being implemented by Canada, China, France, India, Japan, Republic of Korea, Russia, and Ukraine. A report on results of implementation of the first phase of the Joint Study was presented to the INPRO Steering Committee meeting in December 2006. It was also agreed by the Joint Study participants to reveal these results to broader discussion at scientific conferences and meetings. The authors' interpretation of the Joint Study findings and issues is presented in the paper. (authors)

  4. Evaluation of higher distribution and/or utilization voltages. Second interim report (March 1979): identification of components and parameters for cost and energy-efficiency analysis

    SciTech Connect (OSTI)

    Not Available

    1981-04-01

    This interim report provides documentation on the second task, Identification of Components and Parameters for Cost and Energy-Efficiency Analysis, of DOE Contract No. ET-78-C-01-2866, Evaluation of Higher Distribution and/or Utilization Voltages. The work performed under this task includes an identification of the elements of the distribution/utilization system, a characterization of the distribution elements and a characterization of end use elements. The purpose of this task is to identify the distribution and utilization system elements which will be subjected to a detailed analysis and computer modeling in later tasks. The elements identified are characterized in terms of their interface with other elements in the system and with respect to their energy consumption, efficiency, and costs. A major output of this task is a list of elements to be modeled under Task 3 and a set of specifications for the computer model to be developed under that task.

  5. Dynamic underground stripping demonstration project. Interim engineering report

    SciTech Connect (OSTI)

    Newmark, R.L.

    1992-04-01

    LLNL is collaborating with the UC Berkeley College of Engineering to develop and demonstrate a system of thermal remediation techniques for rapid cleanup of localized underground spills. Called dynamic stripping to reflect the rapid and controllable nature of the process, it will combine steam injection, direct electrical heating, and tomographic geophysical imaging in a cleanup of the LLNL gasoline spill. In the first eight months of the project, a Clean Site engineering test was conducted to prove the field application of the techniques. Tests then began on the contaminated site in FY 1992. This report describes the work at the Clean Site, including design and performance criteria, test results, interpretations, and conclusions. We fielded `a wide range of new designs and techniques, some successful and some not. In this document, we focus on results and performance, lessons learned, and design and operational changes recommended for work at the contaminated site. Each section focuses on a different aspect of the work and can be considered a self-contained contribution.

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

    SciTech Connect (OSTI)

    Not Available

    1994-10-21

    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.

  7. Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), and Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants

    SciTech Connect (OSTI)

    Mays, Gary T; Belles, Randy; Cetiner, Sacit M; Howard, Rob L; Liu, Cheng; Mueller, Don; Omitaomu, Olufemi A; Peterson, Steven K; Scaglione, John M

    2012-06-01

    The objective of this siting study work is to support DOE in evaluating integrated advanced nuclear plant and ISFSI deployment options in the future. This study looks at several nuclear power plant growth scenarios that consider the locations of existing and planned commercial nuclear power plants integrated with the establishment of consolidated interim spent fuel storage installations (ISFSIs). This research project is aimed at providing methodologies, information, and insights that inform the process for determining and optimizing candidate areas for new advanced nuclear power generation plants and consolidated ISFSIs to meet projected US electric power demands for the future.

  8. The Kelastic variable wall mining machine. Interim final report

    SciTech Connect (OSTI)

    1995-11-12

    This machine cuts coal along a longwall face extending up to 500 feet by a rotating auger with bits. The machine also transports the coal that is cut acting as screw conveyor. By virtue of an integral shroud comprising part of the conveyor the machine is also amenable to a separation of the zones where men work from air being contaminated by dust and methane gas by the cutting action. Beginning as single intake air courses, the air separates at the working section where one split provides fresh air to the Occupied Zone (OZ) for human needs and the other split purges and carries away dust and methane from face fragmentation in the Cutting Zone (CZ). The attractiveness of the Variable Wall Mining Machine is that it addresses the limitations of current longwall mining equipment: it can consistently out-produce continuous mining machines and most longwall shearing machines. It also is amenable to configuring an environment, the dual-duct system, where the air for human breathing is separated from dust-laden ventilating air with methane mixtures. The objective of the research was to perform a mathematical and experimental study of the interrelationships of the components of the system so that a computer model could demonstrate the workings of the system in an animation program. The analysis resulted in the compilation of the parameters for three different configurations of a dual aircourse system of ventilating underground mines. In addressing the goal of an inherently safe mining system the dual-duct adaptation to the Variable Wall Mining Machine appears to offer the path to solution. The respirable dust problem is solvable; the explosive dust problem is nearly solvable; and the explosive methane problem can be greatly reduced. If installed in a highly gassy mine, the dual duct models would also be considerably less costly.

  9. 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

    1999-11-15

    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.

  10. T-TY Tank Farm Interim Surface Barrier DemonstrationVadose Zone Monitoring Plan

    SciTech Connect (OSTI)

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

    2010-09-27

    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 Energys 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.

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

    SciTech Connect (OSTI)

    Not Available

    1993-12-01

    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.

  12. Formerly Utilized Sites Remedial Action Program (FUSRAP) Hazelwood Interim Storage Site annual site environmental report. Calendar year 1985. [FUSRAP

    SciTech Connect (OSTI)

    Not Available

    1986-04-01

    The Hazelwood Interim Storage Site (HISS) is presently used for the storage of low-level radioactively contaminated soils. Monitoring results show that the HISS is in compliance with DOE concentration guides and radiation protection standards. Derived Concentration Guides (DCGs) represent the concentrations of radionuclides in air or water that would limit the radiation dose to 100 mrem/y. The applicable limits have been revised since the 1984 environmental monitoring report was published. The limits applied in 1984 were based on a radiation protection standard of 500 mrem/y; the limits applied for 1985 are based on a standard of 100 mrem/y. The HISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where low-level radioactive contamination remains from the early years of the nation's atomic energy program. To determine whether the site is in compliance with DOE standards, environmental measurements are expressed as percentages of the applicable DCG, while the calculated doses to the public are expressed as percentages of the applicable radiation protection standard. The monitoring program at the HISS measures uranium, radium, and thorium concentrations in surface water, groundwater, and sediment; radon gas concentrations in air; and external gamma radiation exposure rates. Potential radiation doses to the public are also calculated. The HISS was designated for remedial action under FUSRAP because radioactivity above applicable limits was found to exist at the site and its vicinity. Elevated levels of radiation still exist in areas where remedial action has not yet been completed.

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

    SciTech Connect (OSTI)

    Szojka, S.

    1995-06-01

    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.

  14. 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.

    1994-09-15

    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.

  15. 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

    2011-01-13

    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.

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

    SciTech Connect (OSTI)

    1995-11-17

    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.

  17. Lead-based paint: Interim guidelines for hazard identification and abatement in public and Indian housing

    SciTech Connect (OSTI)

    Not Available

    1990-09-01

    The interim Guidelines provide information on the need for and appropriate methods of identifying and abating lead-based paint (LBP) in the Department of Housing and Urban Development's (HUD's) Public and Indian Housing program. It should be noted that these are interim Guidelines and are subject to change as new information becomes available. All requirements for Public Housing Authorities (PHAs) are considered to apply to Indian Housing Authorities (IHAs), except where specifically excluded by statute. Thus, these Guidelines apply to PHAs and IHAs inclusively. These Guidelines have been prepared by a panel of distinguished experts in the field of LBP and are an outgrowth of the National Institute of Building Sciences (NIBS) effort, which developed the first draft of these guidelines under contract to HUD. These Guidelines represent the first national compilation of technical protocols, practices, and procedures on testing, abatement, worker protection, clean-up, and disposal of LBP in residential structures. These Guidelines should be used in conjunction with the requirements of any State or local codes and regulations which may apply to the specific project under consideration.

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

    Energy Savers [EERE]

    U.S. Department of Energy |June 2015 Interim Report on Impacts from the Consumer Behavior Studies | Page ii Table of Contents Executive Summary .............................................................................................................. iv 1. Introduction ................................................................................................................... 1 1.1 Background about Time-Based Rates and Advanced Metering Infrastructure ............ 1 1.2 Overview of

  19. Peak Underground Working Natural Gas Storage Capacity

    Gasoline and Diesel Fuel Update (EIA)

    of capacity that may understate the amount that can actually be stored. Working Gas Design Capacity: This measure estimates a natural gas facility's working gas capacity, as...

  20. 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.

    2009-10-27

    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.

  1. Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996

    SciTech Connect (OSTI)

    1997-05-06

    OAK A271 Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996. The Rockwell International Hot Laboratory (RIHL) is one of a number of former nuclear facilities undergoing decontamination and decommissioning (D&D) at the Santa Susana Field Laboratory (SSFL). The RIHL facility is in the later stages of dismantlement, with the final objective of returning the site location to its original natural state. This report documents the decontamination and dismantlement activities performed at the facility over the time period 1988 through 1996. At this time, the support buildings, all equipment associated with the facility, and the entire above-ground structure of the primary facility building (Building 020) have been removed. The basement portion of this building and the outside yard areas (primarily asphalt and soil) are scheduled for D&D activities beginning in 1997.

  2. 40 CFR 265 interim-status ground-water monitoring plan for the 2101-M pond

    SciTech Connect (OSTI)

    Chamness, M.A.; Luttrell, S.P.; Dudziak, S.

    1989-03-01

    This report outlines a ground-water monitoring plan for the 2101-M pond, located in the southwestern part of the 200-East Area on the Hanford Site in south-central Washington State. It has been determined that hazardous materials may have been discharged to the pond. Installation of an interim-status ground-water monitoring system is required under the Resource Conservation and Recovery Act to determine if hazardous chemicals are moving out of the pond. This plan describes the location of new wells for the monitoring system, how the wells are to be completed, the data to be collected, and how those data can be used to determine the source and extent of any ground-water contamination from the 2101-M pond. Four new wells are planned, one upgradient and three downgradient. 35 refs., 12 figs., 9 tabs.

  3. Design requirements document for Project W-465, immobilized low-activity waste interim storage

    SciTech Connect (OSTI)

    Burbank, D.A.

    1998-05-19

    The scope of this Design Requirements Document (DRD) is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste (ILAW) produced by the privatized Tank Waste Remediation System (TWRS) treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the TWRS ILAW Interim Storage facility project and provides traceability from the program level requirements to the project design activity. Technical and programmatic risk associated with the TWRS planning basis are discussed in the Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The design requirements provided in this document will be augmented by additional detailed design data documented by the project.

  4. The design of a Phase I non site-specific Centralized Interim Storage Facility

    SciTech Connect (OSTI)

    Stringer, J.; Kane, D.

    1997-10-28

    The Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) recently completed a Topical Safety Analysis Report (TSAR) for a Phase 1 non site specific Centralized Interim Storage Facility (CISF). The TSAR will be used in licensing the CISF when and if a site is designated. The combined Phase 1 and Phase 2 CISF will provide federal storage capability for 40,000 metric tons of uranium (MTU) Spent Nuclear Fuel (SNF) under the oversight of the DOE. The Phase 1 TSAR was submitted to the NRC on May 1, 1997 and is currently under review having been docketed on June 10, 1997. This paper generally describes the Phase 1 CISF design and its operations as presented in the CISF TSAR.

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

    SciTech Connect (OSTI)

    Vigil-Holterman, Luciana R.

    2012-05-07

    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.

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

    SciTech Connect (OSTI)

    TEDESCHI AR

    2008-08-11

    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.

  7. Considerations of the effects of high winds on a low-level radioactive interim storage pile

    SciTech Connect (OSTI)

    Smith, D.E. )

    1991-11-01

    On Wednesday, March 27, 1991, the St. Louis area experienced high winds that damaged a synthetic cover of a low-level radioactive waste storage pile at the US Department of Energy's (DOE's) Hazelwood Interim Storage Site (HISS) in Hazelwood, Missouri. Winds in the St. Louis area at the time of the incident were reported to be 35 mi/h with gusts up to 50 mi/h. Tornado warnings were in effect at the time. The purpose of this summary is to analyze the effects of uplift forces on a synthetic pile cover because of high winds. Consideration is given to anchoring the synthetic cover, type and placement of ballast on the pile, and the type of synthetic membranes best suited to this application. Discussion also includes the emergency procedures used in responding to the incident.

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

    SciTech Connect (OSTI)

    Schilperoort, Daryl L.; Faulk, Darrin

    2013-07-01

    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)

  9. Contaminant transport in unconfined aquifer, input to low-level tank waste interim performance assessment

    SciTech Connect (OSTI)

    Lu, A.H., Westinghouse Hanford

    1996-08-14

    This report describes briefly the Hanford sitewide groundwater model and its application to the Low-Level Tank Waste Disposal (LLTWD) interim Performance Assessment (PA). The Well Intercept Factor (WIF) or dilution factor from a given areal flux entering the aquifer released from the LLTWD site are calculated for base case and various sensitivity cases. In conjunction with the calculation for released fluxes through vadose zone transport,the dose at the compliance point can be obtained by a simple multiplication. The relative dose contribution from the upstream sources was also calculated and presented in the appendix for an equal areal flux at the LLTWD site. The results provide input for management decisions on remediation action needed for reduction of the released fluxes from the upstream facilities to the allowed level to meet the required dose criteria.

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

    SciTech Connect (OSTI)

    TEDESCHI AR

    2008-08-11

    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.

  11. Verification of maximum impact force for interim storage cask for the Fast Flux Testing Facility

    SciTech Connect (OSTI)

    Chen, W.W.; Chang, S.J.

    1996-06-01

    The objective of this paper is to perform an impact analysis of the Interim Storage Cask (ISC) of the Fast Flux Test Facility (FFTF) for a 4-ft end drop. The ISC is a concrete cask used to store spent nuclear fuels. The analysis is to justify the impact force calculated by General Atomics (General Atomics, 1994) using the ILMOD computer code. ILMOD determines the maximum force developed by the concrete crushing which occurs when the drop energy has been absorbed. The maximum force, multiplied by the dynamic load factor (DLF), was used to determine the maximum g-level on the cask during a 4-ft end drop accident onto the heavily reinforced FFTF Reactor Service Building`s concrete surface. For the analysis, this surface was assumed to be unyielding and the cask absorbed all the drop energy. This conservative assumption simplified the modeling used to qualify the cask`s structural integrity for this accident condition.

  12. 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.

    2013-09-01

    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.

  13. Engineering evaluation/cost analysis-environmental assessment for the proposed decontamination of properties in the vicinity of the Hazelwood Interim Storage Site, Hazelwood, Missouri

    SciTech Connect (OSTI)

    Picel, M.H.; Peterson, J.M. . Environmental Assessment and Information Sciences Div.); Williams, M.J. )

    1992-03-01

    The US Department of Energy (DOE), under its Formerly Utilized Sites Remedial Action Program (FUSRAP), is implementing a cleanup program for three groups of properties in the St. Louis, Missouri, area. None of the properties is owned by DOE, but each property contains radioactive residues from federal uranium-processing activities conducted at the SLDS during and after World War II. This engineering evaluation/cost analysis (EE/CA) report has been prepared to support the interim cleanup measures for the contaminated properties in the Hazelwood and Berkeley, Missouri area. The near-term cleanup measures that may be necessary at the vicinity properties are evaluated in the main body of this report. Because of the range of active land uses in the Hazelwood and Berkeley areas and because of the extent of contamination on public and private properties, the potential exists for disturbance and spreading of soil contamination. Specifically, implementation of the proposed action would allow DOE to remove, transport, and safely store contaminated soils from properties where other activities (not involving DOE) are likely to result in either spreading contamination or otherwise complicating ultimate cleanup measures.

  14. Engineering evaluation/cost analysis for the proposed decontamination of properties in the vicinity of the Hazelwood Interim Storage Site, Hazelwood, Missouri -- environment assessment

    SciTech Connect (OSTI)

    Picel, M.H.; Peterson, J.M. . Environmental Assessment and Information Sciences Div.); Williams, M.J. )

    1991-05-01

    The US Department of Energy (DOE), under its Formerly Utilized Sites Remedial Action Program (FUSRAP), is implementing a cleanup program for three groups of properties in the St. Louis, Missouri, area. None of the properties is owned by DOE, but each property contains radioactive residues from federal uranium-processing activities conducted at the SLDS during and after World War II. This engineering evaluation/cost analysis (EE/CA) report has been prepared to support the interim cleanup measures for the contaminated properties in the Hazelwood and Berkeley, Missouri area. The near-term cleanup measures that may be necessary at the vicinity properties are evaluated in the main body of this report. Because of the range of active land uses in the Hazelwood and Berkeley areas and because of the extent of contamination on public and private properties, the potential exists for disturbance and spreading of soil contamination. Specifically, implementation of the proposed action would allow DOE to remove, transport, and safely store contaminated soils from properties where other activities (not involving DOE) are likely to result in either spreading contamination or otherwise complicating ultimate cleanup measures. 25 refs., 4 figs., 6 tabs.

  15. Engineering evaluation/cost analysis-environmental assessment for the proposed decontamination of properties in the vicinity of the Hazelwood Interim Storage Site, Hazelwood, Missouri. Revision 1

    SciTech Connect (OSTI)

    Picel, M.H.; Peterson, J.M.; Williams, M.J.

    1992-03-01

    The US Department of Energy (DOE), under its Formerly Utilized Sites Remedial Action Program (FUSRAP), is implementing a cleanup program for three groups of properties in the St. Louis, Missouri, area. None of the properties is owned by DOE, but each property contains radioactive residues from federal uranium-processing activities conducted at the SLDS during and after World War II. This engineering evaluation/cost analysis (EE/CA) report has been prepared to support the interim cleanup measures for the contaminated properties in the Hazelwood and Berkeley, Missouri area. The near-term cleanup measures that may be necessary at the vicinity properties are evaluated in the main body of this report. Because of the range of active land uses in the Hazelwood and Berkeley areas and because of the extent of contamination on public and private properties, the potential exists for disturbance and spreading of soil contamination. Specifically, implementation of the proposed action would allow DOE to remove, transport, and safely store contaminated soils from properties where other activities (not involving DOE) are likely to result in either spreading contamination or otherwise complicating ultimate cleanup measures.

  16. Deep Vadose Zone Treatability Test for the Hanford Central Plateau. Interim Post-Desiccation Monitoring Results, Fiscal Year 2015

    SciTech Connect (OSTI)

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

    2015-09-01

    A field test of desiccation is being conducted as an element of the Deep Vadose Zone Treatability Test Program. 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 4 years of post-desiccation monitoring data. The DOE field test plan proscribes a total of 5 years of post-desiccation monitoring.

  17. 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.

    2008-07-11

    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.

  18. Evapotranspiration Cover for the 92-Acre Area Retired Mixed Waste Pits:Interim CQA Report

    SciTech Connect (OSTI)

    The Delphi Groupe, Inc., and J. A. Cesare and Associates, Inc.

    2011-06-20

    This Interim Construction Quality Assurance (CQA) Report is for the 92-Acre Evapotranspiration Cover, Area 5 Waste Management Division (WMD) Retired Mixed Waste Pits, Nevada National Security Site, Nevada for the period of January 20, 2011 to May 12, 2011. This Interim Construction Quality Assurance (CQA) Report is for the 92-Acre Evapotranspiration Cover, Area 5 Waste Management Division (WMD) Retired Mixed Waste Pits, Nevada National Security Site, Nevada for the period of January 20, 2011 to May 12, 2011. Construction was approved by the Nevada Division of Environmental Protection (NDEP) under the Approval of Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) for Corrective Action Unit (CAU) 111: Area 5 WMD Retired Mixed Waste Pits, Nevada National Security Site, Nevada, on January 6, 2011, pursuant to Subpart XII.8a of the Federal Facility Agreement and Consent Order. The project is located in Area 5 of the Radioactive Waste Management Complex (RWMC) at the Nevada National Security Site (NNSS), formerly known as the Nevada Test Site, located in southern Nevada, approximately 65 miles northwest of Las Vegas, Nevada, in Nye County. The project site, in Area 5, is located in a topographically closed basin approximately 14 additional miles north of Mercury Nevada, in the north-central part of Frenchman Flat. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. The 92-Acre Area encompasses the southern portion of the Area 5 RWMS, which has been designated for the first final closure operations. This area contains 13 Greater Confinement Disposal (GCD) boreholes, 16 narrow trenches, and 9 broader pits. With the exception of two active pits (P03 and P06), all trenches and pits in the 92-Acre Area had operational covers approximately 2.4 meters thick, at a minimum, in most areas when this project began. The units within the 92-Acre Area are grouped into the following six informal categories based on physical location, waste types and regulatory requirements: (1) Pit 3 Mixed Waste Disposal Unit (MWDU); (2) Corrective Action Unit (CAU) 111; (3) CAU 207; (4) Low-level waste disposal units; (5) Asbestiform low-level waste disposal units; and (6) One transuranic (TRU) waste trench.

  19. BWR Spent Nuclear Fuel Integrity Research and Development Survey for UKABWR Spent Fuel Interim Storage

    SciTech Connect (OSTI)

    Bevard, Bruce Balkcom; Mertyurek, Ugur; Belles, Randy; Scaglione, John M.

    2015-10-01

    The objective of this report is to identify issues and support documentation and identify and detail existing research on spent fuel dry storage; provide information to support potential R&D for the UKABWR (United Kingdom Advanced Boiling Water Reactor) Spent Fuel Interim Storage (SFIS) Pre-Construction Safety Report; and support development of answers to questions developed by the regulator. Where there are gaps or insufficient data, Oak Ridge National Laboratory (ORNL) has summarized the research planned to provide the necessary data along with the schedule for the research, if known. Spent nuclear fuel (SNF) from nuclear power plants has historically been stored on site (wet) in spent fuel pools pending ultimate disposition. Nuclear power users (countries, utilities, vendors) are developing a suite of options and set of supporting analyses that will enable future informed choices about how best to manage these materials. As part of that effort, they are beginning to lay the groundwork for implementing longer-term interim storage of the SNF and the Greater Than Class C (CTCC) waste (dry). Deploying dry storage will require a number of technical issues to be addressed. For the past 4-5 years, ORNL has been supporting the U.S. Department of Energy (DOE) in identifying these key technical issues, managing the collection of data to be used in issue resolution, and identifying gaps in the needed data. During this effort, ORNL subject matter experts (SMEs) have become expert in understanding what information is publicly available and what gaps in data remain. To ensure the safety of the spent fuel under normal and frequent conditions of wet and subsequent dry storage, intact fuel must be shown to: 1.Maintain fuel cladding integrity; 2.Maintain its geometry for cooling, shielding, and subcriticality; 3.Maintain retrievability, and damaged fuel with pinhole or hairline cracks must be shown not to degrade further. Where PWR (pressurized water reactor) information is utilized or referenced, justification has been provided as to why the data can be utilized for BWR fuel.

  20. How it works

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

    How it works MINERvA is a particle physics experiment, located at Fermi National Accelerator Laboratory in Batavia, Illinois. MINERvA was designed to perform high-precision measurements of neutrino interactions on a wide variety of materials, including water, helium, carbon, iron, lead, and plastic. MINERvA is located 100 meters underground, and sits directly in front of the MINOS near detector. The source of MINERvA's neutrino beam is the Neutrinos at the Main Injector beamline, or NuMI. NuMI

  1. 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.

    2010-11-01

    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.

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

    SciTech Connect (OSTI)

    Shizuo Tsurumaki; Hiroyuki Watanabe; Akira Tateishi; Kenichi Horikoshi; Shunichi Suzuki

    2002-07-01

    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)

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

    SciTech Connect (OSTI)

    Hadley, Stanton W; Key, Thomas S

    2009-03-01

    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.

  4. Evaluation of groundwater flow and transport at the Shoal underground nuclear test: An interim report

    SciTech Connect (OSTI)

    Pohll, G.; Chapman, J.; Hassan, A.; Papelis, C.; Andricevic, R.; Shirley, C.

    1998-07-01

    Since 1962, all United States nuclear tests have been conducted underground. A consequence of this testing has been the deposition of large amounts of radioactive materials in the subsurface, sometimes in direct contact with groundwater. The majority of this testing occurred on the Nevada Test Site, but a limited number of experiments were conducted in other locations. One of these is the subject of this report, the Project Shoal Area (PSA), located about 50 km southeast of Fallon, Nevada. The Shoal test consisted of a 12-kiloton-yield nuclear detonation which occurred on October 26, 1963. Project Shoal was part of studies to enhance seismic detection of underground nuclear tests, in particular, in active earthquake areas. Characterization of groundwater contamination at the Project Shoal Area is being conducted by the US Department of Energy (DOE) under the Federal Facility Agreement and Consent Order (FFACO) with the State of Nevada Department of Environmental Protection and the US Department of Defense (DOD). This order prescribes a Corrective Action Strategy (Appendix VI), which, as applied to underground nuclear tests, involves preparing a Corrective Action Investigation Plan (CAIP), Corrective Action Decision Document (CADD), Corrective Action Plan, and Closure Report. The scope of the CAIP is flow and transport modeling to establish contaminant boundaries that are protective of human health and the environment. This interim report describes the current status of the flow and transport modeling for the PSA.

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

    SciTech Connect (OSTI)

    Not Available

    1993-05-01

    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.

  6. OVERVIEW OF CRITERIA FOR INTERIM WET & DRY STORAGE OF RESEARCH REACTOR SPENT NUCLEAR FUEL

    SciTech Connect (OSTI)

    Sindelar, R.; Vinson, D.; Iyer, N.; Fisher, D.

    2010-11-03

    Following discharge from research reactors, spent nuclear fuel may be stored 'wet' in water pools or basins, or it may be stored 'dry' in various configurations including non-sealed or sealed containers until retrieved for ultimate disposition. Interim safe storage practices are based on avoiding degradation to the fuel that would impact functions related to safety. Recommended practices including environmental controls with technical bases, are outlined for wet storage and dry storage of aluminum-clad, aluminum-based research reactor fuel. For wet storage, water quality must be maintained to minimize corrosion degradation of aluminum fuel. For dry storage, vented canister storage of aluminum fuel readily provides a safe storage configuration. For sealed dry storage, drying must be performed so as to minimize water that would cause additional corrosion and hydrogen generation. Consideration must also be given to the potential for radiolytically-generated hydrogen from the bound water in the attendant oxyhydroxides on aluminum fuel from reactor operation for dry storage systems.

  7. Interim Report of the Commission to Review the Effectiveness of the National Energy Laboratories

    SciTech Connect (OSTI)

    Cohon, Jared L.; Glauthier, T. J.; Augustine, Norman R.; Austin, Wanda M.; Elachi, Charles; Fleury, Paul A.; Hockfield, Susan J.; Meserve, Richard A.; Murray, Cherry A.

    2015-02-27

    The Commission to Review the Effectiveness of the National Energy Laboratories was charged by Congress in January 2014 to evaluate the mission, capabilities, size, performance, governance, and agency oversight of the 17 Department of Energy (DOE) laboratories. Given the incredibly broad scope and aggressive timeline (the original deadline was February 2015), the Secretary of Energy and Congress agreed to split the task into two phases. This interim report contains the preliminary observations and recommendations gleaned from Phase 1 of the study, which consisted of a literature review; visits to five of the National Laboratories; semi-structured interviews with staff from across the National Laboratories, DOE, other Federal agencies, companies, other non-governmental organizations, and additional interested parties; and presentations at monthly public Commission meetings. The Commission notes that the purpose of the National Laboratories is to provide critical capabilities and facilities in service of DOE’s mission and the needs of the broader national and international science and technology (S&T) community, including other Federal agencies, academia, and private industry. The National Laboratories are successfully fulfilling that mission today. While the Commission believes significant improvements can be made to many aspects of DOE management and governance of the laboratories, those issues do not detract from the National Laboratories’ remarkable contributions to the American public. In Phase 2 the Commission will focus on ways to make the process of carrying out their missions more efficient and effective.

  8. Environmental monitoring plan for the Niagara Falls Storage Site and the Interim Waste Containment Facility

    SciTech Connect (OSTI)

    Not Available

    1986-04-01

    As part of the US Department of Energy's (DOE) Surplus Facility Management Program (SFMP), the Niagara Falls Storage Site (NFSS) is undergoing remedial action. Vicinity properties adjacent to and near the site are being cleaned up as part of DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP). These programs are a DOE effort to clean up low-level radioactive waste resulting from the early days of the nation's atomic energy program. Radioactively contaminated waste from these remedial action activities are being stored at the NFSS in an interim waste containment facility (IWCF). When the remedial actions and IWCF are completed in 1986, activities at the site will be limited to waste management. The monitoring program was prepared in accordance with DOE Order 5484.1 and is designed to determine the contribution of radioactivity from the site to the environs and to demonstrate compliance with applicable criteria. Major elements of this program will also supplement other monitoring requirements including the performance monitoring system for the IWCF and the closure/post-closure plan. Emphasis will be directed toward the sampling and analysis of groundwater, surface water, air and sediment for parameters which are known to be present in the material stored at the site. The monitoring program will employ a phased approach whereby the first 5 years of data will be evaluated, and the program will be reviewed and modified as necessary. 17 refs., 10 figs., 3 tabs.

  9. Hazelwood Interim Storage Site annual environmental report for calendar year 1990, Hazelwood, Missouri

    SciTech Connect (OSTI)

    Not Available

    1991-08-01

    Environmental monitoring of the US Department of Energy's (DOE) Hazelwood Interim Storage Site (HISS) and surrounding area began in 1984. This document describes the environmental monitoring program, the program's implementation, and the monitoring results for 1990. HISS was assigned to DOE as part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Appropriations Act. DOE placed responsibility for HISS under the Formerly Utilized Sites Remedial Action Program, a DOE program to 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. Environmental monitoring programs have been established at DOE-managed sites to confirm adherence to DOE environmental protection policies; to monitor the potential effects of site operations on human health and the environment; and to ensure compliance with legal and regulatory requirements imposed by federal, state, and local agencies. Environmental monitoring programs are developed and implemented on a site-specific basis to reflect facility characteristics, applicable regulations, hazard potential, quantities and concentrations of materials released, extent and use of affected land and water, and local public interest or concern.

  10. SAMPLE RESULTS FROM THE INTERIM SALT DISPOSITION PROGRAM MACROBATCH 8 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect (OSTI)

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

    2015-01-13

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 8 for the Interim Salt Disposition Program (ISDP). An Actinide Removal Process (ARP) and several Extraction-Scrub- Strip (ESS) tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP and the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). No issues with the projected Salt Batch 8 strategy are identified. A demonstration of the monosodium titanate (MST) (0.2 g/L) removal of strontium and actinides provided acceptable average decontamination factors for plutonium of 2.62 (4 hour) and 2.90 (8 hour); and average strontium decontamination factors of 21.7 (4 hour) and 21.3 (8 hour). These values are consistent with results from previous salt batch ARP tests. The two ESS tests also showed acceptable performance with extraction distribution ratios (D{sub (Cs)}) values of 52.5 and 50.4 for the Next Generation Solvent (NGS) blend (from MCU) and NGS (lab prepared), respectively. These values are consistent with results from previous salt batch ESS tests. Even though the performance is acceptable, SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed in order to improve our predictive capabilities for the ESS tests.

  11. 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.

    1989-01-01

    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).

  12. Improved NLDAS-2 Noah-simulated Hydrometeorological Products with an Interim Run

    SciTech Connect (OSTI)

    Xia, Youlong; Peter-Lidard, Christa; Huang, Maoyi; Wei, Helin; Ek, Michael

    2015-02-28

    In NLDAS-2 Noah simulation, the NLDAS team introduced an intermediate fix suggested by Slater et al. (2007) and Livneh et al. (2010) to reduce large sublimation. The fix is used to constraint surface exchange coefficient (CH) using CH =CHoriginal x max (1.0-RiB/0.5, 0.05) when atmospheric boundary layer is stable. RiB is Richardson number. In NLDAS-2 Noah version, this fix was used for all stable cases including snow-free grid cells. In this study, we simply applied this fix to the grid cells in which both stable atmospheric boundary layer and snow exist simultaneously excluding the snow-free grid cells as we recognize that the fix constraint in NLDAS-2 is too strong. We make a 31-year (1979-2009) Noah NLDAS-2 interim (NoahI) run. We use observed streamflow, evapotranspiration, land surface temperature, soil temperature, and ground heat flux to evaluate the results simulated from NoahI and make the reasonable comparison with those simulated from NLDAS-2 Noah (Xia et al., 2012). The results show that NoahI has the same performance as Noah does for snow water equivalent simulation. However, NoahI significantly improved the other hydrometeorological products simulation as described above when compared to Noah and the observations. This simple modification is being installed to the next Noah version. The hydrometeorological products simulated from NoahI will be staged on NCEP public server for the public in future.

  13. Interagency Working Groups

    Broader source: Energy.gov [DOE]

    The Federal Energy Management Program (FEMP) works closely with agencies and partner organizations to coordinate interagency working groups

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

    SciTech Connect (OSTI)

    Staunton, R.H.

    2004-08-11

    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.

  15. Preparation of waste analysis plans under the Resource Conservation and Recovery Act (Interim guidance)

    SciTech Connect (OSTI)

    Not Available

    1993-03-01

    This document is organized to coincide with the suggested structure of the actual Waste Analysis Plans (WAP) discussed in the previous section. The contents of the remaining eleven chapters and appendices that comprise this document are described below: Chapter 2 addresses waste streams, test parameters, and rationale for sampling and analytical method selection; test methods for analyzing parameters; proceduresfor collecting representative samples; and frequency of sample collection and analyses. These are the core WAP requirements. Chapter 3 addresses analysis requirements for waste received from off site. Chapter 4addresses additional requirements for ignitable, reactive, or incompatible wastes. Chapter 5 addresses unit-specific requirements. Chapter 6 addresses special procedures for radioactive mixed waste. Chapter 7 addresses wastes subject to the land disposal restrictions. Chapter 8 addresses QA/QC procedures. Chapter 9 compares the waste analysis requirements of an interim status facility with those of a permitted facility. Chapter 10 describes the petition process required for sampling and analytical procedures to deviate from accepted methods, such as those identified in promulgated regulations. Chapter 11 reviews the process for modification of WAPs as waste type or handling practices change at a RCRA permitted TSDF. Chapter 12 is the list of references that were used in the preparation of this guidance. Appendix A is a sample WAP addressing physical/chemical treatment and container storage. Appendix B is a sample WAP addressing an incinerator and tank systems. Appendix C discusses the relationship of the WAP to other permitting requirements and includes specific examples of how waste analysis is used to comply with certain parts of a RCRA permit. Appendix D contains the exact wording for the notification/certification requirements under theland disposal restrictions.

  16. 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.

    1997-06-01

    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.

  17. Interim Closure Activities at Corrective Action Unit 114: Area 25 EMAD Facility, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    Boehlecke, R. F.

    2011-10-24

    This letter report documents interim activities that have been completed at CAU 114 to support ongoing access and generate information necessary to plan future closure activities. General housekeeping and cleanup of debris was conducted in the EMAD yard, cold bays, support areas of Building 3900, and postmortem cell tunnel area of the hot bay. All non-asbestos ceiling tiles and loose and broken non-friable asbestos floor tiles were removed from support galleries and office areas. Non-radiologically contaminated piping and equipment in the cold areas of the building and in the two 120-ton locomotives in the yard were tapped, characterized, drained, and verified free of contents.

  18. OSCARS Collaborative Work

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

    OSCARS Collaborative Work Engineering Services The Network OSCARS How It Works Who's Using OSCARS? OSCARS and Future Tech OSCARS Standard and Open Grid Forum OSCARS Developers...

  19. W Boson Mass Working Group Report

    SciTech Connect (OSTI)

    Kilgore, W.; Kilgore, W.

    2010-06-14

    The W boson mass working group discussed the current status of the W boson mass measurement and the prospects for improving on LEP and Tevatron measurements at the LHC.

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

    SciTech Connect (OSTI)

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

    2011-10-01

    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}.

  1. Remedial Investigation work plan for Bear Creek Valley Operable Unit 4 (shallow groundwater in Bear Creek Valley) at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

    To effectively evaluate the cumulative impact of releases from multiple sources of contamination, a structured approach has been adopted for Oak Ridge Reservation (ORR) based on studies of the groundwater and surface water separate from studies of the sources. Based on the realization of the complexity of the hydrogeologic regime of the ORR, together with the fact that there are numerous sources contributing to groundwater contamination within a geographical area, it was agreed that more timely investigations, at perhaps less cost, could be achieved by separating the sources of contamination from the groundwater and surface water for investigation and remediation. The result will be more immediate attention [Records of Decision (RODS) for interim measures or removal actions] for the source Operable Units (OUs) while longer-term remediation investigations continue for the hydrogeologic regime`s, which are labeled as integrator OUs. This Remedial Investigation work plan contains summaries of geographical, historical, operational, geological, and hydrological information specific to the unit. Taking advantage of the historical data base and ongoing monitoring activities and applying the observational approach to focus data gathering activities will allow the Feasibility Study to evaluate all probable or likely alternatives.

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

    SciTech Connect (OSTI)

    Gregson, Michael Warren; Brockmann, John E.; Loiseau, Olivier; Klennert, Lindsay A.; Nolte, Oliver; Molecke, Martin Alan; Autrusson, Bruno A.; Koch, Wolfgang; Pretzsch, Gunter Guido; Brucher, Wenzel; Steyskal, Michele D.

    2008-03-01

    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).

  3. 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.

    2010-10-29

    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.

  4. Options in the Eleventh Year for Interim Standard Offer Number Four Contracts

    SciTech Connect (OSTI)

    Hinrichs, Thomas C.

    1992-03-24

    The Interim Standard Offer Number Four Contracts (ISM), under which most of the geothermal industry is selling power (outside of The Geysers), has an initial ten year period of known fixed energy payments. In the eleventh year, the price goes to the Avoided Cost of the buying utility. The specific contract language is ''Seller will be paid at a rate equal to the utilities' published avoided cost of energy as updated and authorized by the Commission (CPUC)''. The first geothermal contract will reach the end of the initial 10 year period in early 1994, a few will end in 1995 and 1996, and the majority will end in the 1997-2000 period. This is beginning to be focused upon by the utilities, lenders and, of course, the operators themselves. The prime reason for focusing on the issue is that avoided costs of the utilities directly track the delivered cost of the natural gas, and most forecasts are showing that the price of gas in the eleventh year of the contracts will be significantly lower than the last year of the fixed period of energy payments. There are many forums in which the predication of natural gas prices are discussed. In the State of California, the agency responsible for the official forecast is the California Energy Commission. Every two years, the CEC holds hearings for input into its biennial Fuels Report (FR) which establishes the forecast of natural gas prices in addition to other parameters which are used in the planning process. The attached Exhibit I is an excerpt out of the 1991 Fuels Report (FR91). Figure 1 compares the forecast of FR89 and FR91 for the Utility Electric Generation (UEG) in PG&E's service area, and Figure 2, the forecast in the SOCAL service area. The FR91 SOCAL service area forecast indicates a bottoming of the gas price in 1994 at $2.50/mmbtu. Recent prices in 1992 are already at these levels. Converting this to an avoided energy cost brings about a price of 2 to 2-1/2 Cents/kWh. The 1992 energy price in the IS04 contract is 9.3 Cents/kWh.

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

    SciTech Connect (OSTI)

    CHASTAIN, S.A.

    2005-10-24

    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.

  6. Final report of the accident phenomenology and consequence (APAC) methodology evaluation. Spills Working Group

    SciTech Connect (OSTI)

    Brereton, S.; Shinn, J.; Hesse, D; Kaninich, D.; Lazaro, M.; Mubayi, V.

    1997-08-01

    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.

  7. Service and Repair Work

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

    Service and Repair Work Whenever on-site service or repair work needs to be done, a Procurement Work Sheet (PWS) must be completed, and possibly an IWS, authorized and released. PWS is required for service work even if there are no apparent hazards. PWS is required for work in Jupiter Laser Facility even if you have a PWS for service/repairs in another location. To complete a PWS for service work in Jupiter Laser Facility, please contact Sean Holte (2-3905, pager #05312). Notify Brent Stuart and

  8. Sampling and analysis plan for the gunite and associated tanks interim remedial action, wall coring and scraping at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1998-02-01

    This Sampling and Analysis Plan documents the procedures for collecting and analyzing wall core and wall scraping samples from the Gunite and Associated Tanks. These activities are being conducted to support the Comprehensive Environmental Response, Compensation, and Liability Act at the gunite and associated tanks interim remedial action at Oak Ridge National Laboratory in Oak Ridge, Tennessee. The sampling and analysis activities will be performed in concert with sludge retrieval and sluicing of the tanks. Wall scraping and/or wall core samples will be collected from each quadrant in each tank by using a scraping sampler and/or a coring drill deployed by the Houdini robot vehicle. Each sample will be labeled, transported to the Radioactive Materials Analytical Laboratory, and analyzed for physical and radiological characteristics, including total activity, gross alpha, gross beta, radioactive strontium and cesium, and other alpha- and gamma-emitting radionuclides. The data quality objectives process, based on US Environmental Protection Agency guidance, was applied to identify the objectives of this sampling and analysis. The results of the analysis will be used to (1) validate predictions of a strontium concrete diffusion model, (2) estimate the amount of radioactivity remaining in the tank shells, (3) provide information to correlate with measurements taken by the Gunite Tank Isotope Mapping Probe and the Characterization End Effector, and (4) estimate the performance of the wall cleaning system. This revision eliminates wall-scraping samples from all tanks, except Tank W-3. The Tank W-3 experience indicated that the wall scrapper does not collect sufficient material for analysis.

  9. Work with Biological Materials

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

    Work with Biological Materials Print Planning A complete Experiment Safety Sheet (ESS) is required before work can be done at the ALS. This ESS is either a part of the proposal...

  10. HQ Work Control Permit

    Broader source: Energy.gov [DOE]

    To ensure safe operations when undertaking work at DOE Headquarters, the Office of Headquarters Health and Safety has developed a Work Permit document (doc) to help ensure the safety of all workers...

  11. STATEMENT OF WORK

    National Nuclear Security Administration (NNSA)

    PART III - SECTION J APPENDIX B STATEMENT OF WORK Table of Contents 1.0 General.................................................................................................................... 273 2.0 Laboratory Mission and Scope of Work. ................................................................ 274 3.0 Science & Technology. ........................................................................................... 275 3.1 Defense Programs.

  12. Work plan (Nov

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

    Work Plans & Manuals Work Plans & Manuals This list contains audit and inspections manuals and a list of planned reviews to be conducted by the Office of Audits and Inspections. Documents Available for Download November 20, 2014 Work Plan FY 2016 Planned Audits and Inspections for FY 2016 December 23, 2014 Audit Manual 2014 Office of Inspector General Audit Manual

    ARM STM Cloud Modeling Working Group Session AGENDA Brief introduction of new ARM funded modeling projects:

  13. Interagency Sustainability Working Group

    Broader source: Energy.gov [DOE]

    The Interagency Sustainability Working Group (ISWG) is the coordinating body for sustainable buildings in the federal government.

  14. Administering Work Force Discipline

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2015-05-14

    The order provides requirements and responsibilities for administering work force discipline and corrective actions. Supersedes DOE O 3750.1.

  15. SCM Working Group

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

    Atmospheric Radiation Measurement A Little Background 3.5 x 3.5 degree 23 ARM Extended ... Current ARM SGP Observation Network ARM Atmospheric Radiation Measurement Issues with ...

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

    SciTech Connect (OSTI)

    Daugherty, W.

    2014-08-06

    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 F. 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 F. High temperature aging continues for 23 GLT O-ring fixtures at 200 270 F. Room temperature leak test failures have been experienced in all of the GLT O-ring fixtures aging at 350 F and higher temperatures, and in 8 fixtures aging at 300 F. The earliest 300 F GLT O-ring fixture failure was observed at 34 months. The remaining GLT O-ring fixtures aging at 300 F 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 F for 72 - 96 months, which bounds O-ring temperatures anticipated during storage in K-Area Complex (KAC). Based on expectations that the 200 F fixtures will remain leak-tight for a significant period yet to come, 2 additional fixtures began aging in 2011 at 270 F, with hopes that they may reach a failure condition before the 200 F fixtures, thus providing additional time to failure data. High temperature aging continues for 6 GLT-S O-ring fixtures at 200 300 F. Room temperature leak test failures have been experienced in all 8 of the GLT-S O-ring fixtures aging at 350 and 400 F. No failures have yet been observed in GLT-S O-ring fixtures aging at 200 - 300 F 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.

  17. TeamWorks.cdr

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

    Team Team Works Works TeamWorks TRU TeamWorks is a biweekly e-newsletter for the Waste Isolation Pilot Plant team D E P A R T M E N T O F E N E R G Y U N I T E D S T A T E S O F A M E R I C A Tools Feedback By the Numbers O Our Team: People make it happen The latest on WIPP team news ... Working Smart: Survey says: TeamWorks' new look is not the only change you'll notice ... Safety & Security: Get a load of this ... Picking up the paper takes on a whole new meaning ... Operations: The view

  18. ORISE: Working with ORISE

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

    Oak Ridge Institute for Science Education Working with ORISE If you are interested in learning about how your agency can utilize the capabilities of the Oak Ridge Institute for Science and Education (ORISE) through a Work for Others agreement or a procurement contract, or if you are looking for career opportunities, the following information provides an explanation of how to work with ORISE. If you do not see an option that applies to your needs, please contact ORISE General Information.

  19. Work/Life Balance

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

    Workplace » Work/Life Balance /careers/_assets/images/careers-icon.jpg Work/Life Balance Explore the multiple dimensions of a career at Los Alamos Lab: work with the best minds on the planet in an inclusive environment that is rich in intellectual vitality and opportunities for growth. Complete suite of benefits to balance your career Enlarge poster enlarge Enlarge poster enlarge Enlarge poster enlarge Enlarge poster enlarge Enlarge poster enlarge Enlarge poster enlarge Enlarge poster enlarge

  20. Work with Biological Materials

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

    for proper development and review time. Training All resident LBNL users (those whose work authorization includes a JHA) must take the standard LBNL training courses for...

  1. Work with Biological Materials

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

    Work with Biological Materials Print Planning A complete Experiment Safety Sheet (ESS) is required before work can be done at the ALS. This ESS is either a part of the proposal process or may be completed as an independent document. In the ESS, identify each material (including all biological materials) with which you will be working. The regulatory oversight for biological work is very complicated and we need to understand the risk levels involved with the material you plan to use at the ALS,

  2. Work with Biological Materials

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

    Work with Biological Materials Print Planning A complete Experiment Safety Sheet (ESS) is required before work can be done at the ALS. This ESS is either a part of the proposal process or may be completed as an independent document. In the ESS, identify each material (including all biological materials) with which you will be working. The regulatory oversight for biological work is very complicated and we need to understand the risk levels involved with the material you plan to use at the ALS,

  3. INL @ work: Archaeologist

    ScienceCinema (OSTI)

    Lowrey, Dino

    2013-05-28

    INL @ work features jobs performed at the lab. For more information about INL careers, visit http://www.facebook.com/idahonationallaboratory.

  4. Work with Biological Materials

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

    cells, viruses), plant or soil samples (USDA quarantines), recombinant DNA, or blood-borne pathogen. Biological Use Authorization The great majority of biological work at...

  5. Work Authorization System

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2005-04-21

    To establish a work authorization and control process for work performed by designated site and facility management contractors, and other contractors as determined by the procurement executive, consistent with the budget execution and program evaluation requirements of the Department of Energy's Planning, Programming, Budgeting, and Evaluation process. Admin Chg 1, dated 5-21-2014, cancels DOE O 412.1A.

  6. Work Authorization System

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2005-04-21

    To establish a work authorization and control process for work performed by designated site and facility management contractors, and other contractors as determined by the procurement executive, consistent with the budget execution and program evaluation requirements of the Department of Energy's (DOE's) Planning, Programming, Budgeting, and Evaluation process. Cancels DOE O 412.1.

  7. Work Authorization System

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-04-20

    It establishes a work authorization and control process for work performed by designated management and operating (M&O), management and integrating (M&I), environmental restoration management contracts (ERMC) and other contracts determined by the Procurement Executive (hereafter referred to as M&O contractors). Cancels DOE O 5700.7C. Canceled by DOE O 412.1A.

  8. Enterprise Assessments Operational Awareness Record of Observations of the Design and Modification Progress of the Waste Isolation Pilot Plant Underground Interim Ventilation System and Supplemental Ventilation System November 2015

    Broader source: Energy.gov [DOE]

    Enterprise Assessments Operational Awareness Record of Observations of the Design and Modification Progress of the Waste Isolation Pilot Plant Underground Interim Ventilation System and Supplemental Ventilation System November 2015

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

    SciTech Connect (OSTI)

    Wagner, Paul; Nugent, John; Price, William

    1999-02-15

    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...

  10. Trails Working Group

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

    Working Group Trails Working Group Our mission is to inventory, map, and prepare historical reports on the many trails used at LANL. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email The LANL Trails Working Group inventories, maps, and prepares historical reports on the many trails used at LANL. Some of these trails are ancient pueblo footpaths that continue to be used for recreational hiking today. Some serve as quiet

  11. How It Works

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

    How It Works Engineering Services The Network OSCARS How It Works Who's Using OSCARS? OSCARS and Future Tech OSCARS Standard and Open Grid Forum OSCARS Developers Community Read More... Fasterdata IPv6 Network Network Performance Tools The ESnet Engineering Team Contact Us Technical Assistance: 1 800-33-ESnet (Inside US) 1 800-333-7638 (Inside US) 1 510-486-7600 (Globally) 1 510-486-7607 (Globally) Report Network Problems: trouble@es.net Provide Web Site Feedback: info@es.net How It Works

  12. ID@Work

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

    ID@Work ID@Work ID@Work is a video feature that introduces DOE-ID employees and the jobs they perform. These videos are created in Windows Media Video (wmv) format and have no scripts are available. 2013, January Morris Hall is the Radiological Controls Manager for the Idaho Operations Office 2 minutes, (18 MB) 2012, December Mark Arenaz, Director of ID's Office of Project Management Support 2 minutes, (14 MB) 2012, January Carol Henning, Safety Team Lead for Quality and Safety Division 2

  13. How Lasers Work

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

    How Lasers Work "Laser" is an acronym for light amplification by stimulated emission of radiation. A laser is created when the electrons in atoms in special glasses, crystals, or ...

  14. Strategic Initiatives Work Group

    Broader source: Energy.gov [DOE]

    The Work Group, comprised of members representing DOE, contractor and worker representatives, provides a forum for information sharing; data collection and analysis; as well as, identifying best practices and initiatives to enhance safety performance and safety culture across the Complex.

  15. How Fusion Energy Works

    Broader source: Energy.gov [DOE]

    Fusion energy is the energy source of the sun and all of the stars. As part of How Energy Works, we'll cover everything from fuel sources to plasma physics and beyond.

  16. Quality Work Plan Update

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

    the value of an experienced crews * No way to place value on high-quality training * Inconsistent methods of inspection across the network * No national standards for work quality ...

  17. Working Together | Jefferson Lab

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

    Energy Address Natural Gas Storage Safety Working Together to Address Natural Gas Storage Safety April 1, 2016 - 11:15am Addthis Working Together to Address Natural Gas Storage Safety Franklin (Lynn) Orr Franklin (Lynn) Orr Under Secretary for Science and Energy Marie Therese Dominguez Marie Therese Dominguez Administrator, U.S. Department of Transportation's Pipeline and Hazardous Materials Safety Administration As a part of the Administration's ongoing commitment to support state and

  18. Fermilab: Science at Work

    ScienceCinema (OSTI)

    Brendan Casey; Herman White; Craig Hogan; Denton Morris; Mary Convery; Bonnie Fleming; Deborah Harris; Dave Schmitz; Brenna Flaugher; Aron Soha

    2013-02-14

    Six days. Three frontiers. One amazing lab. From 2010 to 2012, a film crew followed a group of scientists at the Department of Energy's Fermilab and filmed them at work and at home. This 40-minute documentary shows the diversity of the people, research and work at Fermilab. Viewers catch a true behind-the-scenes look of the United States' premier particle physics laboratory while scientists explain why their research is important to them and the world.

  19. Partnerships & Sponsored Work

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

    Partnerships & Sponsored Work Partnerships & Sponsored Work Los Alamos scientists and engineers conduct basic research across a wide range of scientific areas to support our national security mission. Many of the technologies, processes, and special technical expertise we have developed has been applied to solving problems in the private sector through mutually beneficial, technology partnerships. Contact Cooperative Research & Development Agreements (CRADA) CRADA Team Email

  20. Working With Us | NREL

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

    Working With Us Join us in building a clean energy future. NREL offers many opportunities to industry, organizations, government, researchers, businesses, students, educators, and vendors. At NREL, we work with organizations large and small through research partnerships, licensing of NREL technologies, support for cleantech stakeholders, and fostering the clean energy economy. Join us to accelerate the movement of renewable energy and energy-efficient solutions into practical applications.

  1. ARM - Measurements

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

    govMeasurementsAerosols

  2. ARM - Measurements

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

    govMeasurementsRadiometric

  3. Revised RCRA closure plan for the Interim Drum Yard (S-030) at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Smith, C.M.

    1994-09-01

    The Interim Drum Yard (IDY) facility is a containerized waste storage area located in the Y-12 exclusion area. It was used to store waste materials which are regulated by RCRA (Resource Conservation and Recovery Act); uranyl nitrate solutions were also stored there. The closure plan outlines the actions required to achieve closure of IDY and is being submitted in accordance with TN Rule 1200-1-11.05(7) and 40 CFR 265.110.

  4. Work Force Retention Work Group Charter | Department of Energy

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

    Force Retention Work Group Charter Work Force Retention Work Group Charter The Work force Retention Work Group is established to support the Department's critical focus on maintaining a high-performing work force at a time when a significant number of the workers needed to support DOE's national security mission are reaching retirement age. PDF icon Work Force Retention Work Group Charter More Documents & Publications Workforce Retention Work Group Status Overview - September 2012 Training

  5. 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.

    2014-09-12

    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.

  6. Exhibit G / working draft

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

    Off-site (Rev 5, 2/28/2014) P.R. No. * Date * Page 1 of 2 Subcontract No. or PO No. * EXHIBIT G OFF-SITE SECURITY REQUIREMENTS G1.0 Definitions and Acronyms (Feb 2014) Definitions and acronyms may be accessed electronically at http://www.lanl.gov/resources/_assets/docs/Exhibit-G/exhibit-g-definitions-acronyms-green.pdf G2.0 Statements Applicable To Scope of Work (July 2013) CONTRACTOR believes that all of the statements listed below are factually correct and applicable to the scope of work (SOW)

  7. 90-day Interim Report on Shale Gas Production- Secretary of Energy Advisory Board

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Shale Gas Subcommittee of the Secretary of Energy Advisory Board is charged with identifying measures that can be taken to reduce the environmental impact and improve the safety of shale gas...

  8. Work Force Discipline

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1983-03-23

    The order provides guidance and procedures and states responsibilities for maintaining work force discipline in DOE. Chg 1, dated 3-11-85; Chg 2, dated 1-6-86; Chg 3, dated 3-21-89; Chg 4, dated 8-2-90; Chg 5, dated 3-9-92; Chg 6, dated 8-21-92, cancels Chg 5.

  9. work_guidance_final

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

    least an appropriate JLab Task List is required (halist, hblist, hclist, hdlist, pslist), and one should consider a formal work control document. See points 2-5 below. * Any setup or task that has a total duration of more than two weeks requires at the very least an appropriate JLab Task List (halist, hblist, hclist, hdlist, pslist). A paper copy

  10. River Protection Project (RPP) Immobilized High Level Waste (HLW) Interim Storage Plan

    SciTech Connect (OSTI)

    BRIGGS, M.G.

    2000-09-22

    This document replaces HNF-1751, Revision 1. It incorporates updates to reflect changes in programmatic direction associated with the vitrification plant contract and associated DOE-ORP guidance. In addition it includes planning associated with failed/used melter and sample handling and disposition work scope. The document also includes format modifications and section numbering update consistent with CH2M HILL Hanford Group, Inc. procedures.

  11. 40 CFR 265 interim status indicator-evaluation ground-water monitoring plan for the 216-B-63 trench

    SciTech Connect (OSTI)

    Bjornstad, B.N.; Dudziak, S.

    1989-03-01

    This document outlines a ground-water monitoring plan for the 216-B-63 trench located in the northeast corner of the 200-East Area on the Hanford Site in southeastern Washington State. It has been determined that hazardous materials (corrosives) were disposed of to the trench during past operations. Installation of an interim-status ground-water monitoring system is required to determine whether hazardous chemicals are leaching to the ground water from beneath the trench. This document summarizes the existing data that are available from near the 216-B-63 trench and presents a plan to determine the extent of ground-water contamination, if any, derived from the trench. The plan calls for the installation of four new monitoring wells located near the west end of the trench. These wells will be used to monitor ground-water levels and water quality immediately adjacent to the trench. Two existing RCRA monitoring wells, which are located near the trench and hydraulically upgradient of it, will be used as background wells. 46 refs., 15 figs., 12 tabs.

  12. 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

    2011-02-01

    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.

  13. TRU TeamWorks

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

    , 2004 By the Numbers WIPP marks five-year anniversary Shipments scheduled to arrive at WIPP for the week of 4/4/04 - 4/10/04: 18 Total shipments received at WIPP: 2,456 Total volume disposed at WIPP: 19,042 m 3 FY04 Performance Metrics D E P A R T M E N T O F E N E R G Y U N I T E D S T A T ES O F A M E R I C A TeamWorks TeamWorks TRU A weekly e-newsletter for the Waste Isolation Pilot Plant team For those who endured the early morning cold of March 26, 1999, to witness WIPP's first shipment,

  14. UFD Working Group 2015

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

    Working Group 2015 - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced

  15. Buildings Sector Working Group

    U.S. Energy Information Administration (EIA) Indexed Site

    July 22, 2013 AEO2014 Model Development For discussion purposes only Not for citation Overview Builldings Working Group Forrestal 2E-069 / July 22, 2013 2 * Residential projects - RECS update - Lighting model - Equipment, shell subsidies - ENERGY STAR benchmarking - Housing stock formation and decay * Commercial projects - Major end-use capacity factors - Hurdle rates - ENERGY STAR buildings * Both sectors - Consumer behavior workshop - Comparisons to STEO - AER  MER - Usual annual updates -

  16. SCM Working Group

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

    Modeling Working Group Translator Update Shaocheng Xie Lawrence Livermore National Laboratory Outline 1. Data development in support of CMWG * Climate modeling best estimate data * Extended and updated TWP-ICE forcing and evaluation data * Radiative heating and cloud microphysics data for TWP-ICE * BBHRP for SGP * Other relevant data 2. Survey results for data used by CMWG and future forcing data development Initial data list * Cloud fraction from ARSCL and TSI * Liquid water path and

  17. ARM - Measurements

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

    govMeasurementsCloud Properties

  18. ARM - Measurements

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

    govMeasurementsSurface Properties

  19. Savannah River Site Interim Waste Management Program Plan FY 1991--1992

    SciTech Connect (OSTI)

    Chavis, D.M.

    1992-05-01

    The primary purpose of the Waste Management Program Plan is to provide an annual report of how Waste Management's operations are conducted, what facilities are being used to manage wastes, what forces are acting to change current waste management systems, and what plans are in store for the coming fiscal year. In addition, this document projects activities for several years beyond the coming fiscal year in order to adequately plan for safe handling, storage, and disposal of radioactive wastes generated at the Savannah River Site and for developing technology for improved management of wastes. In this document, work descriptions and milestone schedules are current as of December 1991.

  20. Savannah River Site Interim Waste Management Program Plan FY 1991--1992

    SciTech Connect (OSTI)

    Chavis, D.M.

    1992-05-01

    The primary purpose of the Waste Management Program Plan is to provide an annual report of how Waste Management`s operations are conducted, what facilities are being used to manage wastes, what forces are acting to change current waste management systems, and what plans are in store for the coming fiscal year. In addition, this document projects activities for several years beyond the coming fiscal year in order to adequately plan for safe handling, storage, and disposal of radioactive wastes generated at the Savannah River Site and for developing technology for improved management of wastes. In this document, work descriptions and milestone schedules are current as of December 1991.

  1. Surficial Geology and Landscape Development in Northern Frenchman Flat, Interim Summary and Soil Data

    SciTech Connect (OSTI)

    Raytheon Services Nevada Environmental Restoration and Waste Management Division

    1995-09-01

    This report summarizes geologic studies by Raytheon Services Nevada near the Area 5 Radioactive Waste Management Site at the Nevada Test Site. These studies are part of a program to satisfy data needs of (1) the Greater Confinement Disposal (GCD) Program Performance Assessment (PA), (2) the low-level waste (LLW) PA, and (3) the Resource Conservation and Recovery Act (RCRA) permit application. The geologic studies were integrated into a single program that worked toward a landscape evolution model of northern Frenchman Flat, with more detailed geologic studies of particular topics as needed. Only the Holocene tectonism and surficial geology components of the landscape model are presented in this report.

  2. Exhibit G / working draft

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

    (Rev 13, 5/22/2014) Security Requirements P.R. No. * Date * Page 1 of 35 Solicitation/Subcontract No. or PO No. Preparer Note (PN): This document contains instructions in blue hidden text. To view hidden text, click on the ¶ (Show/Hide) icon on your tool bar. If that doesn't work, see the document "How to View Hidden Text" on the Exhibit G website at http://int.lanl.gov/security/ExG.shtml. There is no need to delete the blue hidden text instructions since hidden text will not affect

  3. How NIF Works

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

    How Much Do You Spend on Energy? How Much Do You Spend on Energy? U.S.A. Energy Expenditure per person Click on a state Energy Expenditure $3724 per person in 2012 Transportation ▀▀▀▀▀ Residential ▀▀▀▀▀ Data: EIA State Energy Data System View All Maps Addthis

    How NIF Works A weak laser pulse-about 1 billionth of a joule-is created, split, and carried on optical fibers to 48 preamplifiers that increase the pulse's energy by a factor of 10 billion, to a few joules. The 48

  4. HANFORD ENGINEER WORKS

    Office of Legacy Management (LM)

    HANFORD ENGINEER WORKS IJd *P-t - - ~~~ssiticatiC+n cwcetted rat G.E. NUCLEONICS PROJECT xi I ~@L.%&~--G-ENERAI,@ ELECTRIC z ,m ._.__.-. _ I--..-. By Authority of. COMPANY ._ Atmic Energy Commission Office of Hanford Dire&xl Operations Riohland, Washington Attention; Mr. Carleton Shugg, Manager ./ ALPKA-ROLLED EL'GIL%I jw -879 ' . *_ a. f' Richland, Washington February 6, 1948 , Thla Dclc.Jv-<en! :-; . ' - -*...-- f_ ~~~.s No .__. ._. .s / ~. - J-LccIp%. Fr:*? fi This will con&rm

  5. Demonstration of an advanced superconducting generator: Interim report, May 16, 1981--August 15, 1981

    SciTech Connect (OSTI)

    Not Available

    1981-10-23

    The objective of this program, ''Demonstration of an Advanced Superconducting Generator'', is to demonstrate advanced concepts in a prototype superconducting generator. Starting in August 1976, concept study and analysis lead in December 1977 to the selection of concepts for the experimental generator. Continued analysis and design optimization of the selected concepts lead to a design selection for the 10 MVA experiment in November 1978. Iteration with detail design and the application of more accurate analysis resulted in a freeze of the ''fine tuned'' design in September 1979. By May 1980 all secondary design decisions had been made and all major components and materials had been ordered. By December 1980 the installation of the gas turbine prime mover and the helium refrigerator/liquefier had been completed and fabrication had commenced on the stator core and the armature of the experimental generator. Work during this reporting period has been concentrated on the fabrication of the generator and on component development and testing.

  6. Demonstration of an advanced superconducting generator: Interim report, August 16, 1979--December 15, 1979

    SciTech Connect (OSTI)

    Not Available

    1980-04-11

    The objective of this program, ''Demonstration of an Advanced Superconducting Generator,'' is to demonstrate advanced concepts in a prototype superconducting generator. Starting in August 1976, concept study and analysis lead in December 1977 to the selection of concepts for the experimental generator. Continued analysis and design optimization of the selected concepts lead to a design selection for the 10 MVA experiment in November 1978. Iteration with detail design and the application of more accurate analysis resulted in a freeze of the ''fine tuned'' design in September 1979. During this reporting period the emphasis has shifted to the detailed design of major components, construction methods and assembly sequences. An overall construction plan has been worked out. All major components will be completed in 1980 and assembled in 1981. A balanced and cold tested rotor should be ready for generator tests in early 1982. Procurement of major components is proceeding according to the plan.

  7. Demonstration of an advanced superconducting generator: Interim report, August 16, 1981--December 15, 1981

    SciTech Connect (OSTI)

    Not Available

    1982-03-16

    The objective of this program, ''Demonstration of an Advanced Superconducting Generator,'' is to demonstrate advanced concepts in a prototype superconducting generator. Starting in August 1976, concept study and analysis lead in December 1977 to the selection of concepts for the experimental generator. Continued analysis and design optimization of the selected concepts lead to a design selection for the 10 MVA experiment in November 1978. Iteration with detail design and the application of more accurate analyses resulted in a freeze of the ''fine tuned'' design in September 1979. By May 1980 all secondary design decisions had been made and all major components and materials had been ordered. By December 1980 the installation of the gas turbine prime mover and the helium refrigerator/liquefier had been completed and fabrication had commenced on the stator core and the armature of the experimental generator. Work during this reporting period has been concentrated on the fabrication of the generator and on component development and testing.

  8. 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

    2012-03-01

    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.

  9. The CASTOR-V/21 PWR spent-fuel storage cask: Testing and analyses: Interim report

    SciTech Connect (OSTI)

    Dziadosz, D.; Moore, E.V.; Creer, J.M.; McCann, R.A.; McKinnon, M.A.; Tanner, J.E.; Gilbert, E.R.; Goodman, R.L.; Schoonen, D.H.; Jensen, M.

    1986-11-01

    A performance test of a Gesellschaft fuer Nuklear Service CASTOR-V/21 pressurized water reactor (PWR) spent fuel storage cask was performed. The test was the first of a series of cask performance tests planned under a cooperative agreement between Virginia Power and the US Department of Energy. The performance test consisted of loading the CASTOR-V/21 cask with 21 PWR spent fuel assemblies from Virginia Power's Surry reactor. Cask surface and fuel assembly guide tube temperatures, and cask surface gamma and neutron dose rates were measured. Testing was performed with vacuum, nitrogen, and helium backfill environments in both vertical and horizontal cask orientations. Limited spent fuel integrity data were also obtained. Results of the performance test indicate the CASTOR-V/21 cask exhibited exceptionally good heat transfer performance which exceeded design expectations. Peak cladding temperatures with helium and nitrogen backfills in a vertical cast orientation and with helium in a horizontal orientation were less than the allowable of 380/sup 0/C with a total cask heat load of 28 kW. Significant convection heat transfer was present in vertical nitrogen and helium test runs as indicated by peak temperatures occurring in the upper regions of the fuel assemblies. Pretest temperature predictions of the HYDRA heat transfer computer program were in good agreement with test data, and post-test predictions agreed exceptionally well (25/sup 0/C) with data. Cask surface gamma and neutron dose rates were measured to be less than the design goal of 200 mrem/h. Localized peaks as high as 163 mrem/h were measured on the side of the cask, but peak dose rates of <75 mrem/h can easily be achieved with minor refinements to the gamma shielding design. From both heat transfer and shielding perspectives, the CASTOR-V/21 cask can, with minor refinements, be effectively implemented at reactor sites and central storage facilities for safe storage of spent fuel.

  10. Low-level waste management program and interim waste operations technologies

    SciTech Connect (OSTI)

    Mezga, L.J.

    1983-01-01

    The Department of Energy currently supports an integrated technology development and transfer program aimed at ensuring that the technology necessary for the safe management and disposal of LLW by the commercial and defense sectors is available. The program focuses on five technical areas: (1) corrective measures technology, (2) improved shallow land burial technology, (3) greater confinement disposal technology, (4) model development and validation, and (5) treatment methods for problem wastes. The results of activities in these areas are reported in the open literature and the Proceedings of the LLWMP Annual Participants Information Meeting.

  11. How NIF Works

    ScienceCinema (OSTI)

    None

    2010-09-01

    The National Ignition Facility, located at Lawrence Livermore National Laboratory, is the world's largest laser system... 192 huge laser beams in a massive building, all focused down at the last moment at a 2 millimeter ball containing frozen hydrogen gas. The goal is to achieve fusion... getting more energy out than was used to create it. It's never been done before under controlled conditions, just in nuclear weapons and in stars. We expect to do it within the next 2-3 years. The purpose is threefold: to create an almost limitless supply of safe, carbon-free, proliferation-free electricity; examine new regimes of astrophysics as well as basic science; and study the inner-workings of the U.S. stockpile of nuclear weapons to ensure they remain safe, secure and reliable without the need for underground testing. More information about NIF can be found at:

  12. Working Group Report: Sensors

    SciTech Connect (OSTI)

    Artuso, M.; et al.,

    2013-10-18

    Sensors play a key role in detecting both charged particles and photons for all three frontiers in Particle Physics. The signals from an individual sensor that can be used include ionization deposited, phonons created, or light emitted from excitations of the material. The individual sensors are then typically arrayed for detection of individual particles or groups of particles. Mounting of new, ever higher performance experiments, often depend on advances in sensors in a range of performance characteristics. These performance metrics can include position resolution for passing particles, time resolution on particles impacting the sensor, and overall rate capabilities. In addition the feasible detector area and cost frequently provides a limit to what can be built and therefore is often another area where improvements are important. Finally, radiation tolerance is becoming a requirement in a broad array of devices. We present a status report on a broad category of sensors, including challenges for the future and work in progress to solve those challenges.

  13. Panasonic Electric Works Ltd formerly Matsushita Electric Works...

    Open Energy Info (EERE)

    Electric Works Ltd (formerly Matsushita Electric Works) Place: Kadoma-shi, Osaka, Japan Zip: 571-8686 Product: Japanese manufacturer of mainly electric appliances including...

  14. The effects of interim flow operations from Glen Canyon Dam on Colorado River sand bars in the Grand Canyon, Arizona

    SciTech Connect (OSTI)

    Kaplinski, M.A.; Hazel, J.E.; Beus, S.S. . Geology Dept.); Stevens, L.E. . NPS Cooperative Parks Studies Unit); Mayes, H.B. )

    1993-04-01

    Discharges from Glen Canyon Dam (GCD) affect the geomorphology and stability of downstream alluvial sediment deposits. To protect downstream resources, the US DOI mandated interim flow criteria (IFC) on 1 August, 1991. The IFC consist of reduced daily fluctuations (226--566 m[sup 3]/s) and reduced ramping rates (42.5--57 m[sup 3]/s/hr), the primary objective of which is to maintain sediment storage in the river system by minimizing sediment transport. This study was initiated to determine the effectiveness of the IFC in achieving this objective. The authors examined whether reduced daily fluctuations lead to subaerial sand bar erosion and increased subaqueous sediment storage. They collected and analyzed topographic and bathymetric survey data from sand bars throughout the Colorado River corridor in Sept/Oct, 1991 and in Oct/Nov, 1992 to compare changes in sand bar morphology. They examined changing topography due to GCD operation in what they termed the hydrologically active zone (HAZ), that portion of the sand bar exposed to daily dam operations (142--900 m[sup 3]/s stage elevations). Volumes within the HAZ and profiles across this zone were generated from these sediment deposits. Their preliminary results show that, in general, erosion of sediment at higher bar elevations was coincident with deposition along lower parts of the bar platform. The observed response to IFC elevation in order to maintain sediment deposits for Colorado River corridor bio-diversity (e.g., fisheries habitats). 88% of sand bars that showed significant volume gain were preceded by significant volume loss, implying that antecedent conditions are an important factor in sand bar response to GCD operations. Sediment transport capacity was reduced as evidenced by increased sediment storage in recirculation zones and sediment infilling of eddy return channels. The authors conclude that IFC are achieving their primary objective of maintaining sediment storage within the river corridor.

  15. 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.

    2014-09-01

    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.

  16. Report on the performance monitoring system for the interim waste containment at the Niagara Falls Storage Site, Lewiston, New York

    SciTech Connect (OSTI)

    Not Available

    1985-10-01

    The Niagara Falls Storage Site (NFSS) is an interim storage site for low-level radioactive waste, established by the US Department of Energy (DOE) at Lewiston, New York. The waste containment structure for encapsulating low-level radioactive waste at the NFSS has been designed to minimize infiltration of rainfall, prevent pollution of groundwater, preclude formation of leachate, and prevent radon emanation. Accurately determining the performance of the main engineered elements of the containment structure will be important in establishing confidence in the ability of the structure to retain the wastes. For this purpose, a waste containment performance monitoring system has been developed to verify that these elements are functioning as intended. The key objective of the performance monitoring system is the early detection of trends that could be indicative of weaknesses developing in the containment structure so that corrective action can be taken before the integrity of the structure is compromised. Consequently, subsurface as well as surface monitoring techniques will be used. After evaluating several types of subsurface instrumentation, it was determined that vibrating wire pressure transducers, in combination with surface monitoring techniques, would satisfactorily monitor the parameters of concern, such as water accumulation inside the containment facility, waste settlement, and shrinkage of the clay cover. Surface monitoring will consist of topographic surveys based on predetermined gridlines, walkover surveys, and aerial photography to detect vegetative stress or other changes not evident at ground level. This report details the objectives of the performance monitoring system, identifies the elements of the containment design whose performance will be monitored, describes the monitoring system recommended, and outlines the costs associated with the monitoring system. 5 refs., 4 figs., 3 tabs.

  17. 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.

    2013-09-27

    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.

  18. Demonstration of an advanced superconducting generator: Interim report, December 16, 1981--May 15, 1982

    SciTech Connect (OSTI)

    Not Available

    1982-11-03

    The objective of this program, ''Demonstration of an Advanced Superconducting Generator,'' is to demonstrate advanced concepts in a prototype superconducting generator. Starting in August 1976, concept study and analysis lead in December 1977 to the selection of concepts for the experimental generator. Continued analysis and design optimization of the selected concepts lead to a design selection for the 10 MVA experiment in November 1978. Iteration with detail design and the application of more accurate analysis resulted in a freeze of the ''fine tuned'' design in September 1978. By May 1980 all secondary design decisions had been made and all major components and materials had been ordered. By December 1980 the installation of the gas turbine prime mover and the helium refrigerator/liquefier had been completed and fabrication had commenced on the stator core and the armature of the experimental generator. Detail designs were completed and component development and fabrication was carried out during 1981. Work during this report period includes fabrication of the armature and rotor as well as the completion of additional component development tests.

  19. Demonstration of an advanced superconducting generator: Interim report, December 16, 1980--May 15, 1981

    SciTech Connect (OSTI)

    Not Available

    1981-08-10

    The objective of this program, ''Demonstration of an Advanced Superconducting Generator'', is to demonstrate advanced concepts in a prototype superconducting generator. Starting in August 1976, concept study and analysis lead in December 1977 to the selection of concepts for the experimental generator. Continued analysis and design optimization of the selected concepts lead to a design selection for the 10 MVA experiment in November 1978. Iteration with detail design and the application of more accurate analysis resulted in a freeze of the ''fine tuned'' design in September 1979. By May 1980 all secondary design decisions had been made and all major components and materials had been ordered. By December 1980 the installation of the gas turbine prime mover and the helium refrigerator/liquefier had been completed and fabrication had commenced on the stator core and the armature of the experimental generator. Work during this reporting period has been concentrated on the fabrication of the generator and on component development and testing. Mockups of the damper winding and the rotor assembly were fabricated and development and testing of thermal isolation layer material and armature electrical insulation was carried out.

  20. Survey of technology for hybrid vehicle auxiliary power units. Interim report, April 1994-June 1995

    SciTech Connect (OSTI)

    Widener, S.K.

    1995-10-01

    The state-of-the-art of heat engines for use as auxiliary power units in hybrid vehicles is surveyed. The study considers reciprocating or rotary heat engines, excluding gas turbines and fuel cells. The relative merits of various engine-generator concepts are compared. The concepts are ranked according to criteria tailored for a series-type hybrid drive. The two top APU concepts were the free-piston engine/linear generator (FPELG) and the Wankel rotary` engine. The FPELG is highly ranked primarily because of thermal efficiency cost, producibility. reliability, and transient response advantages; it is a high risk concept because of unproven technology. The Wankel engine is proven. with high power density, low cost and low noise. Four additional competitive concepts include two-stroke spark-ignition engine. two-stroke gas generator with turboalternator, free-piston engine gas generator with turboalternator, and homogeneous charge compression ignition engine. This study recommends additional work, including cycle simulation development and preliminary design to better quantify thermal efficiency and power density. Auxiliary concepts were also considered, including two which warrant further study: electrically actuated valves, and lean turndown of a normally stoichiometric engine. These concepts should be evaluated by retrofitting to existing engines.

  1. Stress corrosion cracking of Alloys 600 and 182 in BWR environments. Interim report

    SciTech Connect (OSTI)

    Ljungberg, L.G.; Hofling, C.G.; Sahlberg, A.; Moeller, J.

    1992-05-01

    Wrought Alloy 600 and weldments of Alloy 182 are being tested for initiation and propagation of intergranular stress corrosion cracking (IGSCC). Crack initiation is tested on compact tension (CT) specimens with U-notches of various radii under enhanced crevice conditions, in a test loop in a Swedish BWR. After one year exposure there was initiation of IGSCC in a large portion of the Alloy 182 specimens, but nearly no initiation in Alloy 600. Crack propagation was measured in a laboratory loop on CT specimens under constant or cyclic load. Low carbon Alloy 600, or Alloy 182 high in titanium and niobium versus carbon, cracked at lower rates than material with high carbon activity. Materials with low concentrations of phosphorus and sulfur cracked slower than those high in these elements in clean environment, but no such effect was found in environment with sulfate. Alloy 182 weld metal generally cracked at higher rates than Alloy 600.

  2. Conversion of forest residues to a methane-rich gas: Interim Report

    SciTech Connect (OSTI)

    Feldmann, H.G.; Paisley, M.A.; Appelbaum, H.R.

    1986-03-01

    A process is being developed that produces a fuel gas with a heating value of 500 Btu/SCF from diverse forms of biomass, including shredded bark, wood chips, and sawdust. The system uses a high throughput, non-oxygen gasifier that employs sand circulation to supply process heat. Results obtained with a 10-inch I.D. gasifier are presented and compared with those in a 6-inch I.D. reactor. Feed rates up to 12 tons/day (dry) have been achieved corresponding to a specific wood throughput of 2000 lbs/ft/sup 2/-hr. Gas compositions in the two reactors are in excellent agreement and performance in the larger reactor, as measured by carbon conversion, is significantly improved. Cost projections comparing this process with direct combustion are presented that indicate gasification technology should have very significant cost advantages for both generation of plant steam and cogeneration of electricity. 5 refs., 14 figs., 5 tabs.

  3. Low work function, stable thin films

    DOE Patents [OSTI]

    Dinh, Long N.; McLean, II, William; Balooch, Mehdi; Fehring, Jr., Edward J.; Schildbach, Marcus A.

    2000-01-01

    Generation of low work function, stable compound thin films by laser ablation. Compound thin films with low work function can be synthesized by simultaneously laser ablating silicon, for example, and thermal evaporating an alkali metal into an oxygen environment. For example, the compound thin film may be composed of Si/Cs/O. The work functions of the thin films can be varied by changing the silicon/alkali metal/oxygen ratio. Low work functions of the compound thin films deposited on silicon substrates were confirmed by ultraviolet photoelectron spectroscopy (UPS). The compound thin films are stable up to 500.degree. C. as measured by x-ray photoelectron spectroscopy (XPS). Tests have established that for certain chemical compositions and annealing temperatures of the compound thin films, negative electron affinity (NEA) was detected. The low work function, stable compound thin films can be utilized in solar cells, field emission flat panel displays, electron guns, and cold cathode electron guns.

  4. Working at EERE | Department of Energy

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

    Employment Opportunities » Working at EERE Working at EERE As a model employer and diversity/inclusion leader, we treat people as our greatest asset at the Office of Energy Efficiency and Renewable Energy (EERE). Our goal is to be an employer of choice and a diversity leader, and we measure our success by the engagement of our employees, the satisfaction of our customers and our relationships with the communities in which we work. In EERE, we constantly strive for a workplace that is inclusive

  5. 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

    1983-06-01

    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.

  6. Internal temperature monitor for work pieces

    DOE Patents [OSTI]

    Berthold, John W. (Salem, OH)

    1993-01-01

    A method and apparatus for measuring the internal temperature of a work piece comprises an excitation laser for generating laser pulses which are directed through a water cooled probe, and in an optical fiber, to a first surface of the work piece. The laser is of sufficient intensity to ablate the surface of the work piece, producing a displacement and a resulting ultrasonic pulse which propagates within the thickness of the work piece to an opposite surface. The ultrasonic pulse is reflected from the opposite surface and returns to the first surface to create a second displacement. A second continuous laser also shines its light through an optical fiber in the probe into the first surface and is used in conjunction with signal processing equipment to measure the time between the first and second displacements. This time is proportional to the time-of-flight of the ultrasonic pulse in the work piece which, with a known or detected thickness of the work piece, can be used to calculate the internal temperature of the work piece.

  7. Internal temperature monitor for work pieces

    DOE Patents [OSTI]

    Berthold, J.W.

    1993-07-13

    A method and apparatus for measuring the internal temperature of a work piece comprises an excitation laser for generating laser pulses which are directed through a water cooled probe, and in an optical fiber, to a first surface of the work piece. The laser is of sufficient intensity to ablate the surface of the work piece, producing a displacement and a resulting ultrasonic pulse which propagates within the thickness of the work piece to an opposite surface. The ultrasonic pulse is reflected from the opposite surface and returns to the first surface to create a second displacement. A second continuous laser also shines its light through an optical fiber in the probe into the first surface and is used in conjunction with signal processing equipment to measure the time between the first and second displacements. This time is proportional to the time-of-flight of the ultrasonic pulse in the work piece which, with a known or detected thickness of the work piece, can be used to calculate the internal temperature of the work piece.

  8. 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

    2009-07-22

    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.

  9. Evaluation of Aluminum-Boron Carbide Neutron Absorbing Materials for Interim Storage of Used Nuclear Fuel

    SciTech Connect (OSTI)

    Wang, Lumin; Wierschke, Jonathan Brett

    2015-04-08

    The objective of this work was to understand the corrosion behavior of Boral® and Bortec® neutron absorbers over long-term deployment in a used nuclear fuel dry cask storage environment. Corrosion effects were accelerated by flowing humidified argon through an autoclave at temperatures up to 570°C. Test results show little corrosion of the aluminum matrix but that boron is leaching out of the samples. Initial tests performed at 400 and 570°C were hampered by reduced flow caused by the rapid build-up of solid deposits in the outlet lines. Analysis of the deposits by XRD shows that the deposits are comprised of boron trioxide and sassolite (H3BO3). The collection of boron- containing compounds in the outlet lines indicated that boron was being released from the samples. Observation of the exposed samples using SEM and optical microscopy show the growth of new phases in the samples. These phases were most prominent in Bortec® samples exposed at 570°C. Samples of Boral® exposed at 570°C showed minimal new phase formation but showed nearly the complete loss of boron carbide particles. Boron carbide loss was also significant in Boral samples at 400°C. However, at 400°C phases similar to those found in Bortec® were observed. The rapid loss of the boron carbide particles in the Boral® is suspected to inhibit the formation of the new secondary phases. However, Material samples in an actual dry cask environment would be exposed to temperatures closer to 300°C and less water than the lowest test. The results from this study conclude that at the temperature and humidity levels present in a dry cask environment, corrosion and boron leaching will have no effect on the performance of Boral® and Bortec® to maintain criticality control.

  10. CRAD, Work Controls Assessment Plan

    Broader source: Energy.gov [DOE]

    Management should have an established work control process in place with authorized, controlled and documented methods that provide an accurate status of the work to be performed.

  11. Parallel computing works

    SciTech Connect (OSTI)

    Not Available

    1991-10-23

    An account of the Caltech Concurrent Computation Program (C{sup 3}P), a five year project that focused on answering the question: Can parallel computers be used to do large-scale scientific computations '' As the title indicates, the question is answered in the affirmative, by implementing numerous scientific applications on real parallel computers and doing computations that produced new scientific results. In the process of doing so, C{sup 3}P helped design and build several new computers, designed and implemented basic system software, developed algorithms for frequently used mathematical computations on massively parallel machines, devised performance models and measured the performance of many computers, and created a high performance computing facility based exclusively on parallel computers. While the initial focus of C{sup 3}P was the hypercube architecture developed by C. Seitz, many of the methods developed and lessons learned have been applied successfully on other massively parallel architectures.

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

    SciTech Connect (OSTI)

    ,

    1981-04-01

    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)

  13. Use of an Individual Plant Examination (IPE) to enhance outage management. Phase 1, Interim report

    SciTech Connect (OSTI)

    Putney, B.; Averett, M.; Riley, J.

    1992-10-01

    A comparative emissions study was conducted on combustion products of various solid domestic cooking fuels; the objective was to compare relative levels of organic and inorganic toxic emissions from traditional Pakistani fuels (wood, wood charcoal, and dried animal dung) with manufactured low-rank coal briquettes (Lakhra and Sor-Range coals) under conditions simulating domestic cooking. A small combustion shed 12 m{sup 3} internal volume, air exchange rate 14 h{sup {minus}1} was used to simulate south Asian cooking rooms. 200-g charges of the various fueb were ignited in an Angethi stove located inside the shed, then combusted to completion; effluents from this combustion were monitored as a function of time. Measurements were made of respirable particulates, volatile and semi-volatile organics, CO, SO{sub 2}, and No{sub x}. Overall it appears that emissions from coal briquettes containing combustion amendments (slaked lime, clay, and potassium nitrate oxidizer) are no greater than emissions Erom traditional fuels, and in some cases are significantly lower; generally, emissions are highest for afl fuels in the early stages of combustion.

  14. A Tow-Level Progressive Damage for Simulating Carbon-Fiber Textile Composites: Interim Report

    SciTech Connect (OSTI)

    Zywicz, E.

    2000-07-01

    A numerical approach to model the elasto-plastic and tensile damage response of tri-axially braided carbon-fiber polymeric-matrix composites is developed. It is micromechanically based and consists of a simplified unit cell geometry, a plane-stress tow-level constitutive relationship, a one-dimensional undulation constitutive law, and a non-traditional shell element integration rule. The braided composite lamina is idealized as periodic in the plane, and a simplified three-layer representative volume (RV) is assembled from axial and braider tows and pure resin regions. The constituents in each layer are homogenized with an iso-strain assumption in the fiber-direction and an iso-stress condition in the other directions. In the upper and lower layers, the fiber-direction strain is additively decomposed into an undulation and a tow portion. A finite-deformation tow model predicts the plane-stress tow response and is coupled to the undulation constitutive relationship. The overall braid model is implemented in DYNA3D and works with traditional shell elements. The finite-deformation tow constitutive relationship is derived from the fiber elasticity and the isotropic elasto-plastic power-law hardening matrix response using a thermodynamic framework and simple homogenization assumptions. The model replicates tensile damage evolution, in a smeared sense, parallel and perpendicular to the fiber axis and is regularized to yield mesh independent results. The tow-level model demonstrates reasonable agreement, prior to damage, with detailed three-dimensional FE (finite element) elasto-plastic simulations of aligned, periodically arranged, uni-directional composites. The 3-layer braid model response is compared with predictions obtained from detailed micromechanical simulations of the braid's unit cell in uni-axial extension, shear, and flexure for three braid angles. The elastic properties show good agreement as does the non-linear response for loadings dominated by the axial tows. In loadings dominated by the braider tow response, the absence of a non-linear undulation model deteriorates the agreement. Nonetheless, the present approach is applicable to a broad range of tri-axially braided composites as well as for unidirectional composites, but presently lacks any compressive failure mechanisms and an adequate non-linear undulation model.

  15. Video Shoot Scope of Work

    Broader source: Energy.gov [DOE]

    Video Shoot Scope of Work, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  16. Reservoir Modeling Working Group Meeting

    Broader source: Energy.gov [DOE]

    Reservoir Modeling working group meeting presentation on May 10, 2012 at the 2012 Peer Review Meeting.

  17. High Temperature Membrane Working Group

    Broader source: Energy.gov [DOE]

    This presentation provides an overview of the High Temperature Membrane Working Group Meeting in May 2007.

  18. Clean Energy Works Oregon (CEWO)

    Broader source: Energy.gov [DOE]

    Presents Clean Energy Works Oregon's program background and the four easy steps to lender selection.

  19. Radiation Safety Work Control Form

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

    Radiation Safety Work Control Form (see instructions on pg-3) Rev. May 2014 Area: Form #: Date: Preliminary Applicability Screen: (a) Will closing the beam line injection stoppers mitigate the radiological hazards introduced by the proposed work? Yes No (b) Can the closed state of the beam line injection stoppers be assured during the proposed work (ie., work does NOT involve injection stoppers or associated HPS)? Yes No If the answers to both questions are yes, the work can be performed safely

  20. COMMISSIONING AND START-UP TESTS OF ALPHA-CONTAMINATED SOLID WASTE SORTING, CEMENTING, AND INTERIM STORAGE FACILITIES AT BELGOPROCESS (BELGIUM)

    SciTech Connect (OSTI)

    GLIBERT, R.C.; NUYT, G.; LAMOTTE, G.; RENARD, CL.; DE GOEYSE, A.; GOETSCHALCKX, R.; GHYS, B.

    2003-02-27

    The alpha-contaminated solid waste generated in Belgium results from past activities in the fuel cycle (R & D +Reprocessing and MOX fabrication pilot plants) and present operation of BELGONUCLEAIRE's MOX fuel fabrication plant. After the main steps in the management of alpha-contaminated solid waste were established, BELGONUCLEAIRE, with the backing of BELGOPROCESS and ONDRAF/NIRAS, started the design and construction of the T & C and interim-storage facilities for this alpha waste. The accumulated solid alpha radwaste containing a mixture of combustible and non-combustible material will be sorted. After sorting, both the accumulated and recently-generated non-combustible alpha waste will be embedded in a cement matrix. The erection of the sorting and cementing units which include glove-boxes and the interim storage building for conditioned packages was completed at BELGOPROCESS, at the beginning of year 2002. Start-up operations for both facilities have been performed. Operating tests of the sorting and cementing units were completed in July 2002 and inactive operation campaigns were started in August 2002. The results of the tests and inactive campaigns are given. Overall testing of the storage building supervised by the Safety Authorities was successfully performed at the end of 202 after completion of the operating tests on the equipment. The present paper summarizes the main information collected during the tests and campaigns, some of which has led to modifications of the equipment originally installed.

  1. 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

    1993-10-01

    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.

  2. Interim PET After Two ABVD Cycles in Early-Stage Hodgkin Lymphoma: Outcomes Following the Continuation of Chemotherapy Plus Radiotherapy

    SciTech Connect (OSTI)

    Simontacchi, Gabriele; Filippi, Andrea Riccardo; Ciammella, Patrizia; Buglione, Michela; Saieva, Calogero; Magrini, Stefano Maria; Livi, Lorenzo; Iotti, Cinzia; Botto, Barbara; Vaggelli, Luca; Re, Alessandro; Merli, Francesco; Ricardi, Umberto

    2015-08-01

    Purpose: This multicenter retrospective study was designed to evaluate the prognostic role of interim fluorodeoxyglucose-labeled positron emission tomography (i-FDG-PET) in a cohort of patients affected with early-stage Hodgkin lymphoma (HL) treated initially with adriamycin, bleomycin, vinblastine, dacarbazine (ABVD) chemotherapy followed by radiation therapy, and to assess the role of chemotherapy continuation plus radiation therapy for i-FDG-PET-positive patients. Methods and Materials: Data from 257 patients were retrieved from 4 hematology and radiation oncology departments. Inclusion criteria were stage I to IIAB HL, “intention-to-treat” AVBD plus radiation therapy, and FDG-PET at diagnosis and after the first 2 ABVD cycles. All i-FDG-PET scans underwent blinded local review by using the Deauville 5-point scoring system; patients were stratified as negative or positive using 2 Deauville score cutoff values, ≥3 or ≥4. Results: Median follow-up time was 56 months (range: 9-163 months); 5-year overall survival (OS) and disease-specific survival (DSS) for the whole cohort were 97.5% and 98.3%, respectively. Five-year progression-free survival (PFS) was 95.6%. After i-FDG-PET revision, 43 of 257 patients (16.7%) had a positive i-FDG-PET (Deauville scores: 3-5). Five-year PFS rates for i-FDG-PET-negative and i-FDG-PET-positive patients were 98.1% and 83.7%, respectively, if using a Deauville score cutoff of 3, and 97.7% and 78.6%, respectively, if using a cutoff of 4 (P=.0001). Five-year OS for i-FDG-PET-negative and i-FDG-PET-positive patients was 98.5% and 93.0%, respectively, if using a cutoff of 3, and 98.6% and 89.3%, respectively, if using a cutoff of 4 (P=.029 and P=.002). At univariate regression analysis, i-FDG-PET positivity was associated with worse OS and PFS. At multivariate analysis, performed only for PFS, i-FDG-PET positivity confirmed its negative impact (P=.002). Conclusions: i-FDG-PET is prognostic for PFS and OS in early-stage HL patients treated with combined modality therapy; the continuation of chemotherapy followed by radiation therapy is able to obtain durable, complete remission in most i-FDG-PET-positive patients.

  3. Erosion Potential of a Burn Site in the Mojave-Great Basin Transition Zone: Interim Summary of One Year of Measurements

    SciTech Connect (OSTI)

    Etyemezian, V.; Shafer, D.; Miller, J.; Kavouras, I.; Campbell, S.; DuBois, D.; King, J.; Nikolich, G.; Zitzer, S.

    2010-05-18

    A historic return interval of 100 years for large fires in deserts in the Southwest U.S. is being replaced by one where fires may reoccur as frequently as every 20 to 30 years. This increase in fires has implications for management of Soil Sub-Project Corrective Action Units (CAUs) for which the Department of Energy, National Nuclear Security Administration Nevada Site office (NNSA/NSO) has responsibility. A series of studies has been initiated at uncontaminated analog sites to better understand the possible impacts of erosion and transport by wind and water should contaminated soil sites burn over to understand technical and perceived risk they might pose to site workers and public receptors in communities around the NTS, TTR, and NTTR; and to develop recommendations for stabilization and restoration after a fire. The first of these studies was undertaken at the Jacob fire, a lightning-caused fire approximately 12 kilometers north of Hiko, Nevada, that burned approximately 200 ha between August 6-8, 2008, and is representative of a transition zone on the NTS between the Mojave and Great Basin Deserts, where the largest number of Soil Sub-Project CAUs/CASs are located.

  4. Overview of DOE Production Work

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

    ... FCTO. * The DOE Photoelectrochemical Hydrogen Production Working Group published the Springer Brief in Energy: "Photoelectrochemical Water Splitting: Standards, Experimental ...

  5. Work with Us | Buildings | NREL

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

    Work with Us At NREL, industry, universities, and government agencies have many opportunities to take advantage of our residential and commercial buildings expertise. Here's how you can work with us to improve the energy efficiency of your buildings. NREL's award-winning work with the commercial and public sectors to improve building energy performance is central to its mission. Learn about our awards. Partner with Us You can work with our experts and use NREL's outstanding facilities and

  6. Interim Action Determination

    Energy Savers [EERE]

    Smith Dawson & Andrews Interested Parties - Smith Dawson & Andrews PDF icon 09-03-10_Smith_Dawson_Andrews.pdf More Documents & Publications Interested Parties - ARPA-E / National Association of Manufacturers Interested Parties - Chrystler Interested Parties - Myriant

    WAPA Public Comment Interested Parties - WAPA Public Comment Comments Received in Response to Western Area Power Administration's Federal Register Notice Titled 'Notice of Proposed Program and Request for Public

  7. Interim Action Determination

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

    ... for vitrification in DWPF would result in 0.07 latent cancer fatalities (or, zero) in the offsite population, and 0.11 latent cancer fatalities (or, zero) in the worker population. ...

  8. Interim Chronic Beryllium Disease

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-12-08

    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.

  9. July 2012, Work Force Retention Work Group Status Overview

    Energy Savers [EERE]

    Work Force Retention Work Group Status Overview Accomplishments: 1. Progress on the completion of the 10 CFR 1046 modifications to address barriers to workforce retention. Written response to public comment is being drafted by HS-51. 2. Pro-Force (PF) union representative, Randy Lawson, identified this accomplishment as the single most significant step toward PF workforce retention in over 20 years. 3. Draft re-charter of PF Career Options Committee (PFCOC) to establish a PF Working Group

  10. Working memory, situation models, and synesthesia

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Radvansky, Gabriel A.; Gibson, Bradley S.; McNerney, M. Windy

    2013-03-04

    Research on language comprehension suggests a strong relationship between working memory span measures and language comprehension. However, there is also evidence that this relationship weakens at higher levels of comprehension, such as the situation model level. The current study explored this relationship by comparing 10 grapheme–color synesthetes who have additional color experiences when they read words that begin with different letters and 48 normal controls on a number of tests of complex working memory capacity and processing at the situation model level. On all tests of working memory capacity, the synesthetes outperformed the controls. Importantly, there was no carryover benefitmore » for the synesthetes for processing at the situation model level. This reinforces the idea that although some aspects of language comprehension are related to working memory span scores, this applies less directly to situation model levels. As a result, this suggests that theories of working memory must take into account this limitation, and the working memory processes that are involved in situation model construction and processing must be derived.« less

  11. Working memory, situation models, and synesthesia

    SciTech Connect (OSTI)

    Radvansky, Gabriel A.; Gibson, Bradley S.; McNerney, M. Windy

    2013-03-04

    Research on language comprehension suggests a strong relationship between working memory span measures and language comprehension. However, there is also evidence that this relationship weakens at higher levels of comprehension, such as the situation model level. The current study explored this relationship by comparing 10 grapheme–color synesthetes who have additional color experiences when they read words that begin with different letters and 48 normal controls on a number of tests of complex working memory capacity and processing at the situation model level. On all tests of working memory capacity, the synesthetes outperformed the controls. Importantly, there was no carryover benefit for the synesthetes for processing at the situation model level. This reinforces the idea that although some aspects of language comprehension are related to working memory span scores, this applies less directly to situation model levels. As a result, this suggests that theories of working memory must take into account this limitation, and the working memory processes that are involved in situation model construction and processing must be derived.

  12. Work For Others (Non-Department of Energy Funded Work)

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2001-09-28

    Work for Others (WFO) is the performance of work for non-Department of Energy (DOE) entities by DOE/National Nuclear Security Administration (NNSA) and/or their respective contractor personnel or the use of DOE/NNSA facilities that is not directly funded by DOE appropriations. Cancels DOE O 481.1A.

  13. Work For Others (Non-Department of Energy Funded Work)

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2001-01-03

    Work for Others (WFO) is the performance of work for non-Department of Energy (DOE) entities by DOE/National Nuclear Security Administration (NNSA) and/or their respective contractor personnel or the use of DOE/NNSA facilities that is not directly funded by DOE appropriations. WFO has the following objectives. Cancels DOE O 481.1.

  14. HEADQUARTERS MEDIATION PROGRAM MEDIATION WORKS!

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

    MEDIATION WORKS Mediation helps to build relationships. People solve their own problems ... It Preserves Relationships You resolve your dispute while building a better relationship ...

  15. Module 2- Work Breakdown Structure

    Broader source: Energy.gov [DOE]

    This module defines and illustrates the Work Breakdown Structure (WBS), WBS dictionary, Organizational Breakdown Structure (OBS) and Responsibility Assignment Matrix (RAM).

  16. High Temperature Membrane Working Group

    Broader source: Energy.gov [DOE]

    The High Temperature Membrane Working Group consists of government, industry, and university researchers interested in developing high temperature membranes for fuel cells.

  17. Working with SRNL - Technology Transfer

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

    SRNL GO Tech Briefs Contacts Ombudsman Tech Home SRNL Home Working with SRNL Technology Transfer 2015 SRNL Research and Technology Recognition Reception Click to view the 2015...

  18. Radiation Safety Work Control Form

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

    Radiation Safety Work Control Form (see instructions on pg-3) Rev. May 2014 Area: Form : Date: Preliminary Applicability Screen: (a) Will closing the beam line injection stoppers...

  19. INL @ work: Nuclear Reactor Operator

    ScienceCinema (OSTI)

    Russell, Patty

    2013-05-28

    INL @ work features jobs at the Idaho National Laboratory. Learn more about careers and energy research at INL's facebook site http://www.facebook.com/idahonationallaboratory

  20. WageWorks Screen Shot(s)

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

    WageWorks Screen Shot(s)

  1. Work Authorization System | Department of Energy

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

    Work Authorization System Work Authorization System PDF icon Work Authorization System More Documents & Publications Policy Flash 2014-30 DOE Order 412.1a, Work Authorization ...

  2. September 2012, Work Force Retention Work Group Status Overview

    Energy Savers [EERE]

    Work Force Retention Work Group Status Overview 2 Subgroups: Pro-Force and Non-Pro-Force Pro-Force Subgroup: Accomplishments: 1. Completion of 10 CFR 1046 [Protective Force Personnel Medical, Physical Readiness, Training, and Access Authorization Standards] as a final rule that includes modification efforts to address barriers to workforce retention. 2. Pro-Force (PF) union representative, Randy Lawson, identified this accomplishment as the single most significant step toward PF workforce

  3. Work for Others (Non-Department of Energy Funded Work)

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2005-01-24

    Work for Others is the performance of work for non-Department of Energy (DOE) entities by DOE/National Nuclear Security Administration (NNSA) and/or their respective contractor personnel or the use of DOE/NNSA facilities that is not directly funded by DOE appropriations. Cancels DOE O 481.1B. Certified 1-13-11. Admin Chg 1, dated 3-14-11.

  4. INTERIM REPORT FOR HANFORD TANKS AY-102 & AP-101 EFFECT OF CHEMISTRY & OTHER VARIABLES ON CORROSION & STRESS CORROSION CRACKING

    SciTech Connect (OSTI)

    HARTY, W.M.

    2007-05-05

    The objective of this work is to determine the range of conditions where the tank steel is susceptible to localized corrosion and SCC in simulants for waste in tanks AY-102 and AP-101.

  5. RCRA corrective action: Work plans

    SciTech Connect (OSTI)

    Not Available

    1995-02-01

    This Information Brief describes the work plans that owners/operators may have to prepare in conjunction with the performance of corrective action for compliance with RCRA guidelines. In general, the more complicated the performance of corrective action appears from the remedial investigation and other analyses, the more likely it is that the regulator will impose work plan requirements. In any case, most owner/operators will prepare work plans in conjunction with the performance of corrective action processes as a matter of best engineering management practices.

  6. Get Access to Work Onsite

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

    Get Access to Work Onsite Print The following process MUST be completed online by new and returning users at least TWO WEEKS prior to arrival at the ALS. Not a U.S. citizen? Please...

  7. Utility Security & Resiliency: Working Together

    Broader source: Energy.gov [DOE]

    Presentation—given at the Federal Utility Partnership Working Group (FUPWG) Fall 2008 meeting—discusses Edison Electric Institute (EEI), including its key security objectives, key activities, cybersecurity activities, and spare transformer equipment program (STEP).

  8. Attachment 1 - Performance Work Statement

    National Nuclear Security Administration (NNSA)

    including TTR. Waste acceptance services will be performed at the NNSS and at waste generator sites. DE-SOL-0005982 Attachment 1 Page 1 2. Scope of Work 2.1 Requirement: The EPS...

  9. FY 1994 Annual Work Plan

    SciTech Connect (OSTI)

    Not Available

    1993-09-30

    In accordance with the Inspector General`s Strategic Planning Policy directive, the Office of Inspector General (OIG) annually updates its Strategic Plan with budgetary and program guidance for the next fiscal year. The program guidance identifies and establishes priorities for OIG coverage of important DOE issues and operations, provides the basis for assigning OIG resources, and is the source for issues covered in Assistant Inspectors General annual work plans. The Office of the Assistant Inspector General for Audits (AIGA) publishes an Annual Work Plan in September of each year. The plan includes the OIG program guidance and shows the commitment of resources necessary to accomplish the assigned work and meet our goals. The program guidance provides the framework within which the AIGA work will be planned and accomplished. Audits included in this plan are designed to help insure that the requirements of our stakeholders have been considered and blended into a well balanced audit program.

  10. Recovery Act Funds at Work

    Broader source: Energy.gov [DOE]

    Funds from the American Recovery and Reinvestment Act of 2009 (Recovery Act) are being put to work to improve safety, reliability, and service in systems across the country. Here are case studies from a variety of Recovery Act programs.

  11. BEDES Strategic Working Group Recommendations

    Broader source: Energy.gov [DOE]

    The BEDES Strategic Working Group Recommendations document is a guide to how the BEDES Dictionary can be brought to market and provide the services for which it was designed.

  12. BEDES Strategic Working Group Recommendations

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

    Building Energy Data Exchange Specification: Strategic Working Group Recommendations Rick Diamond, Robin Mitchell, Andrea Mercado, Shankar Earni, and Lindsay Holiday Lawrence Berkeley National Laboratory Jonathan Raab, Raab Associates October 27, 2014 Disclaimer This document was prepared as an account of work sponsored by the United States Government. While this document is believed to contain correct information, neither the United States Government nor any agency thereof, nor The Regents of

  13. HEADQUARTERS MEDIATION PROGRAM MEDIATION WORKS!

    Energy Savers [EERE]

    HEADQUARTERS MEDIATION PROGRAM MEDIATION WORKS! Mediation helps to strengthen relationships. People solve their own problems by looking to the future, rather than finding fault with the past. YOU (the participant involved) make the decisions. * Mediation often works in conjunction with other dispute resolution processes, such as grievances or equal employment opportunity (EEO) complaints. However, mediation does NOT forestall established timeframes within those processes, nor does it constitute

  14. Work with Us | Bioenergy | NREL

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

    Work with Us NREL provides partnerships and collaboration in the research and development of bioenergy including bio-based energy, fuels, and products. Woman in front of monitor displaying line graph in industrial facility; other workers in background. Leverage the expertise of our research staff and the efficiency of working in our world-class facilities. Contact Us Robert Baldwin Partnership and Business Development Email | 303-384-6858 Richard Bolin Partnership and Business Development Email

  15. AEO2016 Electricity Working Group

    U.S. Energy Information Administration (EIA) Indexed Site

    Office of Electricity, Coal, Nuclear, and Renewables Analysis December 8, 2015 | Washington, DC AEO2016 Electricity Working Group WORKING GROUP PRESENTATION FOR DISCUSSION PURPOSES DO NOT QUOTE OR CITE AS RESULTS ARE SUBJECT TO CHANGE What to look for: Electricity sector in AEO2016 * Inclusion of EPA final Clean Power Plan in Reference Case * Updated cost estimates for new generating technologies * Major data update on existing coal plant status: MATS- compliant technology or retirement

  16. Submitting Work | The Ames Laboratory

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

    Submitting Work Customers may directly contact the supervisor of the required service area to discuss the technical details of proposed projects. Iowa State University requestors need to bring an Intramural Purchase Order (IPO) with them from their departmental office to request services. After the technical details of the project are known, a cost estimate is prepared. Ames Laboratory operations work less than $1,000 is submitted directly to the shop using the Engineering Services Shop -

  17. Shell Measures

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

    New Commercial Program Development Commercial Current Promotions Industrial Federal Agriculture BPA is working on improved program structures that will support utilities in...

  18. ARM - Measurements

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

    Abstract Full Proposal (PDF, 886K) Collaborations Meetings CLOWD Working Group News Discovery Channel Earth Live Blog News & Press RACORO Backgrounder (PDF, 528K) Contacts...

  19. file://\\Bellview\TeamWorks\TRUTeamWorks.htm

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

    8/03 TRU TeamWorks will resume printing on January 8, 2004 | Shipments expected this we December 18, 2003 The Big Story: It's a wrap - 2003 Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e- mail. WIPP Shipments (as of 12/18/03 at 8:14 a.m.) Shipments scheduled to arrive at

  20. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    | NRC Officials Visit WIPP Tod A weekly e-newsletter for the Waste Isolation Pilot Plant team September 25, 2003 The Big Story Recertification - a work in progress Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 9-25-03 at 7:16 a.m.) 21 Shipments

  1. Work for Others (Non-Department of Energy Funded Work)

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2005-01-24

    Work for Others is the performance of work for non-Department of Energy (DOE) entities by DOE/National Nuclear Security Administration (NNSA) and/or their respective contractor personnel or the use of DOE/NNSA facilities that is not directly funded by DOE appropriations. Cancels DOE O 481.1B. Certified 1-13-11. Admin Chg 1, dated 3-14-11, cancels DOE O 481.1C. Admin Chg 2, dated 3-9-15, cancels DOE O 481.1C Admin Chg 1

  2. WPN 15-4 Quality Work Plan Requirement Update

    Energy Savers [EERE]

    WEATHERIZATION PROGRAM NOTICE 15-4 EFFECTIVE DATE: October 21, 2014 SUBJECT: Quality Work Plan Requirement Update PURPOSE: This guidance provides updates to WPN 14-4 issued December 2, 2013. This guidance supersedes 14-4 and describes requirements to support and verify quality work in the Department of Energy's (DOE) Weatherization Assistance Program (WAP). It defines what constitutes a quality installation of weatherization measures, outlines how those measures are inspected and validated, and

  3. 2006 High Temperature Membrane Working Group Meeting Archives | Department

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

    of Energy 6 High Temperature Membrane Working Group Meeting Archives 2006 High Temperature Membrane Working Group Meeting Archives View 2006 meeting presentations from the High Temperature Membrane Working Group. September 14, 2006, San Francisco, California Agenda Minutes Discussion Overview, James Fenton, University of Central Florida Membrane Performance and Durability Overview for Automotive Fuel Cell Applications, Tom Greszler, GM Measuring Physical Properties of Polymer Electrolyte

  4. Enterprise Assessments Operational Awareness Record of Observations of the Design and Modification Progress of the Waste Isolation Pilot Plant Underground Interim Ventilation System and Supplemental Ventilation System November 2015

    Energy Savers [EERE]

    EA Operational Awareness Record Report Number: EA-WIPP-IVS/SVS-2015-11-15 Site: Waste Isolation Pilot Plant (WIPP) Subject: Observations of the design and modification progress of the WIPP Underground Interim Ventilation System and Supplemental Ventilation System Dates of Activity: 11/15/2015 - 11/19/2015 Report Preparer: Jeff Snook Activity Description / Purpose: The Office of Environment, Safety and Health Assessments within the Office of Enterprise Assessments (EA) is reviewing the design,

  5. ARM - Measurement -

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

    govMeasurements ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Measurement : Categories Instruments The above measurement is considered scientifically relevant for the following instruments. Refer to the datastream (netcdf) file headers of each instrument for a list of all available measurements, including those recorded for diagnostic or quality assurance purposes. Field Campaign Instruments UV-MFRSR : Ultraviolet

  6. CFCC working group meeting: Proceedings

    SciTech Connect (OSTI)

    1997-12-31

    This report is a compilation of the vugraphs presented at this meeting. Presentations covered are: CFCC Working Group; Overview of study on applications for advanced ceramics in industries for the future; Design codes and data bases: The CFCC program and its involvement in ASTM, ISO, ASME, and military handbook 17 activities; CFCC Working Group meeting (McDermott Technology); CFCC Working Group meeting (Textron); CFCC program for DMO materials; Developments in PIP-derived CFCCs; Toughened Silcomp (SiC-Si) composites for gas turbine engine applications; CFCC program for CVI materials; Self-lubricating CFCCs for diesel engine applications; Overview of the CFCC program`s supporting technologies task; Life prediction methodologies for CFCC components; Environmental testing of CFCCs in combustion gas environments; High-temperature particle filtration ORNL/DCC CRADA; HSCT CMC combustor; and Case study -- CFCC shroud for industrial gas turbines.

  7. Coiled tubing working life prediction

    SciTech Connect (OSTI)

    Wu, J.

    1995-12-31

    Failure of coiled tubing, due to the repeated bending and plastic deformation of coiled tubing on and off the reel and gooseneck, is of great concern in coiled tubing operations. This paper discusses the coiled tubing working life based on one of the coiled tubing life models published in the literature, and compares the results with other models. Certain agreements are found among these models. A group of curves is presented to illustrate the coiled tubing working life affected by coiled tubing size and wall thickness, internal pressure, yield strength, reel diameter, gooseneck radius, operation condition (corrosion) and butt-welded connection (stress concentration). The results show that coiled tubing life can be greatly increased by increasing CT wall thickness and CT strength, while the coiled tubing working life decreases under high internal pressure, corrosion, and butt-weld conditions. These curves can be easily used in estimating coiled tubing life for the field use.

  8. Long working distance interference microscope

    DOE Patents [OSTI]

    Sinclair, Michael B.; DeBoer, Maarten P.; Smith, Norman F.

    2004-04-13

    Disclosed is a long working distance interference microscope suitable for three-dimensional imaging and metrology of MEMS devices and test structures on a standard microelectronics probe station. The long working distance of 10-30 mm allows standard probes or probe cards to be used. This enables nanometer-scale 3-D height profiles of MEMS test structures to be acquired across an entire wafer. A well-matched pair of reference/sample objectives is not required, significantly reducing the cost of this microscope, as compared to a Linnik microinterferometer.

  9. Get Access to Work Onsite

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

    Get Access to Work Onsite Print The following process MUST be completed online by new and returning users at least TWO WEEKS prior to arrival at the ALS. Not a U.S. citizen? Please look at Documents for Foreign Nationals well ahead of your visit. Bring all relevant documents to the ALS in order to complete your registration. NOTE: Users who are citizens of, or were born in, T4 countries (Cuba, Iran, Sudan, and Syria) need DOE permission to work at the ALS, a process which can take 4-6 months to

  10. License Amendment Request for Storing Exelon Sister Nuclear Stations Class B/C LLRW in the LaSalle Station Interim Radwaste Storage Facility - 13620

    SciTech Connect (OSTI)

    Azar, Miguel; Gardner, Donald A.; Taylor, Edward R.

    2013-07-01

    Exelon Nuclear (Exelon) designed and constructed an Interim Radwaste Storage Facility (IRSF) in the mid-1980's at LaSalle County Nuclear Station (LaSalle). The facility was designed to store low-level radioactive waste (LLRW) on an interim basis, i.e., up to five years. The primary reason for the IRSF was to offset lack of disposal in case existing disposal facilities, such as the Southeast Compact's Barnwell Disposal Facility in Barnwell, South Carolina, ceased accepting radioactive waste from utilities not in the Southeast Compact. Approximately ninety percent of the Radwaste projected to be stored in the LaSalle IRSF in that period of time was Class A, with the balance being Class B/C waste. On July 1, 2008 the Barnwell Disposal Facility in the Southeast Compact closed its doors to out of- compact Radwaste, which precluded LaSalle from shipping Class B/C Radwaste to an outside disposal facility. Class A waste generated by LaSalle is still able to be disposed at the 'Envirocare of Utah LLRW Disposal Complex' in Clive, Utah. Thus the need for utilizing the LaSalle IRSF for storing Class B/C Radwaste for an extended period, perhaps life-of-plant or more became apparent. Additionally, other Exelon Midwest nuclear stations located in Illinois that did not build an IRSF heretofore also needed extended Radwaste storage. In early 2009, Exelon made a decision to forward Radwaste from the Byron Nuclear Station (Byron), Braidwood Nuclear Station (Braidwood), and Clinton Nuclear Station (Clinton) to LaSalle's IRSF. As only Class B/C Radwaste would need to be forwarded to LaSalle, the original volumetric capacity of the LaSalle IRSF was capable of handling the small number of additional expected shipments annually from the Exelon sister nuclear stations in Illinois. Forwarding Class B/C Radwaste from the Exelon sister nuclear stations in Illinois to LaSalle would require an amendment to the LaSalle Station operating license. Exelon submitted the License Amendment Request (LAR) to NRC on January 6, 2010; NRC approved the LAR on July 21, 2011. A similar decision was made by Exelon in early 2009 to forward Radwaste from Limerick Nuclear Station to its sister station, the Peach Bottom Atomic Power Station; both in Pennsylvania. A LAR submittal to the NRC was also provided and NRC approval was received in 2011. (authors)

  11. Prioritization of groups of substances for Environmental Quality Standard (EQS) development: Recent work with de-icing chemicals

    SciTech Connect (OSTI)

    Lewis, S.; Wilkinson, H.

    1995-12-31

    An estimated 100,000 chemicals are used by mankind, increasing by around 2,000 per year, each with a variety of by-products associated with their manufacture and use, degradation, or destruction. Each has the potential to be released to the environment possibly causing harmful effects, and indeed many cause localized pollution problems for the National Rivers Authority, who is responsible for pollution control. Some of the substances that cause localized pollution problems within the UK require the derivation of an Environmental Quality Standard (EQS). However, derivation of these standards is a lengthy an sometimes costly process. In order to highlight those substances that require an EQS, the National Centre for Environmental Toxicology based at WRc plc, prioritizes groups of substances for EQS development for the NRA. Over recent months, the National Centre for Environmental Toxicology has worked on fire fighting foams, polyelectrolytes, timber treatment chemicals and herbicides for use near water. Its most recent work is on de-icing chemicals. The methodology used to prioritize these pollutants and how the recommendations are used by the NRA will be presented. The process will be illustrated with the current work on de-icing chemicals and interim results will also be available for discussion.

  12. Hydrogen Pipeline Working Group | Department of Energy

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

    Pipeline Working Group Hydrogen Pipeline Working Group The Hydrogen Pipeline Working Group of research and industry experts focuses on issues related to the cost, safety, and ...

  13. Working Gas in Underground Storage Figure

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Working Gas in Underground Storage Figure Working Gas in Underground Storage Figure Working Gas in Underground Storage Compared with 5-Year Range Graph....

  14. Policy Memo: Working Effectively with Contractors | Department...

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

    Policy Memo: Working Effectively with Contractors Policy Memo: Working Effectively with Contractors Guidance on working effectively with contractors. PDF icon MAPolicyMemoWorkingw...

  15. LotusWorks | Open Energy Information

    Open Energy Info (EERE)

    LotusWorks Jump to: navigation, search Name: LotusWorks Place: Ireland Product: Engineering, technical and construction management service provider. References: LotusWorks1 This...

  16. ACME solar works | Open Energy Information

    Open Energy Info (EERE)

    ACME solar works Jump to: navigation, search Logo: ACME solar works Name: ACME solar works Address: 20738 Brown Lane Place: Summerdale, Alabama Zip: 36580 Sector: Solar Product:...

  17. Measurement Science

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

    physicist Albert Migliori, having led the development of a powerful tool for ... The body of work that led to the award began with a project to develop Resonant Ultrasound ...

  18. Measurement Science

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

    wins 2016 Joseph F. Keithley Award for Advances in Measurement Science October 15, 2015 Honors to Albert Migliori, developer of resonant ultrasound spectroscopy LOS ALAMOS, N.M., Oct. 15, 2015-Los Alamos National Laboratory physicist Albert Migliori, having led the development of a powerful tool for important measurements in condensed matter physics including superconductivity, is being given the Joseph F. Keithley Award For Advances in Measurement Science, the top instrumentation prize of the

  19. ARM - Measurements

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

    Deployment Operations Measurements SGP Data Plots NASA Data Plots ARM Data Discovery ... SPEC Humidity Diode Laser Hygrometer (DLH) NASA Turbulence AIMMS-20 SPEC Cloud Properties ...

  20. ARM - Measurements

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

    Measurement Instrument Sponsor Aircraft State PositionVelocity @ 10Hz Trimble DSM(tm) AAF PitchRollAzimuth Trimble Advanced Navigation System (TANS)10Hz AAF...

  1. Renewable Electricity Working Group Presentation

    U.S. Energy Information Administration (EIA) Indexed Site

    Renewable Electricity Working Group Chris Namovicz, Renewable Electricity Analysis Team July 9, 2013 Agenda * Review status of AEO 2013 * Discuss new model updates and development efforts for AEO 2014 and future AEOs - Model updates - Policy updates - Planned additions updates - Performance updates * Obtain feedback from stakeholders on any key items that EIA should look at Chris Namovicz, July 9 2 Status of AEO 2013 Chris Namovicz, July 9 * AEO 2013 was released in stages this year - Reference

  2. Working with SRNL - AMC - Industry

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

    Industry The dynamic, long-term relationships that would emerge from this laboratory, industry, and academic collaborative would generate new concepts and approaches that not only "spin in" modern manufacturing methods that support DOE mission success but also "spin out" new innovations to support overall chemical and manufacturing competitiveness within the United States. Technology and innovation are being driven by the need to work smarter to reduce risk. The Advanced

  3. Working with SRNL - AMC - Leadership

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

    The Advanced Manufacturing Collaborative Academia Government Industry AMC Leadership Contact AMC Home SRNL Home Working with SRNL Advanced Manufacturing Collaborative AMC Leadership Charles Meyers Thad Adams Steven Tibrea Charles Meyers 803-725-3020 Chuck.Meyers@srnl.doe.gov Click to view bio Thad Adams 803-725-5510 Thad.Adams@srnl.doe.gov Click to view bio Steven Tibrea 803-725-3978 Steven.Tibrea@srnl.doe.gov Click to view bio

  4. Working with SRNL - Technology Partnerships

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

    SRNL Home SRNL Contacts Media Contacts For information about the Savannah River National Laboratory, contact: Lana Patterson, Communications Coordinator SRNL Executive Communications lana.patterson@srnl.doe.gov 803.725.4396 Technology Transfer For information on working with SRNL in the development and use of new technology, contact: Matthew Biasiny Partnerships and Commercialization matthew.biasiny@srs.gov 803.725.0406 Protocol Office For information pertaining to SRNL business related visits

  5. file://\\Bellview\TeamWorks\TRUTeamWorks.PDF

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

    Total shipments received at WIPP as of 8-25-03: 1,956 | Shipments expected this week: Hanford A weekly e-newsletter for the Waste Isolation Pilot Plant team August 25, 2003 The Big Story INEEL drum fire and Senate Bill S. 1424: questions and answers Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here

  6. file://\\Bellview\TeamWorks\TRUTeamWorks.htm

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

    9/04 Shipments expected this week: RFETS (14), SRS (6) February 5, 2004 The Big Story Southeastern NM Legislative delegation WIPP update Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 2/9/04 at 8:21 a.m.) Shipments scheduled to arrive at WIPP this

  7. file://\\Bellview\TeamWorks\TRUTeamWorks.htm

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

    4/04 Shipments expected for the week of 02/29/04 through 3/6/04: RFETS (14), SRS (6) A weekly e-newsletter for the Waste Isolation Pilot Plant team March 4, 2004 The Big Story Raising crane Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 03/4/04 at 7:51

  8. file://\\Bellview\TeamWorks\TRUTeamWorks.htm

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

    30/03 Shipments expected this week: RFETS (11), SRS (4), Hanford (2) A weekly e-newsletter for the Waste Isolation Pilot Plant team October 30, 2003 ARROW-PAK Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e- mail. WIPP Shipments (as of 10/30/03 at 6:59 a.m.) Shipments

  9. file://\\Bellview\TeamWorks\TRUTeamWorks.htm

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

    6/03 | Shipments expected this week: RFETS (13), SRS (6) | A weekly e-newsletter for the Waste Isolation Pilot Plant team November 6, 2003 The Big Story FY03 cleanup and disposal accomplishments Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of

  10. http://bellview/TeamWorks/TRUTeamWorks.PDF

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

    Thursday, 9/4/03 | Total shipments received at WIPP: 1,978 | Shipments expected this week: Hanford (2), LA A weekly e-newsletter for the Waste Isolation Pilot Plant team September 4, 2003 The Big Story Get ready, set, go for 100 Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e

  11. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    15/04 Shipments expected this week: Hanford (2), NTS (2), RFETS (11), SRS (6) January 15, 2004 The Big Story Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 1/15/04 at 7:09 a.m. Shipments scheduled to arrive at WIPP this week 21 Total shipments

  12. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    2/04 Shipments expected this week: Hanford (3), NTS (2), RFETS (11), SRS (6) January 22, 2004 The Big Story Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 1/22/04 at 7:22 a.m. Shipments scheduled to arrive at WIPP this week 22 Total shipments

  13. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    9/04 Shipments expected this week: NTS (2), RFETS (13), SRS (6) January 29, 2004 The Big Story WTS restructures workforce Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 1/29/04 at 7:14 a.m.) Shipments scheduled to arrive at WIPP this week 21 Total

  14. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    A weekly e-newsletter for the Waste Isolation Pilot Plant team September 18, 2003 The Big Story Characterization Operations completed at ANL-E Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 9-18-03 at 7:17 a.m.) 21 Shipments scheduled to arrive

  15. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    /03 | Shipments expected this week: Hanford (1), RFETS (11), SRS (6) | A weekly e-newsletter for the Waste Isolation Pilot Plant team October 2, 2003 The Big Story Laboratory setup at CEMRC is teamwork in action Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP

  16. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    9/03 | Shipments expected this week: Hanford (1), RFETS (11), SRS (6) | A weekly e-newsletter for the Waste Isolation Pilot Plant team October 9, 2003 The Big Story It's a whole new "WIPP Experience" Topics Characterization News Transportation News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e- mail. WIPP Shipments (as of

  17. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    16/03 | Shipments expected this week: ANL-E (2) , RFETS (11), SRS (6) | A weekly e-newsletter for the Waste Isolation Pilot Plant team October 16, 2003 The Big Story EM-6 to review WIPP baseline Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of

  18. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    3/03 | Shipments expected this week: RFETS (11), SRS (4), Hanford (2) | A weekly e-newsletter for the Waste Isolation Pilot Plant team October 23, 2003 Sealed sources: questions and answers Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 10/23/03

  19. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    13/03 | Shipments expected this week: RFETS (11), SRS (6) | WIPP welcomes new CBFO Deputy Ma A weekly e-newsletter for the Waste Isolation Pilot Plant team November 13, 2003 The Big Story Farewell to a leader Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP

  20. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    20/03 | Shipments expected this week: Hanford (2), RFETS (14), SRS (6) | A weekly e-newsletter for the Waste Isolation Pilot Plant team November 20, 2003 The Big Story WIPP welcomes Lloyd Piper Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of

  1. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    04/03 | Shipments expected this week: Hanford (2), RFETS (11), SRS (3) | December 4, 2003 The Big Story H.R.2754 to usher in change Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments (as of 12/4/03 at 8:05 a.m.) Shipments scheduled to arrive at WIPP this

  2. http://bellview/TeamWorks/TRUTeamWorks.htm

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

    1/03 | Shipments expected this week: Hanford (2), RFETS (11), SRS (3) | December 11, 2003 The Big Story Standardization - a cost saving innovation Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives Back to Main Page WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e- mail. WIPP Shipments (as of 12/11/03 at 7:47 a.m.) Shipments scheduled to arrive

  3. Environmental Justice Interagency Working Group releases "Promising...

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

    Environmental Justice Interagency Working Group releases "Promising Practices for EJ Methodologies in NEPA Reviews" Environmental Justice Interagency Working Group releases ...

  4. Status report. Characterization of Weld Residual Stresses on a Full-Diameter SNF Interim Storage Canister Mockup.

    SciTech Connect (OSTI)

    Enos, David; Bryan, Charles R.

    2015-08-01

    This report documents the mockup specifications and manufacturing processes; the initial cutting of the mockup into three cylindrical pieces for testing and the measured strain changes that occurred during the cutting process; and the planned weld residual stress characterization activities and the status of those activities.

  5. Work Plan - U.S.-India Coal Working Group | Department of Energy

    Energy Savers [EERE]

    Work Plan - U.S.-India Coal Working Group Work Plan - U.S.-India Coal Working Group PDF icon Work Plan - U.S.-India Coal Working Group More Documents & Publications Work Group Telecom (Draft Charters) U.S.-India Coal Working Group Terms of Reference Work Group Leadership Meetings: Transition Elements

  6. THE HIGGS WORKING GROUP: SUMMARY REPORT.

    SciTech Connect (OSTI)

    DAWSON, S.; ET AL.

    2005-08-01

    This working group has investigated Higgs boson searches at the Tevatron and the LHC. Once Higgs bosons are found their properties have to be determined. The prospects of Higgs coupling measurements at the LHC and a high-energy linear e{sup +}e{sup -} collider are discussed in detail within the Standard Model and its minimal supersymmetric extension (MSSM). Recent improvements in the theoretical knowledge of the signal and background processes are presented and taken into account. The residual uncertainties are analyzed in detail. Theoretical progress is discussed in particular for the gluon-fusion processes gg {yields} H(+j), Higgs-bremsstrahlung off bottom quarks and the weak vector-boson-fusion (VBF) processes. Following the list of open questions of the last Les Houches workshop in 2001 several background processes have been calculated at next-to-leading order, resulting in a significant reduction of the theoretical uncertainties. Further improvements have been achieved for the Higgs sectors of the MSSM and NMSSM. This report summarizes our work performed before and after the workshop in Les Houches. Part A describes the theoretical developments for signal and background processes. Part B presents recent progress in Higgs boson searches at the Tevatron collider. Part C addresses the determination of Higgs boson couplings, part D the measurement of tan {beta} and part E Higgs boson searches in the VBF processes at the LHC. Part F summarizes Higgs searches in supersymmetric Higgs decays, part G photonic Higgs decays in Higgs-strahlung processes at the LHC, while part H concentrates on MSSM Higgs bosons in the intense-coupling regime at the LHC. Part I presents progress in charged Higgs studies and part J the Higgs discovery potential in the NMSSM at the LHC. The last part K describes Higgs coupling measurements at a 1 TeV linear e{sup +}e{sup -} collider.

  7. MEASURING PROJECTOR

    DOE Patents [OSTI]

    Franck, J.V.; Broadhead, P.S.; Skiff, E.W.

    1959-07-14

    A semiautomatic measuring projector particularly adapted for measurement of the coordinates of photographic images of particle tracks as prcduced in a bubble or cloud chamber is presented. A viewing screen aids the operator in selecting a particle track for measurement. After approximate manual alignment, an image scanning system coupled to a servo control provides automatic exact alignment of a track image with a reference point. The apparatus can follow along a track with a continuous motion while recording coordinate data at various selected points along the track. The coordinate data is recorded on punched cards for subsequent computer calculation of particle trajectory, momentum, etc.

  8. Mixed Waste Working Group report

    SciTech Connect (OSTI)

    Not Available

    1993-11-09

    The treatment of mixed waste remains one of this country`s most vexing environmental problems. Mixed waste is the combination of radioactive waste and hazardous waste, as defined by the Resource Conservation and Recovery Act (RCRA). The Department of Energy (DOE), as the country`s largest mixed waste generator, responsible for 95 percent of the Nation`s mixed waste volume, is now required to address a strict set of milestones under the Federal Facility Compliance Act of 1992. DOE`s earlier failure to adequately address the storage and treatment issues associated with mixed waste has led to a significant backlog of temporarily stored waste, significant quantities of buried waste, limited permanent disposal options, and inadequate treatment solutions. Between May and November of 1993, the Mixed Waste Working Group brought together stakeholders from around the Nation. Scientists, citizens, entrepreneurs, and bureaucrats convened in a series of forums to chart a course for accelerated testing of innovative mixed waste technologies. For the first time, a wide range of stakeholders were asked to examine new technologies that, if given the chance to be tested and evaluated, offer the prospect for better, safer, cheaper, and faster solutions to the mixed waste problem. In a matter of months, the Working Group has managed to bridge a gap between science and perception, engineer and citizen, and has developed a shared program for testing new technologies.

  9. Workforce Retention Work Group | Department of Energy

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

    Workforce Retention Work Group Workforce Retention Work Group The Workforce Retention Work Group was established to collaboratively address the needs of the Department to maintain a skilled work force in the face of anticipated retirements and to address the specific health and safety concerns of that work force that could impede retention. Due to the broad nature of the issues reflected within this working group, the chartered objectives and outcomes have been moved forward to be worked by the

  10. Measuring Radiation

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

    Measurement Activity SI Units and Prefixes Conversions Safety Around Radiation Sources Types of Radiation Exposure Managing Radiation Emergencies Procedure Demonstration Measurement Activity: How Much Is Present? The size or weight of a container or shipment does not indicate how much radioactivity is in it. The amount of radioactivity in a quantity of material can be determined by noting how many curies of the material are present. This information should be found on labels and/or shipping

  11. Measurement of the absolute \

    SciTech Connect (OSTI)

    Aunion, Jose Luis Alcaraz; /Barcelona, IFAE

    2010-07-01

    This thesis presents the measurement of the charged current quasi-elastic (CCQE) neutrino-nucleon cross section at neutrino energies around 1 GeV. This measurement has two main physical motivations. On one hand, the neutrino-nucleon interactions at few GeV is a region where existing old data are sparse and with low statistics. The current measurement populates low energy regions with higher statistics and precision than previous experiments. On the other hand, the CCQE interaction is the most useful interaction in neutrino oscillation experiments. The CCQE channel is used to measure the initial and final neutrino fluxes in order to determine the neutrino fraction that disappeared. The neutrino oscillation experiments work at low neutrino energies, so precise measurement of CCQE interactions are essential for flux measurements. The main goal of this thesis is to measure the CCQE absolute neutrino cross section from the SciBooNE data. The SciBar Booster Neutrino Experiment (SciBooNE) is a neutrino and anti-neutrino scattering off experiment. The neutrino energy spectrum works at energies around 1 GeV. SciBooNE was running from June 8th 2007 to August 18th 2008. In that period, the experiment collected a total of 2.65 x 10{sup 20} protons on target (POT). This thesis has used full data collection in neutrino mode 0.99 x 10{sup 20} POT. A CCQE selection cut has been performed, achieving around 70% pure CCQE sample. A fit method has been exclusively developed to determine the absolute CCQE cross section, presenting results in a neutrino energy range from 0.2 to 2 GeV. The results are compatible with the NEUT predictions. The SciBooNE measurement has been compared with both Carbon (MiniBoonE) and deuterium (ANL and BNL) target experiments, showing a good agreement in both cases.

  12. ARM Aerosol Working Group Meeting

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

    and MFRSR Measurements ARM STM 2008 Norfolk, VA Connor Flynn 1 , Annette Koontz 1 , Anne Jefferson 2 , Jim Barnard 1 , Sally McFarlane 1 1 Pacific Northwest National Laboratory 2 CIRES, University of Colorado, Boulder Progress towards ARM DOE 2008 Performance Metric 3 & 4 * Produce and make available new continuous time series of aerosol total column depth, based on results from the AMF deployment in Niger, Africa. * Produce and make available new continuous time series of retrieved dust

  13. A study of cryogenic techniques for operating hydrogen masers. Interim report, 1 July 1979-31 January 1980

    SciTech Connect (OSTI)

    Vessot, R.F.C.

    1980-02-01

    Cryogenic Techniques are applied to the Atomic Hydrogen Maser Frequency Standard to extend the storage time of the atoms and reduce the thermal noise accompanying the signal and within the resonance linewidth. Oscillation has been achieved below 25K using wall coatings of frozen CF 4. A pair of new masers is under construction so that frequency stability improvement can be measured. Stability at the 10 to the -16th power level in Delta f/f for averaging time intervals of 1,000 seconds is expected at temperatures below 30K.

  14. 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

    1993-04-01

    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.

  15. Temperature Measurements in the Magnetic Measurement Facility

    SciTech Connect (OSTI)

    Wolf, Zachary

    2010-12-13

    Several key LCLS undulator parameter values depend strongly on temperature primarily because of the permanent magnet material the undulators are constructed with. The undulators will be tuned to have specific parameter values in the Magnetic Measurement Facility (MMF). Consequently, it is necessary for the temperature of the MMF to remain fairly constant. Requirements on undulator temperature have been established. When in use, the undulator temperature will be in the range 20.0 {+-} 0.2 C. In the MMF, the undulator tuning will be done at 20.0 {+-} 0.1 C. For special studies, the MMF temperature set point can be changed to a value between 18 C and 23 C with stability of {+-}0.1 C. In order to ensure that the MMF temperature requirements are met, the MMF must have a system to measure temperatures. The accuracy of the MMF temperature measurement system must be better than the {+-}0.1 C undulator tuning temperature tolerance, and is taken to be {+-}0.01 C. The temperature measurement system for the MMF is under construction. It is similar to a prototype system we built two years ago in the Sector 10 alignment lab at SLAC. At that time, our goal was to measure the lab temperature to {+-}0.1 C. The system has worked well for two years and has maintained its accuracy. For the MMF system, we propose better sensors and a more extensive calibration program to achieve the factor of 10 increase in accuracy. In this note we describe the measurement system under construction. We motivate our choice of system components and give an overview of the system. Most of the software for the system has been written and will be discussed. We discuss error sources in temperature measurements and show how these errors have been dealt with. The calibration system is described in detail. All the LCLS undulators must be tuned in the Magnetic Measurement Facility at the same temperature to within {+-}0.1 C. In order to ensure this, we are building a system to measure the temperature of the undulators to {+-}0.01 C. This note describes the temperature measurement system under construction.

  16. Exascale Hardware Architectures Working Group

    SciTech Connect (OSTI)

    Hemmert, S; Ang, J; Chiang, P; Carnes, B; Doerfler, D; Leininger, M; Dosanjh, S; Fields, P; Koch, K; Laros, J; Noe, J; Quinn, T; Torrellas, J; Vetter, J; Wampler, C; White, A

    2011-03-15

    The ASC Exascale Hardware Architecture working group is challenged to provide input on the following areas impacting the future use and usability of potential exascale computer systems: processor, memory, and interconnect architectures, as well as the power and resilience of these systems. Going forward, there are many challenging issues that will need to be addressed. First, power constraints in processor technologies will lead to steady increases in parallelism within a socket. Additionally, all cores may not be fully independent nor fully general purpose. Second, there is a clear trend toward less balanced machines, in terms of compute capability compared to memory and interconnect performance. In order to mitigate the memory issues, memory technologies will introduce 3D stacking, eventually moving on-socket and likely on-die, providing greatly increased bandwidth but unfortunately also likely providing smaller memory capacity per core. Off-socket memory, possibly in the form of non-volatile memory, will create a complex memory hierarchy. Third, communication energy will dominate the energy required to compute, such that interconnect power and bandwidth will have a significant impact. All of the above changes are driven by the need for greatly increased energy efficiency, as current technology will prove unsuitable for exascale, due to unsustainable power requirements of such a system. These changes will have the most significant impact on programming models and algorithms, but they will be felt across all layers of the machine. There is clear need to engage all ASC working groups in planning for how to deal with technological changes of this magnitude. The primary function of the Hardware Architecture Working Group is to facilitate codesign with hardware vendors to ensure future exascale platforms are capable of efficiently supporting the ASC applications, which in turn need to meet the mission needs of the NNSA Stockpile Stewardship Program. This issue is relatively immediate, as there is only a small window of opportunity to influence hardware design for 2018 machines. Given the short timeline a firm co-design methodology with vendors is of prime importance.

  17. Solution of basic operational problems of water-development works at the Votkinsk hydroproject

    SciTech Connect (OSTI)

    Deev, A. P.; Borisevich, L. A.; Fisenko, V. F.

    2012-11-15

    Basic operational problems of water-development works at the Votkinsk HPP are examined. Measures for restoration of normal safety conditions for the water-development works at the HPP, which had been taken during service, are presented.

  18. TWRS Systems Engineering Working Plan

    SciTech Connect (OSTI)

    Eiholzer, C.R.

    1994-09-16

    The purpose of this Systems Engineering (SE) Working Plan (SEWP) is to describe how the Westinghouse Hanford Company (WHC) Tank Waste Remediation System (TWRS) will implement the SE polity and guidance provided in the Tank Waste Remediation System (TWRS) Systems Engineering Management Plan (SEMP). Sections 2.0 through 4.0 cover how the SE process and management will be performed to develop a technical baseline within TWRS. Section 5.0 covers the plans and schedules to implement the SE process and management within TWRS. Detailed information contained in the TWRS Program SEMP is not repeated in this document. This SEWP and the SE discipline defined within apply to the TWRS Program and new and ongoing TWRS projects or activities, including new facilities and safety. The SE process will be applied to the existing Tank Farm operations where the Richland TWRS Program Office management determines the process appropriate and where value will be added to existing Tank Farm system and operations.

  19. FY 1996 annual work plan

    SciTech Connect (OSTI)

    1995-09-30

    In April 1994, the Department of Energy (DOE) Strategic Plan was issued. This Plan presents the Department`s strategic outlook in response to a changing world. It discusses the Department`s unique capabilities; its mission, vision, and core values; and key customer and stakeholder considerations. The DOE Strategic Plan lists business strategies and critical success factors which are intended to aid the Department in accomplishing its mission and reaching its vision of itself in the future. The Office of Inspector General (OIG) has an important role in carrying out the goals and objectives of the Secretary`s Strategic Plan. The ultimate goal of the OIG is to facilitate positive change by assisting its customers, responsible Government officials, in taking actions to improve programs and operations. The Inspector General annually issues his own Strategic Plan that contains program guidance for the next fiscal year. As part of its responsibility in carrying out the OIG mission, the Office of the Deputy Inspector General for Audit Services (Office of Audit Services) publishes an Annual Work Plan that sets forth audits that are planned for the next fiscal year. Selection of these audits is based on the overall budget of the Department, analyses of trends in Departmental operations, guidance contained in the agency`s strategic plans, statutory requirements, and the expressed needs and audit suggestions of Departmental program managers and OIG managers and staff. This work plan includes audits that are carried over from FY 1995 and audits scheduled to start during FY 1996. Audits included in the plan will be performed by OIG staff.

  20. Smoke hazards resulting from the burning of shipboard paints. Part 3. Interim report, 1 September 1981-31 August 1983

    SciTech Connect (OSTI)

    Williams, F.W.; Powell, E.A.; Zinn, B.T.

    1987-09-18

    Investigations continued to evaluate the hazards caused by smoke formation in shipboard fires. The physical properties of the smoke particulates generated during combustion were determined for two types of paints used by the U.S. Navy in ships and submarines. These were a chlorinated alkyd paint and and intumescent paint. The physical properties measured were particle size distribution, mean particle diameter, mass fraction of fuel converted to particulates, optical density, particle refractive index, and particulate volume fraction. The dependence of these properties on the temperature of the test-chamber atmosphere (room temperature to a maximum of 300/sup 0/C) and the mode of combustion (flamming or smoldering) was determined for both materials. The results of this study indicated that both paints produce smoke with a log-normal particle size distribution during smoldering combustion in the room temperature tests. Optical measurements made during these tests show that both paints produce smoke particulates with mean diameters that vary with time between 0.6 and 1.2 microm. Under these conditions the chlorinated alkyd paint produces pale yellow spherical liquid droplets, while the intumescent paint produces a mixture of light tan and white solid particles.

  1. Applying User Centered Design to Research Work

    SciTech Connect (OSTI)

    Scholtz, Jean; Love, Oriana J.; Pike, William A.; Bruce, Joseph R.; Kim, Dee DH; McBain, Arthur S.

    2014-07-01

    The SuperIdentity (SID) research project is a collaboration between six universities in the UK (Bath, Dundee, Kent, Leicester, Oxford, and Southampton) and the Pacific Northwest National Laboratory (PNNL). SID offers an innovative and exciting new approach to the concept of identity. The assumption underlying our hypothesis is that while there may be many dimensions to an identity - some more stable than others - all should ultimately reference back to a single core identity or a 'SuperIdentity.' The obvious consequence is that identification is improved by the combination of measures. Our work at PNNL has focused on the developing use cases to use in developing a model of identity and in developing visualizations for both researchers to explore the model and in the future for end users to use in determining various paths that may be possible to obtain various identity attributes from a set that is already known.

  2. Standing Technical Committee Working Sessions | Department of Energy

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

    Standing Technical Committee Working Sessions Standing Technical Committee Working Sessions The strategic planning process charts the course for the U.S. Department of Energy (DOE) Building America program's efforts to widely deploy new integrated packages of energy-saving measures in new and existing homes. Following are presentations from the program's 2012 Residential Energy Efficiency Stakeholder Meeting. PDF icon space_conditioning_stc.pdf PDF icon ahem_stc.pdf PDF icon hot_water_stc.pdf

  3. Calibration of a Neutron Hydroprobe for Moisture Measurements in Small-Diameter Steel-Cased Boreholes

    SciTech Connect (OSTI)

    Ward, Anderson L.; Wittman, Richard S.

    2009-08-01

    Computation of soil moisture content from thermalized neutron counts for the T-Farm Interim cover requires a calibration relationship but none exists for 2-in tubes. A number of calibration options are available for the neutron probe, including vendor calibration, field calibration, but none of these methods were deemed appropriate for the configuration of interest. The objective of this work was to develop a calibration relation for converting neutron counts measured in 2-in access tubes to soil water content. The calibration method chosen for this study was a computational approach using the Monte Carlo N-Particle Transport Code (MCNP). Model calibration was performed using field measurements in the Hanford calibration models with 6-in access tubes, in air and in the probe shield. The bet-fit model relating known water content to measured neutron counts was an exponential model that was essentially equivalent to that currently being used for 6-in steel cased wells. The MCNP simulations successfully predicted the neutron count rate for the neutron shield and the three calibration models for which data were collected in the field. However, predictions for air were about 65% lower than the measured counts . This discrepancy can be attributed to uncertainties in the configuration used for the air measurements. MCNP-simulated counts for the physical models were essentially equal to the measured counts with values. Accurate prediction of the response in 6-in casings in the three calibration models was motivation to predict the response in 2-in access tubes. Simulations were performed for six of the seven calibration models as well as 4 virtual models with the entire set covering a moisture range of 0 to 40%. Predicted counts for the calibration models with 2-in access tubes were 40 to 50% higher than in the 6-inch tubes. Predicted counts for water were about 60% higher in the 2-in tube than in the 6-in tube. The discrepancy between the 2-in and 6-in tube can be attributed to the smaller air gap between the probe and the 2-in access tube. The best-fit model relating volumetric water content to count ratio (CR) is of the form e^A x CR^B with A=0.3596 0.0216 and B=0.4629 0.0629 and r^2= 0.9998. It is recommended that the calibration function based on the count ratio, rather than raw counts, be used to avoid the effects of electronic noise in the probe that may arise due to the conditions at the time of measurement. These results suggest that the MCNP code can be used to extend calibrations for the neutron probe to different conditions including access tube size as well as composition without the need to construct additional physical models.

  4. Naval Air Warfare Center, Aircraft Division at Warminster Environmental Materials Program. Phase 1. Interim report, October 1989-May 1992

    SciTech Connect (OSTI)

    Spadafora, S.J.; Hegedus, C.R.; Clark, K.J.; Eng, A.T.; Pulley, D.F.

    1992-06-24

    With the recent increase in awareness about the environment, there is an expanding concern of the deleterious effects of current materials and processes. Federal, state and local environmental agencies such as the EPA, State Air Resource Boards and local Air Quality Management Districts (AQMD) have issued legislation that restrict or prohibit the use and disposal of hazardous materials. National and local laws like the Clean Air and Clean Water Acts, Resource Conservation and Recovery Act, and AQMD regulations are examples of rules that govern the handling and disposal of hazardous materials and waste. The Department of Defense (DoD), in support of this effort, has identified the major generators of hazardous materials and hazardous waste to be maintenance depots and operations, particularly cleaning, pretreating, plating, painting and paint removal processes. Reductions of waste in these areas has been targeted as a primary goal in the DOD. The Navy is committed to significantly reducing its current hazardous waste generation and is working to attain a near zero discharge of hazardous waste by the year 2000. In order to attain these goals, the Naval Air Warfare Center Aircraft Division at Warminster has organized and is carrying out a comprehensive program in cooperation with the Naval Air Systems Command, the Air Force and the Department of Energy that deal with the elimination or reduction of hazardous materials. .... Environmental materials, Organic coatings, Inorganic pretreatments, Paint removal techniques, Cleaners, CFC'S.

  5. Graduate Program Time Limits and Work Schedules

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

    Time Limits and Work Schedules Graduate Program Time Limits and Work Schedules Point your career towards Los Alamos Lab: work with the best minds on the planet in an inclusive...

  6. Undergraduate Program Time Limits and Work Schedules

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

    Time Limits and Work Schedules Undergraduate Program Time Limits and Work Schedules Point your career towards Los Alamos Lab: work with the best minds on the planet in an inclusive...

  7. SpringWorks | Open Energy Information

    Open Energy Info (EERE)

    SpringWorks Jump to: navigation, search Name: SpringWorks Place: Minnetonka, Minnesota Zip: 55343-8684 Product: SpringWorks was created to discover and nurture incubation companies...

  8. Working with Modules within Perl and Python

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

    Working with Modules within Perl and Python Working with Modules within Perl and Python It can often be convenient to work with the modules system from within perl or python...

  9. Federal Utility Partnership Working Group Meeting: Washington...

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

    Presentation-given at the Fall 2012 Federal Utility Partnership Working Group (FUPWG) ... More Documents & Publications Federal Utility Partnership Working Group Meeting: ...

  10. Federal Utility Partnership Working Group Seminar: Chairman's...

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

    Seminar: Chairman's Corner Federal Utility Partnership Working Group Seminar: Chairman's Corner Presentation covers the Federal Utility Partnership Working Group Seminar: Chairman's ...

  11. Federal Utility Partnership Working Group Meeting: Chairman's...

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

    Federal Utility Partnership Working Group Meeting: Chairman's Corner Presentation-given at the April 2012 Federal Utility Partnership Working Group (FUPWG) meeting-lists key ...

  12. Federal Utility Partnership Working Group Meeting: Washington...

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

    Federal Utility Partnership Working Group Meeting: Washington Update PDF icon fupwgspring12unruh.pdf More Documents & Publications Federal Utility Partnership Working Group ...

  13. Federal Utility Partnership Working Group Meeting Chairman's...

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

    Federal Utility Partnership Working Group Meeting Chairman's Corner Presentation-given at the Fall 2012 Federal Utility Partnership Working Group (FUPWG) meeting-lists key utility ...

  14. Working with Schools | Department of Energy

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

    Schools Working with Schools Better Buildings Residential Network Marketing & Outreach Peer Exchange Call Series: Working with Schools, Call Slides and Summary, April 24, 2014. PDF ...

  15. Working with Condominium Owners and Associations | Department...

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

    Working with Condominium Owners and Associations Better Buildings Neighborhood Program Multifamily and Low-Income Peer Exchange Call: Working with Condominium Owners and ...

  16. Nanoscale Chemical Imaging of a Working Catalyst

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

    Nanoscale Chemical Imaging of a Working Catalyst Nanoscale Chemical Imaging of a Working Catalyst Print Wednesday, 28 January 2009 00:00 The heterogeneous catalysts used in most ...

  17. PIA - Radiological Work Permit | Department of Energy

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

    PIA - Radiological Work Permit PDF icon PIA - Radiological Work Permit More Documents & Publications PIA - Bonneville Power Adminstration Ethics Helpline Occupational Medical ...

  18. Federal Utility Partnership Working Group Utility Partners

    Broader source: Energy.gov [DOE]

    Federal Utility Partnership Working Group (FUPWG) utility partners are eager to work closely with Federal agencies to help achieve energy management goals.

  19. Washington Working Natural Gas Underground Storage Capacity ...

    Gasoline and Diesel Fuel Update (EIA)

    Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Washington Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Year Jan Feb Mar Apr May Jun...

  20. Mississippi Working Natural Gas Underground Storage Capacity...

    Gasoline and Diesel Fuel Update (EIA)

    Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Mississippi Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Year Jan Feb Mar Apr May Jun...

  1. Pennsylvania Working Natural Gas Underground Storage Capacity...

    Gasoline and Diesel Fuel Update (EIA)

    Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Pennsylvania Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Year Jan Feb Mar Apr May...

  2. Brad Foote Gear Works | Open Energy Information

    Open Energy Info (EERE)

    Brad Foote Gear Works Jump to: navigation, search Name: Brad Foote Gear Works Place: Cicero, Illinois Zip: 60804-1404 Sector: Wind energy Product: Gearing systems manufacturer...

  3. DOE Contractor Work Force Restructuring Approval Thresholds

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

    Contractor Work Force Restructuring Approval Thresholds Up to 100 employees Contractor can ... to provide approval for NNSA work force restructurings in consultation with LM 501 ...

  4. REGULATORY COOPERATION COUNCIL - WORK PLANNING FORMAT: Natural...

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

    COUNCIL - WORK PLANNING FORMAT: Natural Gas Use in Transportation PDF icon RCC Workplan NGV.PDF More Documents & Publications REGULATORY COOPERATION COUNCIL - WORK PLANNING ...

  5. California Working Natural Gas Underground Storage Capacity ...

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Working Natural Gas Underground Storage Capacity (Million Cubic Feet) California Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Year Jan Feb Mar Apr May Jun...

  6. Nano Design Works | Argonne National Laboratory

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

    Nano Design Works Nano Design Works (NDW) capitalizes on the power of nanotechnology and provides services to strengthen its impact. With expertise in nanomaterials, computing,...

  7. Design report for the interim waste containment facility at the Niagara Falls Storage Site. [Surplus Facilities Management Program

    SciTech Connect (OSTI)

    Not Available

    1986-05-01

    Low-level radioactive residues from pitchblende processing and thorium- and radium-contaminated sand, soil, and building rubble are presently stored at the Niagara Falls Storage Site (NFSS) in Lewiston, New York. These residues and wastes derive from past NFSS operations and from similar operations at other sites in the United States conducted during the 1940s by the Manhattan Engineer District (MED) and subsequently by the Atomic Energy Commission (AEC). The US Department of Energy (DOE), successor to MED/AEC, is conducting remedial action at the NFSS under two programs: on-site work under the Surplus Facilities Managemnt Program and off-site cleanup of vicinity properties under the Formerly Utilized Sites Remedial Action Program. On-site remedial action consists of consolidating the residues and wastes within a designated waste containment area and constructing a waste containment facility to prevent contaminant migration. The service life of the system is 25 to 50 years. Near-term remedial action construction activities will not jeopardize or preclude implementation of any other remedial action alternative at a later date. Should DOE decide to extend the service life of the system, the waste containment area would be upgraded to provide a minimum service life of 200 years. This report describes the design for the containment system. Pertinent information on site geology and hydrology and on regional seismicity and meteorology is also provided. Engineering calculations and validated computer modeling studies based on site-specific and conservative parameters confirm the adequacy of the design for its intended purposes of waste containment and environmental protection.

  8. Hadron Colliders Working Group Report

    SciTech Connect (OSTI)

    S. Peggs and M.J. Syphers

    2001-11-08

    The ''point design'' studied this year shows that a staged VLHC (40, {approx} 200 TeV) is feasible, with no insurmountable challenges. Further work can provide a more optimized design, by studying various alternative field strengths (e.g., superferric magnets for Stage 1) for improvements to vacuum, wall impedance, and other major performance parameters. It may be that a ''single-stage'' scenario for accessing higher energies sooner is the correct approach. A next-step design study should be considered to look at the two cases near to and complementary to the 2001 VLHC Design Study. The effectiveness of photon stops and their engineering design need to be addressed in the near future to truly determine if these devices can lead this effort to even higher luminosities and energies. The superbunch approach should continue to be studied, as well as IR designs, new instrumentation and diagnostics, and beam dynamics issues. Finally, a well organized VLHC-motivated beam studies effort should become part of the national program.

  9. Current work in energy analysis

    SciTech Connect (OSTI)

    1998-03-01

    This report describes the work performed at Berkeley Lab most recently. One of the Labs accomplishments is the publication of Scenarios of US Carbon Reductions, an analysis of the potential of energy technologies to reduce carbon emissions in the US. This analysis is described and played a key role in shaping the US position on climate change in the Kyoto Protocol negotiations. The Labs participation in the fundamental characterization of the climate change issue by the IPCC is described. Described also is a study of leaking electricity, which is stimulating an international campaign for a one-watt ceiling for standby electricity losses from appliances. This ceiling has the potential to save two-thirds of the 5% of US residential electricity currently expended on standby losses. The 54 vignettes contained in the report summarize results of research activities ranging in scale from calculating the efficacy of individual lamp ballasts to estimating the cost-effectiveness of the national Energy Star{reg_sign} labeling program, and ranging in location from a scoping study of energy-efficiency market transformation in California to development of an energy-efficiency project in the auto parts industry in Shandong Province, China.

  10. Abstract Measurement

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

    Heat Pump Systems » Absorption Heat Pumps Absorption Heat Pumps Absorption heat pumps are essentially air-source heat pumps driven not by electricity, but by a heat source such as natural gas, propane, solar-heated water, or geothermal-heated water. Because natural gas is the most common heat source for absorption heat pumps, they are also referred to as gas-fired heat pumps. There are also absorption (or gas-fired) coolers available that work on the same principle. Unlike some absorption heat

  11. file://\\troi2\wwwroot\TeamWorks\index.htm

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

    3, 2011 WIPP Quick Facts (As of 12-11-11) 10,214 Shipments received since opening (9,682 CH and 532 RH) 79,468 Cubic meters of waste disposed (79,200 CH and 268 RH) 155,269 Containers disposed in the underground (154,737 CH and 532 RH) Photo at right: CBFO Interim Manager Ed Ziemianski (far right) presented the awards to several of the participants. Also shown from left to right are Debra Hicks and Randy Pettigrew of Pettigrew & Associates; Owen Lofton of the Bureau of Land Management; Hank

  12. Thermodynamic properties of liquefied petroleum gases (LPG). Interim report 15 Aug 75-31 Jan 77 (final)

    SciTech Connect (OSTI)

    Sallet, D.W.; Wu, K.F.

    1980-04-01

    The thermodynamic properties of several liquefied petroleum gases (with particular emphasis on propane) are discussed in detail. It is concluded that the widely used propane data by Stearns and George are too inconsistent and too inaccurate to be used for mass flow calculations of propane and propane mixtures through safety valves of rail tank cars. Accordingly, the thermodynamic properties of propane, propylene, n-butane, and a mixture of 65% (by mole) propane, 25% propylene, and 10% n-butane are recalculated using equations of states proposed by Benedict-Webb-Rubin (BWR) and by Starling. It is shown that Starling's equation results in thermodynamic properties which are more consistent and compare better with measured values than the BWR equation. Thermodynamic data for the four liquefied petroleum gases discussed above are calculated and presented in tabular form. In addition, predictions of pure propane mass flow rates (based upon isentropic), homogeneous equilibrium flow) are given. The influence of the thermodynamic data upon the predicted mass flow rates is demonstrated.

  13. Analysis of fuel relocation for the NRC/PNL Halden assemblies IFA-431, IFA-432, and IFA-513. Interim report

    SciTech Connect (OSTI)

    Williford, R.E.; Mohr, C.L.; Lanning, D.D.; Cunningham, M.E.; Rausch, W.N.

    1980-06-01

    The effects of the thermally-induced cracking and subsequent relocation of UO2 fuel pellets on the thermal and mechanical behavior of light-water reactor fuel rods during irradiation are quantified in this report. Data from the Nuclear Regulatory Commission/Pacific Northwest Laboratory Halden experiments on instrumented fuel assemblies (IFA) IFA-431, IFA-432, and IFA-513 are analyzed. Beginning-of-life in-reactor measurements of fuel center temperatures, linear heat ratings, and cladding axial elongations are used in a new model to solve for the effective thermal conductivity and elastic moduli of the cracked fuel column. The primary assumptions of the new model are that (1) the cracked fuel is in a hydrostatic state of stress in the (r,theta) plane, and that (2) there is no axial slipping between fuel and cladding. Three basic parameters are used to describe the cracked fuel: (1) the crack pattern, (2) the crack roughness, and (3) the fuel surface (gap) roughness. Recommendations are made on refining the model.

  14. WPN 15-4: QUALITY WORK PLAN REQUIREMENT UPDATE

    Broader source: Energy.gov [DOE]

    Effective October 21, 2014: This guidance provides updates to WPN 14-4 issued December 2, 2013. This guidance supersedes 14-4 and describes requirements to support and verify quality work in the Department of Energy’s (DOE) Weatherization Assistance Program (WAP). It defines what constitutes a quality installation of weatherization measures, outlines how those measures are inspected and validated, and prescribes acceptable training and credentialing of workers.

  15. 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

    2011-03-01

    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.

  16. Interpretation of brine-permeability tests of the Salado Formation at the Waste Isolation Pilot Plant site: First interim report

    SciTech Connect (OSTI)

    Beauheim, R.L. ); Saulnier, G.J. Jr.; Avis, J.D. )

    1991-08-01

    Pressure-pulse tests have been performed in bedded evaporites of the Salado Formation at the Waste Isolation Pilot Plant (WIPP) site to evaluate the hydraulic properties controlling brine flow through the Salado. Hydraulic conductivities ranging from about 10{sup {minus}14} to 10{sup {minus}11} m/s (permeabilities of about 10{sup {minus}21} to 10{sup {minus}18} m{sup 2}) have been interpreted from nine tests conducted on five stratigraphic intervals within eleven meters of the WIPP underground excavations. Tests of a pure halite layer showed no measurable permeability. Pore pressures in the stratigraphic intervals range from about 0.5 to 9.3 MPa. An anhydrite interbed (Marker Bed 139) appears to be one or more orders of magnitude more permeable than the surrounding halite. Hydraulic conductivities appear to increase, and pore pressures decrease, with increasing proximity to the excavations. These effects are particularly evident within two to three meters of the excavations. Two tests indicated the presence of apparent zero-flow boundaries about two to three meters from the boreholes. The other tests revealed no apparent boundaries within the radii of influence of the tests, which were calculated to range from about four to thirty-five meters from the test holes. The data are insufficient to determine if brine flow through evaporites results from Darcy-like flow driven by pressure gradients within naturally interconnected porosity or from shear deformation around excavations connecting previously isolated pores, thereby providing pathways for fluids at or near lithostatic pressure to be driven towards the low-pressure excavations. Future testing will be performed at greater distances from the excavations to evaluate hydraulic properties and processes beyond the range of excavation effects.

  17. A Measurement

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

    Neutrino-Induced Charged-Current Neutral Pion Production by Robert H. Nelson B.S., University of California, Santa Barbara, 2003 A thesis submitted to the Faculty of the Graduate School of the University of Colorado in partial fulfillment of the requirements for the degree of Doctor of Philosophy Department of Physics 2010 This thesis entitled: A Measurement of Neutrino-Induced Charged-Current Neutral Pion Production written by Robert H. Nelson has been approved for the Department of Physics

  18. Available Measurement

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

    Instruments on the Twin Otter Available Measurement Instrument PI or Group Total aerosol number concentration Condensation Particle Counters (CPC) Up to 3 CIRPAS Aerosol/cloud size distribution d=0.1 - 2.5 µm d=0.8 - 80 µm Passive Cavity Aerosol Spectrometer Probe (PCASP) Cloud Aerosol and Precipitation Spectrometer (CAPS) CIRPAS Aerosol/cloud size distribution d=2.5 - 50 µm Forward Scattering Spectrometer Probe (FSSP) CIRPAS Cloud liquid water content Gerber PVM Johnson probe on CAPS CIRPAS

  19. Quality Work Plan Inspection and Monitoring Requirement

    Broader source: Energy.gov [DOE]

    Inspection and monitoring requirements for Weatherization Assistance Program's comprehensive Quality Work Plan.

  20. Working Gas in Underground Storage Figure

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Gas in Underground Storage Figure Working Gas in Underground Storage Compared with 5-Year Range Graph...