Sample records for testing activity requirements

  1. Gas Test Loop Functional and Technical Requirements

    SciTech Connect (OSTI)

    Glen R. Longhurst; Soli T. Khericha; James L. Jones

    2004-09-01T23:59:59.000Z

    This document defines the technical and functional requirements for a gas test loop (GTL) to be constructed for the purpose of providing a high intensity fast-flux irradiation environment for developers of advanced concept nuclear reactors. This capability is needed to meet fuels and materials testing requirements of the designers of Generation IV (GEN IV) reactors and other programs within the purview of the Advanced Fuel Cycle Initiative (AFCI). Space nuclear power development programs may also benefit by the services the GTL will offer. The overall GTL technical objective is to provide developers with the means for investigating and qualifying fuels and materials needed for advanced reactor concepts. The testing environment includes a fast-flux neutron spectrum of sufficient intensity to perform accelerated irradiation testing. Appropriate irradiation temperature, gaseous environment, test volume, diagnostics, and access and handling features are also needed. This document serves to identify those requirements as well as generic requirements applicable to any system of this kind.

  2. On the Strategy and Requirements for Neutronics Testing in ITER

    SciTech Connect (OSTI)

    Youssef, M.Z. [University of California-Los Angeles (United States); Sawan, M.E. [University of Wisconsin-Madison (United States)

    2005-05-15T23:59:59.000Z

    Neutronics testing is among the several types of fusion technology testing scheduled to be performed in ITER. The three ports assigned for testing will test several blanket concepts proposed by the various parties with test blanket modules (TBM) that utilize different breeders and coolants. Nevertheless, neutronics issues to be resolved in ITER-TBM are generic in nature and are important to each TBM type. Dedicated neutronics tests specifically address the accuracy involved in predicting key neutronics parameters such as tritium production rate, TPR, volumetric heating rate, induced activation and decay heat, and radiation damage to the reactor components. In this paper, we address some strategies for performing the neutronics tests. Tritium self-sufficiency cannot be confirmed by testing in ITER, however, the testing can provide valuable information regarding the main parameters needed to assess the feasibility of achieving tritium self-sufficiency. The paper also addresses the operational requirement (i.e. flux and fluence) as well as the geometrical requirement of the test module (i.e. minimum size) in order to have meaningful and useful tests. Measured neutronics data require high spatial resolution. This necessitates that the measured quantity be as flat as possible in the innermost locations inside the test module. This requirement has been confirmed in the present work based on results from two-dimensional calculations. The US and Japan solid breeder test blanket modules are placed inside half a port in ITER. The R-{theta} model used accounts for the presence of the ITER shielding blanket and the surrounding frame of the port.

  3. Methane Activation Structural and Mechanistic Requirements for

    E-Print Network [OSTI]

    Iglesia, Enrique

    Methane Activation Structural and Mechanistic Requirements for Methane Activation and Chemical and petrochemical processes and in fuel cells. The strong bonds in CH4 (439 kJmolÀ1 [1] ) and the endothermic nature by BP as part of the Methane Conversion Cooperative Research Program at the University of California

  4. Advanced Vehicle Testing Activity (AVTA) ? PHEV Evaluations...

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

    1.pdf More Documents & Publications Advanced Vehicle Testing Activity (AVTA) - Vehicle Testing and Demonstration Activities AVTA PHEV Demonstrations and Testing Argonne...

  5. Hydrogen ICE Vehicle Testing Activities

    SciTech Connect (OSTI)

    J. Francfort; D. Karner

    2006-04-01T23:59:59.000Z

    The Advanced Vehicle Testing Activity teamed with Electric Transportation Applications and Arizona Public Service to develop and monitor the operations of the APS Alternative Fuel (Hydrogen) Pilot Plant. The Pilot Plant provides 100% hydrogen, and hydrogen and compressed natural gas (H/CNG)-blended fuels for the evaluation of hydrogen and H/CNG internal combustion engine (ICE) vehicles in controlled and fleet testing environments. Since June 2002, twenty hydrogen and H/CNG vehicles have accumulated 300,000 test miles and 5,700 fueling events. The AVTA is part of the Department of Energy’s FreedomCAR and Vehicle Technologies Program. These testing activities are managed by the Idaho National Laboratory. This paper discusses the Pilot Plant design and monitoring, and hydrogen ICE vehicle testing methods and results.

  6. Summary of Construction Equipment Tests and Activities

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

    Construction Equipment Tests and Activities Bruce Glagola - Sept 2013 Construction Equipment Tests A series of tests were conducted by the APS Construction Vibration...

  7. Automated Requirements Testing with Abstract Oracles Bernhard K. Aichernig

    E-Print Network [OSTI]

    , a mapping between abstract and concrete test data is required. The presented framework focuses on the usage of formal requirements specifications as test ora­ cles for concrete implementations. The approach is based, then the model may serve as a test oracle and specification as well. In Fig­ A A op abstract C C op concrete r r

  8. Advanced Vehicle Testing Activity (AVTA) - Vehicle Testing and...

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

    Advanced Vehicle Testing Activity (AVTA) Non-PHEV Evaluations and Data Collection AVTA HEV, NEV, BEV and HICEV Demonstrations and Testing Benchmarking of Advanced HEVs and...

  9. Boron-10 ABUNCL Active Testing

    SciTech Connect (OSTI)

    Kouzes, Richard T.; Ely, James H.; Lintereur, Azaree T.; Siciliano, Edward R.

    2013-07-09T23:59:59.000Z

    The Department of Energy Office of Nuclear Safeguards and Security (NA-241) is supporting the project Coincidence Counting With Boron-Based Alternative Neutron Detection Technology at Pacific Northwest National Laboratory (PNNL) for the development of a 3He proportional counter alternative neutron coincidence counter. The goal of this project is to design, build and demonstrate a system based upon 10B-lined proportional tubes in a configuration typical for 3He-based coincidence counter applications. This report provides results from testing of the active mode of the General Electric Reuter-Stokes Alternative Boron-Based Uranium Neutron Coincidence Collar (ABUNCL) at Los Alamos National Laboratory using sources and fuel pins.

  10. HEV Fleet Testing Advanced Vehicle Testing Activities - 2010...

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

    Testing Advanced Vehicle Testing Activity Maintenance Sheet for 2010 Ford Fusion VIN 3FADP0L32AR194699 Date Mileage Description Cost 1012009 5915 Changed oil and filter 28.77...

  11. Fleet Testing Advanced Vehicle Testing Activities - 2010 Honda...

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

    Vehicle Testing Activity Maintenance Sheet for 2010 Honda Insight LX VIN JHMZE2H59AS011748 HEV Fleet Testing Date Mileage Description Cost 842009 5,752 Changed oil and filter...

  12. Energy cost and muscular activity required for propulsion during walking

    E-Print Network [OSTI]

    Kram, Rodger

    Energy cost and muscular activity required for propulsion during walking Jinger S. Gottschall Kram. Energy cost and muscular activity required for propulsion during walk- ing. J Appl Physiol 94 there was a positive linear relationship between a horizontal impeding force and energy expen- diture. Using a wind

  13. Lead Coolant Test Facility - Design Concept and Requirements

    SciTech Connect (OSTI)

    Soli Khericha, Ph. D.

    2011-08-01T23:59:59.000Z

    The Idaho National Laboratory prepared a preliminary technical and functional requirements (T&FR), thermal hydraulic design and cost estimate for a lead coolant test facility. The purpose of this small scale facility is to simulate lead coolant fast reactor (LFR) coolant flow in an open lattice geometry core using seven electrical rods and liquid lead or lead-bismuth eutectic. Based on review of current world lead or lead-bismuth test facilities and research need listed in the Generation IV Roadmap, five broad areas of requirements are identified in this paper: (1) Develop and Demonstrate Feasibility of Submerged Heat Exchanger; (2) Develop and Demonstrate Open-lattice Flow in Electrically Heated Core; (3) Develop and Demonstrate Chemistry Control; (4) Demonstrate Safe Operation; and (5) Provision for Future Testing Across these five broad areas are supported by twenty-one specific requirements. The purpose of this facility is to focus the lead fast reactor community domestically on the requirements for the next unique state of the art test facility. The facility thermal hydraulic design is based on the maximum simulated core power using seven electrical heater rods of 420 kW; average linear heat generation rate of 300 W/cm. The core inlet temperature for liquid lead or Pb/Bi eutectic is 4200C. The design includes approximately seventy-five data measurements such as pressure, temperature, and flow rates. The preliminary estimated cost of construction of the facility is $3.7M (in 2006 $). It is also estimated that the facility will require two years to be constructed and ready for operation.

  14. Energy-efficiency testing activities of the Mobile Energy Laboratory

    SciTech Connect (OSTI)

    Parker, G.B.

    1991-01-01T23:59:59.000Z

    This report summarizes energy-efficiency testing activities during the first and second quarters of fiscal year 1990 applying the Mobile Energy Laboratory (MEL) testing capabilities. Four MELs, developed by the US Department of Energy (DOE) Federal Energy Management Program (FEMP), are administered by Pacific Northwest Laboratory (PNL) for energy testing and program support functions at federal facilities. The using agencies principally fund MEL applications, while DOE/FEMP funds program administration and capability enhancement activities. This report fulfills the requirements established in the MEL Use Plan (PNL-6861) for semiannual reporting on energy-efficiency testing activities using the MEL capabilities. The MEL Use Committee, formally established in 1989, developed the MEL Use Plan and meets semiannually to establish priorities for energy-efficient testing applications using the MEL capabilities.

  15. Testing Oxygen Reduction Reaction Activity with the Rotating...

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

    Testing Oxygen Reduction Reaction Activity with the Rotating Disc Electrode Technique Testing Oxygen Reduction Reaction Activity with the Rotating Disc Electrode Technique...

  16. Study of fueling requirements for the Engineering Test Reactor

    SciTech Connect (OSTI)

    Ho, S.K.; Perkins, L.J.

    1987-10-16T23:59:59.000Z

    An assessment of the fueling requirement for the TIBER Engineering Test Reactor is studied. The neutral shielding pellet ablation model with the inclusion of the effects of the alpha particles is used for our study. The high electron temperature in a reactor-grade plasma makes pellet penetration very difficult. The launch length has to be very large (several tens of meters) in order to avoid pellet breakage due to the low inertial strength of DT ''ice.'' The minimum repetition rate corresponding to the largest allowable pellet, is found to be about 1 Hz. A brief survey is done on the various operational and conceptual pellet injection schemes for plasma fueling. The underlying conclusion is that an alternative fueling scheme of coaxial compact-toroid plasma gun is very likely needed for effective central fueling of reactor-grade plasmas. 16 refs.

  17. U.S. Department of Energy -- Advanced Vehicle Testing Activity: Plug-in Hybrid Electric Vehicle Testing and Demonstration Activities

    SciTech Connect (OSTI)

    James E. Francfort; Donald Karner; John G. Smart

    2009-05-01T23:59:59.000Z

    The U.S. Department of Energy’s (DOE) Advanced Vehicle Testing Activity (AVTA) tests plug-in hybrid electric vehicles (PHEV) in closed track, dynamometer and onroad testing environments. The onroad testing includes the use of dedicated drivers on repeated urban and highway driving cycles that range from 10 to 200 miles, with recharging between each loop. Fleet demonstrations with onboard data collectors are also ongoing with PHEVs operating in several dozen states and Canadian Provinces, during which trips- and miles-per-charge, charging demand and energy profiles, and miles-per-gallon and miles-per-kilowatt-hour fuel use results are all documented, allowing an understanding of fuel use when vehicles are operated in charge depleting, charge sustaining, and mixed charge modes. The intent of the PHEV testing includes documenting the petroleum reduction potential of the PHEV concept, the infrastructure requirements, and operator recharging influences and profiles. As of May 2008, the AVTA has conducted track and dynamometer testing on six PHEV conversion models and fleet testing on 70 PHEVs representing nine PHEV conversion models. A total of 150 PHEVs will be in fleet testing by the end of 2008, all with onboard data loggers. The onroad testing to date has demonstrated 100+ miles per gallon results in mostly urban applications for approximately the first 40 miles of PHEV operations. The primary goal of the AVTA is to provide advanced technology vehicle performance benchmark data for technology modelers, research and development programs, and technology goal setters. The AVTA testing results also assist fleet managers in making informed vehicle purchase, deployment and operating decisions. The AVTA is part of DOE’s Vehicle Technologies Program. These AVTA testing activities are conducted by the Idaho National Laboratory and Electric Transportation Engineering Corporation, with Argonne National Laboratory providing dynamometer testing support. The proposed paper and presentation will discuss PHEV testing activities and results. INL/CON-08-14333

  18. International inspection activity impacts upon DOE safeguards requirements

    SciTech Connect (OSTI)

    Zack, N.R. [Los Alamos National Lab., NM (United States). Safeguards Systems Group; Crawford, D.W. [USDOE Office of Safeguards and Security, Washington, DC (United States)

    1995-09-01T23:59:59.000Z

    The US has placed certain special nuclear materials declared excess to their strategic needs under international safeguards through the International Atomic Energy Agency (IAEA). This Presidential initiative has obligated materials at several Department of Energy (DOE) facilities for these safeguards activities to demonstrate the willingness of the US to ban production or use of nuclear materials outside of international safeguards. However, IAEA inspection activities generally tend to be intrusive in nature and are not consistent with several domestic safeguards procedures implemented to reduce worker radiation exposures and increase the cost-effectiveness and efficiency of accounting for and storing of special nuclear materials. To help identify and provide workable solutions to these concerns, the Office of Safeguards and Security has conducted a program to determine possible changes to the DOE safeguards and security requirements designed to help facilities under international safeguards inspections more easily comply with domestic safeguards goals during international inspection activities. This paper will discuss the impact of international inspection activities on facility safeguards operations and departmental safeguards procedures and policies.

  19. Issues and test requirements in radiation shielding of fusion reactors

    SciTech Connect (OSTI)

    Nakagawa, M.; Abdou, M.A.

    1986-11-01T23:59:59.000Z

    Radiation shield issues for fusion reactors have been investigated and the experiments and facilities required to resolve the issues have been identified and characterized as part of the FINESSE program. This paper summarizes the recommended approach to fusion shield research and development, provides a summary of the necessary experiments and facilities, and presents the results of technical analyses involved.

  20. Issues and test requirements in radiation shielding of fusion reactors

    SciTech Connect (OSTI)

    Nakagawa, M.; Abdou, M.A.

    1986-01-01T23:59:59.000Z

    Radiation shield issues for fusion reactors have been investigated and the experiments and facilities required to resolve the issues have been identified and characterized as part of the FINESSE program. This paper summarizes the recommended approach to fusion shield R and D, provides a summary of the necessary experiments and facilities, and presents the results of technical analyses involved.

  1. Beam Test of the Superstructure Instrumentation Requirements for

    E-Print Network [OSTI]

    of the HOM-coupler signals ¯ Measurement of the BPM signals ¯ Measurement of beam orbit and energy #12 procedure "HOM Search". #12;Measurement of the BPM signals 8 Beam Test of the Superstructure Measurement of the BPM signals Beside (?!) the re-entrant cavity BPM (C. Magne), a stripline BPM (DESY

  2. Vehicle Technologies Office: Advanced Vehicle Testing Activity...

    Energy Savers [EERE]

    (AVTA) Data and Results The Vehicle Technologies Office (VTO) supports work to develop test procedures and carry out testing on a wide range of advanced vehicles and technologies...

  3. Engineering Scaling Requirements for Solid Breeder Blanket Testing

    SciTech Connect (OSTI)

    Ying, A.; Sharafat, S.; Youssef, M.; An, J.; Hunt, R.; Rainsberry, P.; Abdou, M. [University of California, Los Angeles (United States)

    2005-05-15T23:59:59.000Z

    An engineering scaling process is applied to the solid breeder ITER TBM designs in accordance with the testing objectives of validating the design tools and the database, and evaluating blanket performance under prototypical operating conditions. The goal of scaling is to ensure that changes in structural response and performance caused by changes in size and operating conditions do not reduce the usefulness of the tests. Initially, constitutive equations are applied to lay out the basic operating and design parameters that dominate blanket phenomena. The suitability of these similarity criteria for the TBM design is then confirmed by comparing finite element predictions of prototype and scale model responses. The TBM design also takes into account the need to check the codes and data for future design use. Specifically, predictability of tritium production and nuclear heating rates in a complex geometry, tritium release and permeation characteristics under fusion environments belong to this category. We conclude that this engineering scaling design process has maximized the value of ITER testing.

  4. Seismic requirements for design of nuclear power plants and nuclear test facilities

    SciTech Connect (OSTI)

    Not Available

    1985-02-01T23:59:59.000Z

    This standard establishes engineering requirements for the design of nuclear power plants and nuclear test facilities to accommodate vibratory effects of earthquakes.

  5. Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials

    E-Print Network [OSTI]

    Abdou, Mohamed

    Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials, Russian Federation Abstract Within the framework of the ITER Test Blanket Working Group, the ITER Parties have made several proposals for test blanket modules to be tested in ITER from the first day of H

  6. Recovery Efficiency Test Project: Phase 1, Activity report

    SciTech Connect (OSTI)

    Overbey, W.K. Jr.; Wilkins, D.W.; Keltch, B.; Saradji, B.; Salamy, S.P.

    1988-04-01T23:59:59.000Z

    This report is the second volume of the Recovery Efficiency Test Phase I Report of Activities. Volume 1 covered selection, well planning, drilling, coring, logging and completion operations. This volume reports on well testing activities, reclamation activities on the drilling site and access roads, and the results of physical and mechanical properties tests on the oriented core material obtained from a horizontal section of the well. 3 refs., 21 figs., 10 tabs.

  7. activation test locations: Topics by E-print Network

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

    activation test locations First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Active Testing CERN Preprints...

  8. activities field test: Topics by E-print Network

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

    activities field test First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Active Testing CERN Preprints...

  9. Active Waste Materials Corrosion and Decontamination Tests

    SciTech Connect (OSTI)

    MJ Danielson; MR Elmore; SG Pitman

    2000-08-15T23:59:59.000Z

    Stainless steel alloys, 304L and 316L, were corrosion tested in representative radioactive samples of three actual Hanford tank waste solutions (Tanks AW-101, C-104, AN-107). Both the 304L and 316L exhibited good corrosion performance when immersed in boiling waste solutions. The maximum general corrosion rate was 0.015 mm/y (0.60 mils per year). Generally, the 304L had a slightly higher rate than the 316L. No localized attack was observed after 122 days of testing in the liquid phase, liquid/vapor phase, or vapor phase. Radioactive plate-out decontamination tests indicated that a 24-hour exposure to 1 {und M} HNO{sub 3} could remove about 99% of the radioactive components in the metal film when exposed to the C-104 and AN-107 solutions. The decontamination results are less certain for the AW-101 solution, since the initial contamination readings exceeded the capacity of the meter used for this test.

  10. Driver mental workload requirements on horizontal curves based on occluded vision test measurements

    E-Print Network [OSTI]

    Shafer, Mark Anthony

    1994-01-01T23:59:59.000Z

    This thesis documents an evaluation of driver mental workload requirements on horizontal curves based on occluded vision test measurements. Driver workload is an important concept in the design of highway systems. A successful highway design...

  11. activation requires modulation: Topics by E-print Network

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

    for photovoltaic module efficiency of 33.9% (active area). The latest prototype module Photovoltaic Systems (ISFOC) in Puertollano, Spain, the efficiency significantly exceeds...

  12. Preliminary requirements for a Fluoride Salt-Cooled High-Temperature Test Reactor (FHTR)

    SciTech Connect (OSTI)

    Massie, M.; Forsberg, C.; Forget, B. [Dept. of Nuclear Science and Engineering, Massachusetts Inst. of Technology, Cambridge, MA 02139 (United States); Hu, L. W. [Nuclear Reactor Laboratory, Massachusetts Inst. of Technology, 77 Massachusetts Avenue, Cambridge, MA 02139 (United States)

    2012-07-01T23:59:59.000Z

    A Fluoride Salt-Cooled High-Temperature Test Reactor (FHTR) design is being developed at MIT to provide the first demonstration and test of a salt-cooled reactor using high-temperature fuel. The first step is to define the requirements. The top level requirements are (1) provide the confidence that a larger demonstration reactor is warranted and (2) develop the necessary data for a larger-scale reactor. Because requirements will drive the design of the FHTR, a significant effort is being undertaken to define requirements and understand the tradeoffs that will be required for a practical design. The preliminary requirements include specifications for design parameters and necessary tests of major reactor systems. Testing requirements include demonstration of components, systems, and procedures for refueling, instrumentation, salt temperature control to avoid coolant freezing, salt chemistry and volume control, tritium monitoring and control, and in-service inspection. Safety tests include thermal hydraulics, neutronics - including intrinsic core shutdown mechanisms such as Doppler feedback - and decay heat removal systems. Materials and coolant testing includes fuels (including mechanical wear and fatigue) and system corrosion behavior. Preliminary analysis indicates a thermal power output below 30 MW, an initial core using pebble-bed or prismatic-block fuel, peak outlet temperatures of at least 700 deg. C, and use of FLi{sup 7}Be ({sup 7}LiF-BeF{sub 2}) coolant. The option to change-out the reactor core, fuel type, and major components is being investigated. While the FHTR will be used for materials testing, its primary mission is as a reactor system performance test to enable the design and licensing of a FHR demonstration power reactor. (authors)

  13. CURRENT TESTING ACTIVITIES AT THE ACRELAB RENEWABLE ENERGY SYSTEMS TEST FACILITY , E S Spooner2

    E-Print Network [OSTI]

    , AUSTRALIA 2 University of New South Wales, Kensington, NSW, AUSTRALIA 3 Australian CRC for Renewable Energy) on the Murdoch University campus in Perth, Western Australia. The facility provides independent testing of RECURRENT TESTING ACTIVITIES AT THE ACRELAB RENEWABLE ENERGY SYSTEMS TEST FACILITY T L Pryor1 , E

  14. Activity Based Costing - DOE Directives, Delegations, and Requirements

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

    outlines the Activity Based Costing method and discusses applicable uses of ABC. g4301-1chp24.pdf -- PDF Document, 11 KB Writer: John Makepeace Subjects: Administration Management...

  15. Advanced Vehicle Testing Activity (AVTA) ? Non-PHEV Evaluations...

    Energy Savers [EERE]

    Non-PHEV Evaluations and Data Collection Advanced Vehicle Testing Activity (AVTA) Non-PHEV Evaluations and Data Collection Presentation from the U.S. DOE Office of Vehicle...

  16. Determination of Importance Evaluation for Exploratory Studies Facility (ESF) Subsurface Testing Activities

    SciTech Connect (OSTI)

    C.J. Byrne

    2001-02-20T23:59:59.000Z

    This Determination of Importance Evaluation (DIE) applies to the Subsurface Exploratory Studies Facility (ESF), encompassing the Topopah Spring (TS) Loop from Station 0+00 meters (m) at the North Portal to breakthrough at the South Portal (approximately 78+77 m), and ancillary test and operation support areas including the Enhanced Characterization of the Repository Block (ECRB) Cross Drift. This evaluation applies specifically to site characterization testing activities ongoing and planned in the Subsurface ESF. ESF site characterization activities are being performed to obtain the information necessary to determine whether the Yucca Mountain Site is suitable as a geologic repository for spent nuclear fuel and high-level radioactive waste. A more detailed description of these testing activities is provided in Section 6 of this DIE. Generally, the construction and operation of excavations associated with these testing activities are evaluated in the DIE for the Subsurface ESF (CRWMS M&O 1999a) and the DIE for the ESF ECRB Cross Drift (CRWMS M&O 2000a). The scope of this DIE also entails the proposed Unsaturated Zone (UZ) Transport Test at Busted Butte. Although, not a part of the TS Loop or ECRB Cross Drift, the associated testing activities are Subsurface testing activities. Busted Butte is located to the south south-east of the TS Loop and is outside the Conceptual Controlled Area Boundary (CCAB). These activities provide access to the Calico Hills (CH) geologic structure. In the case of Busted Butte, construction and operation of excavations are evaluated herein (since this activity was not previously evaluated in CRWMS M&O 1999a). The objectives of this DIE are to determine whether Subsurface ESF testing, and associated activities, could potentially impact site characterization testing and/or the waste isolation capabilities of the site. Controls needed to limit any potential impacts are identified in Section 13. The validity and veracity of the individual tests, including data collection, are the responsibility of the assigned Principal Investigator(s) (PIS) and are not evaluated in this DIE. This DIE focuses on integrating and compiling the evaluations of previous DIES which were prepared for various ESF subsurface testing activities, including the use of temporary items currently located or being developed for these testing activities, and to provide a bounding evaluation for potential future ESF subsurface testing activities that are sufficiently similar to the generic testing activities addressed herein. Subsurface testing activities items/facilities evaluated herein include: ongoing and planned testing in the TS Loop, alcoves, and niches, planned testing in the ECRB Starter Tunnel, borehole drilling and workover, and tracers, fluids, and materials (TFM) usage. Detailed identification of individual testing items/facilities and generic descriptions for subsurface-testing-related activities are provided in Section 6. The conclusions and requirements of this DIE conservatively bound the conclusions and requirements of previously approved DIES for the ESF subsurface testing activities addressed herein, based on conservative engineering judgment and on concurrence with this DIE (via a formal review process) by the originating and reviewing organizations of the previously approved evaluations. Hence, this DIE supersedes the following DIES listed in Table 1.1.

  17. Technical note Insertion loss testing of active noise reduction

    E-Print Network [OSTI]

    Wong, Willy

    Technical note Insertion loss testing of active noise reduction headsets using acoustic fixture Jie. Department of Electrical and Computer Engineering, University of Toronto, 10 King's College Road, Toronto, ON measured insertion losses of four types of commercially avail- able ANR headsets using an Acoustic Test

  18. Safety requirements, facility user needs, and reactor concepts for a new Broad Application Test Reactor

    SciTech Connect (OSTI)

    Ryskamp, J.M. [ed.; Liebenthal, J.L.; Denison, A.B.; Fletcher, C.D.

    1992-07-01T23:59:59.000Z

    This report describes the EG&G Laboratory Directed Research and Development Program (LDRD) Broad Application Test Reactor (BATR) Project that was conducted in fiscal year 1991. The scope of this project was divided into three phases: a project process definition phase, a requirements development phase, and a preconceptual reactor design and evaluation phase. Multidisciplinary teams of experts conducted each phase. This report presents the need for a new test reactor, the project process definition, a set of current and projected regulatory compliance and safety requirements, a set of facility user needs for a broad range of projected testing missions, and descriptions of reactor concepts capable of meeting these requirements. This information can be applied to strategic planning to provide the Department of Energy with management options.

  19. Safety requirements, facility user needs, and reactor concepts for a new Broad Application Test Reactor

    SciTech Connect (OSTI)

    Ryskamp, J.M. (ed.); Liebenthal, J.L.; Denison, A.B.; Fletcher, C.D.

    1992-07-01T23:59:59.000Z

    This report describes the EG G Laboratory Directed Research and Development Program (LDRD) Broad Application Test Reactor (BATR) Project that was conducted in fiscal year 1991. The scope of this project was divided into three phases: a project process definition phase, a requirements development phase, and a preconceptual reactor design and evaluation phase. Multidisciplinary teams of experts conducted each phase. This report presents the need for a new test reactor, the project process definition, a set of current and projected regulatory compliance and safety requirements, a set of facility user needs for a broad range of projected testing missions, and descriptions of reactor concepts capable of meeting these requirements. This information can be applied to strategic planning to provide the Department of Energy with management options.

  20. Lead Coolant Test Facility Technical and Functional Requirements, Conceptual Design, Cost and Construction Schedule

    SciTech Connect (OSTI)

    Soli T. Khericha

    2006-09-01T23:59:59.000Z

    This report presents preliminary technical and functional requirements (T&FR), thermal hydraulic design and cost estimate for a lead coolant test facility. The purpose of this small scale facility is to simulate lead coolant fast reactor (LFR) coolant flow in an open lattice geometry core using seven electrical rods and liquid lead or lead-bismuth eutectic. Based on review of current world lead or lead-bismuth test facilities and research need listed in the Generation IV Roadmap, five broad areas of requirements of basis are identified: Develop and Demonstrate Prototype Lead/Lead-Bismuth Liquid Metal Flow Loop Develop and Demonstrate Feasibility of Submerged Heat Exchanger Develop and Demonstrate Open-lattice Flow in Electrically Heated Core Develop and Demonstrate Chemistry Control Demonstrate Safe Operation and Provision for Future Testing. These five broad areas are divided into twenty-one (21) specific requirements ranging from coolant temperature to design lifetime. An overview of project engineering requirements, design requirements, QA and environmental requirements are also presented. The purpose of this T&FRs is to focus the lead fast reactor community domestically on the requirements for the next unique state of the art test facility. The facility thermal hydraulic design is based on the maximum simulated core power using seven electrical heater rods of 420 kW; average linear heat generation rate of 300 W/cm. The core inlet temperature for liquid lead or Pb/Bi eutectic is 420oC. The design includes approximately seventy-five data measurements such as pressure, temperature, and flow rates. The preliminary estimated cost of construction of the facility is $3.7M. It is also estimated that the facility will require two years to be constructed and ready for operation.

  1. Regulatory Guidance Letter 87-08 SUBJECT: Testing Requirements for Dredged Material

    E-Print Network [OSTI]

    US Army Corps of Engineers

    Regulatory Guidance Letter 87-08 SUBJECT: Testing Requirements for Dredged Material Evaluations that "The district engineer will review applications for permits for the discharge of dredged or fill)." The guidelines at 40 CFR 230.10(c) state in part that ".. no discharge of dredged or fill material shall

  2. rev. 9-2014 Required Tests for URI Teacher Education Students

    E-Print Network [OSTI]

    Rhode Island, University of

    Language students (not 5622/ K-6). See above. The Oral Proficiency Test (OPI) and the Written Proficiency Spanish: World Language Latin Italian** OPI and WPT (required for all): *One score must be Advanced Low or better; the other must be Intermediate High or better **For Italian, OPI must be Advanced Low or better

  3. Test Requirements and Conceptual Design for a Potassium Test Loop to Support an Advanced Potassium Rankine Cycle Power Conversion Systems

    SciTech Connect (OSTI)

    Yoder, JR.G.L.

    2006-03-08T23:59:59.000Z

    Parameters for continuing the design and specification of an experimental potassium test loop are identified in this report. Design and construction of a potassium test loop is part of the Phase II effort of the project ''Technology Development Program for an Advanced Potassium Rankine Power Conversion System''. This program is supported by the National Aeronautics and Space Administration. Design features for the potassium test loop and its instrumentation system, specific test articles, and engineered barriers for ensuring worker safety and protection of the environment are described along with safety and environmental protection requirements to be used during the design process. Information presented in the first portion of this report formed the basis to initiate the design phase of the program; however, the report is a living document that can be changed as necessary during the design process, reflecting modifications as additional design details are developed. Some portions of the report have parameters identified as ''to be determined'' (TBD), reflecting the early stage of the overall process. In cases where specific design values are presently unknown, the report attempts to document the quantities that remain to be defined in order to complete the design of the potassium test loop and supporting equipment.

  4. Round-robin testing of a reference glass for low-activity waste forms

    SciTech Connect (OSTI)

    Ebert, W. L.; Wolf, S. F.

    1999-12-06T23:59:59.000Z

    A round robin test program was conducted with a glass that was developed for use as a standard test material for acceptance testing of low-activity waste glasses made with Hanford tank wastes. The glass is referred to as the low-activity test reference material (LRM). The program was conducted to measure the interlaboratory reproducibility of composition analysis and durability test results. Participants were allowed to select the methods used to analyze the glass composition. The durability tests closely followed the Product Consistency Test (PCT) Method A, except that tests were conducted at both 40 and 90 C and that parallel tests with a reference glass were not required. Samples of LRM glass that had been crushed, sieved, and washed to remove fines were provided to participants for tests and analyses. The reproducibility of both the composition and PCT results compare favorably with the results of interlaboratory studies conducted with other glasses. From the perspective of reproducibility of analysis results, this glass is acceptable for use as a composition standard for nonradioactive components of low-activity waste forms present at >0.1 elemental mass % and as a test standard for PCTS at 40 and 90 C. For PCT with LRM glass, the expected test results at the 95% confidence level are as follows: (1) at 40 C: pH = 9.86 {+-} 0.96; [B] = 2.30 {+-} 1.25 mg/L; [Na] = 19.7 {+-} 7.3 mg/L; [Si] = 13.7 {+-} 4.2 mg/L; and (2) at 90 C: pH = 10.92 {+-} 0.43; [B] = 26.7 {+-} 7.2 mg/L; [Na] = 160 {+-} 13 mg/L; [Si] = 82.0 {+-} 12.7 mg/L. These ranges can be used to evaluate the accuracy of PCTS conducted at other laboratories.

  5. Testing and analysis to determine the shell thickness required to prevent puncture

    SciTech Connect (OSTI)

    Ammerman, D.J.; Radloff, H.D.; Eifert, E.J.

    1998-05-01T23:59:59.000Z

    Type B radioactive material packages are required to withstand a hypothetical puncture accident of a free fall from a height of one meter onto a 15 cm diameter mild steel puncture probe. For many packages it is desirable to have this accident event not result in puncture or tearing of the outer shell of the package. The wall thickness necessary to prevent this has historically been determined by test or the use of empirical relations. This technique generally results in overly conservative designs, but the degree of conservatism is uncertain. The use of modem finite element codes to determine package response to puncture accidents can result in designs that are both safe and economical. The work reported in this paper is aimed at developing a method to analytically determine the wall thickness required to prevent puncture. For designers and regulators to have confidence in this analytical method, however, it must be benchmarked against test results. A series of tests has been conducted with differing shell thicknesses, shell materials of mild steel and stainless steel, and shell backing materials of lead, foam, and air. The results of these tests have been compared with pre-test analytical predictions of the response obtained from the nonlinear transient dynamic finite element program PRONTO-2D. From this comparison it can be seen that the finite element method can accurately predict the response of packages to puncture accidents. This implies that an analytical technique based on the finite element method can be used to design packages having known response and margin of safety against tearing of the outer shell. In addition, the analytical technique can accurately predict the deformed shape of the package following the test. This may be important for subsequent calculations, such as external dose and heat input during a thermal event.

  6. Boron-10 ABUNCL Prototype Models And Initial Active Testing

    SciTech Connect (OSTI)

    Kouzes, Richard T.; Ely, James H.; Lintereur, Azaree T.; Siciliano, Edward R.

    2013-04-23T23:59:59.000Z

    The Department of Energy Office of Nuclear Safeguards and Security (NA-241) is supporting the project Coincidence Counting With Boron-Based Alternative Neutron Detection Technology at Pacific Northwest National Laboratory (PNNL) for the development of a 3He proportional counter alternative neutron coincidence counter. The goal of this project is to design, build and demonstrate a system based upon 10B-lined proportional tubes in a configuration typical for 3He-based coincidence counter applications. This report provides results from MCNPX model simulations and initial testing of the active mode variation of the Alternative Boron-Based Uranium Neutron Coincidence Collar (ABUNCL) design built by General Electric Reuter-Stokes. Initial experimental testing of the as-delivered passive ABUNCL was previously reported.

  7. Uranium Adsorption on Granular Activated Carbon – Batch Testing

    SciTech Connect (OSTI)

    Parker, Kent E.; Golovich, Elizabeth C.; Wellman, Dawn M.

    2013-09-26T23:59:59.000Z

    The uranium adsorption performance of two activated carbon samples (Tusaar Lot B-64, Tusaar ER2-189A) was tested using unadjusted source water from well 299-W19-36. These batch tests support ongoing performance optimization efforts to use the best material for uranium treatment in the Hanford Site 200 West Area groundwater pump-and-treat system. A linear response of uranium loading as a function of the solution-to-solid ratio was observed for both materials. Kd values ranged from ~380,000 to >1,900,000 ml/g for the B-64 material and ~200,000 to >1,900,000 ml/g for the ER2-189A material. Uranium loading values ranged from 10.4 to 41.6 ?g/g for the two Tusaar materials.

  8. New requirements for digital radiographic testing of welds according to ISO standards

    SciTech Connect (OSTI)

    Zscherpel, U.; Ewert, U.; Jechow, M. [BAM Federal Institute for Materials Research and Testing, D-12200 Berlin (Germany)

    2013-01-25T23:59:59.000Z

    Users of EN 14784-2 (general principles for computed radiography with phosphor imaging plates) reported about difficulties to achieve testing class B in weld testing with imaging plates. One of the reasons is the insufficient consideration of the inherent detector unsharpness (u{sub i}) in the minimum requirements. Digital detectors have a higher inherent unsharpness compared to film, which can even exceed the geometrical unsharpness (u{sub g}) of the typical contact technique. In EN 444 and ISO 5579 (general principles for film radiography) u{sub i} is neglected for the calculation of the minimum source-to-object distance (SOD), because it is small compared to the geometric unsharpness (u{sub g}). Considering u{sub i} for digital detectors results in a new equation for SOD (see ISO/FDIS 17636-2). Therefore, the increase in total image unsharpness requires the compensation by a larger SOD to reduce u{sub g}. This contribution discusses the need for change of the SOD for different setups (detectors, focal spots, etc.) and explains the difference in image quality, achieved on basis of the extended equation of ISO/FDIS 17636-2. Furthermore, the detection of image quality indicators depends on the achieved Contrast-to-Noise ratio (CNR) and total image unsharpness. Both of them are essential parameters, which influence the contrast sensitivity. Additionally, new compensation principles (e.g. compensation of missing spatial resolution by enhanced contrast sensitivity) allow to widen the application range of digital detectors for radiographic weld testing.

  9. Activation of building air in a Tokamak Engineering Test Facility

    SciTech Connect (OSTI)

    Leonard, B.R. Jr.; Perry, R.T.

    1980-09-01T23:59:59.000Z

    The production of radionuclides by neutron reactions in the building air of a conceptual Tokamak Engineering Test Facility has been calculated. The short-lived radionuclides /sup 13/N, /sup 16/N and /sup 41/Ar are all found to greatly exceed their maximum permissable concentration values. Longer-lived radionuclides /sup 3/H, /sup 14/C and /sup 39/Ar are also found to be produced in significant concentrations. The present results are compared with values calculated for three other fusion devices; TFTR, INS, and FMIT. These comparisons show that the ETF can be a prolific producer of activated air.

  10. Tc-99 Adsorption on Selected Activated Carbons - Batch Testing Results

    SciTech Connect (OSTI)

    Mattigod, Shas V.; Wellman, Dawn M.; Golovich, Elizabeth C.; Cordova, Elsa A.; Smith, Ronald M.

    2010-12-01T23:59:59.000Z

    CH2M HILL Plateau Remediation Company (CHPRC) is currently developing a 200-West Area groundwater pump-and-treat system as the remedial action selected under the Comprehensive Environmental Response, Compensation, and Liability Act Record of Decision for Operable Unit (OU) 200-ZP-1. This report documents the results of treatability tests Pacific Northwest National Laboratory researchers conducted to quantify the ability of selected activated carbon products (or carbons) to adsorb technetium-99 (Tc-99) from 200-West Area groundwater. The Tc-99 adsorption performance of seven activated carbons (J177601 Calgon Fitrasorb 400, J177606 Siemens AC1230AWC, J177609 Carbon Resources CR-1240-AW, J177611 General Carbon GC20X50, J177612 Norit GAC830, J177613 Norit GAC830, and J177617 Nucon LW1230) were evaluated using water from well 299-W19-36. Four of the best performing carbons (J177606 Siemens AC1230AWC, J177609 Carbon Resources CR-1240-AW, J177611 General Carbon GC20X50, and J177613 Norit GAC830) were selected for batch isotherm testing. The batch isotherm tests on four of the selected carbons indicated that under lower nitrate concentration conditions (382 mg/L), Kd values ranged from 6,000 to 20,000 mL/g. In comparison. Under higher nitrate (750 mg/L) conditions, there was a measureable decrease in Tc-99 adsorption with Kd values ranging from 3,000 to 7,000 mL/g. The adsorption data fit both the Langmuir and the Freundlich equations. Supplemental tests were conducted using the two carbons that demonstrated the highest adsorption capacity to resolve the issue of the best fit isotherm. These tests indicated that Langmuir isotherms provided the best fit for Tc-99 adsorption under low nitrate concentration conditions. At the design basis concentration of Tc 0.865 µg/L(14,700 pCi/L), the predicted Kd values from using Langmuir isotherm constants were 5,980 mL/g and 6,870 mL/g for for the two carbons. These Kd values did not meet the target Kd value of 9,000 mL/g. Tests conducted to ascertain the effects of changing pH showed that at pH values of 6.5 and 7.5, no significant differences existed in Tc-adsorption performance for three of the carbons, but the fourth carbon performed better at pH 7.5. When the pH was increased to 8.5, a slight decline in performance was observed for all carbons. Tests conducted to ascertain the temperature effect on Tc-99 adsorption indicated that at 21 ºC, 27 ºC, and 32 ºC there were no significant differences in Tc-99 adsorption for three of the carbons. The fourth carbon showed a noticeable decline in Tc-99 adsorption performance with increasing temperature. The presence of volatile organic compounds (VOCs) in the source water did not significantly affect Tc-99 adsorption on either of two carbons tested. Technetium-99 adsorption differed by less than 15% with or without VOCs present in the test water, indicating that Tc-99 adsorption would not be significantly affected if VOCs were removed from the water prior to contact with carbon.

  11. ERK activation is required for hydrostatic pressure-induced tensile changes in

    E-Print Network [OSTI]

    Athanasiou, Kyriacos

    ERK activation is required for hydrostatic pressure-induced tensile changes in engineered articular, Davis, CA, USA Abstract The objective of this study was to identify ERK 1/2 involvement in the changes-assembled cartilage constructs. In study 1, ERK 1/2 phosphorylation was detected by immunoblot, following application

  12. Necessity and Requirements of a Collaborative Effort to Develop a Large Wind Turbine Blade Test Facility in North America

    SciTech Connect (OSTI)

    Cotrell, J.; Musial, W.; Hughes, S.

    2006-05-01T23:59:59.000Z

    The wind power industry in North America has an immediate need for larger blade test facilities to ensure the survival of the industry. Blade testing is necessary to meet certification and investor requirements and is critical to achieving the reliability and blade life needed for the wind turbine industry to succeed. The U.S. Department of Energy's (DOE's) Wind Program is exploring options for collaborating with government, private, or academic entities in a partnership to build larger blade test facilities in North America capable of testing blades up to at least 70 m in length. The National Renewable Energy Laboratory (NREL) prepared this report for DOE to describe the immediate need to pursue larger blade test facilities in North America, categorize the numerous prospective partners for a North American collaboration, and document the requirements for a North American test facility.

  13. Advanced Vehicle Testing Activity (AVTA) Data and Results

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office (VTO) supports work to develop test procedures and carry out testing on a wide range of advanced vehicles and technologies through the Advanced Vehicle Testing...

  14. Energy-efficiency testing activities of the Mobile Energy Laboratory - Semiannual Report: April 1, 1990, Through September 30, 1990

    SciTech Connect (OSTI)

    Parker, G.B.; Currie, J.W.

    1991-03-01T23:59:59.000Z

    This report summarizes energy-efficiency testing activities applying the Mobile Energy Laboratory (MEL) testing capabilities during the third and fourth quarters of fiscal year (FY) 1990. The MELs, developed by the US Department of Energy (DOE) Federal Energy Management Program (FEMP), are administered by Pacific Northwest Laboratory (PNL) and the Naval Energy and Environmental Support Activity (NEESA) for energy testing and energy conservation program support functions at federal facilities. MELs are equipped for the on-site evaluation of energy use efficiency. The using agencies principally fund MEL applications, while DOE/FEMP funds program administration and capability enhancement activities. This report fulfills the requirements established in Section 8 of the MEL Use Plan (PNL-6861) for semiannual reporting on energy-efficiency testing activities using the MEL capabilities. The MEL Use Committee, formally established in 1989, developed the MEL Use Plan and meets semiannually to establish priorities for energy-efficient testing applications using the MEL capabilities. This report describes the testing, test results, and suggested courses of action.

  15. LOW ACTIVITY WASTE FEED SOLIDS CARACTERIZATION AND FILTERABILITY TESTS

    SciTech Connect (OSTI)

    McCabe, D.; Crawford, C.; Duignan, M.; Williams, M.; Burket, P.

    2014-04-03T23:59:59.000Z

    The primary treatment of the tank waste at the DOE Hanford site will be done in the Waste Treatment and Immobilization Plant (WTP) that is currently under construction. The baseline plan for the WTP Pretreatment facility is to treat the waste, splitting it into High Level Waste (HLW) feed and Low Activity Waste (LAW) feed. Both waste streams are then separately vitrified as glass and sealed in canisters. The LAW glass will be disposed onsite in the Integrated Disposal Facility (IDF). There are currently no plans to treat the waste to remove technetium in the WTP Pretreatment facility, so its disposition path is the LAW glass. Options are being explored to immobilize the LAW portion of the tank waste, i.e., the LAW feed from the WTP Pretreatment facility. Removal of {sup 99}Tc from the LAW Feed, followed by off-site disposal of the {sup 99}Tc, would eliminate a key risk contributor for the IDF Performance Assessment (PA) for supplemental waste forms, and has potential to reduce treatment and disposal costs. Washington River Protection Solutions (WRPS) is developing some conceptual flow sheets for LAW treatment and disposal that could benefit from technetium removal. One of these flowsheets will specifically examine removing {sup 99}Tc from the LAW feed stream to supplemental immobilization. The conceptual flow sheet of the {sup 99}Tc removal process includes a filter to remove insoluble solids prior to processing the stream in an ion exchange column, but the characteristics and behavior of the liquid and solid phases has not previously been investigated. This report contains results of testing of a simulant that represents the projected composition of the feed to the Supplemental LAW process. This feed composition is not identical to the aqueous tank waste fed to the Waste Treatment Plant because it has been processed through WTP Pretreatment facility and therefore contains internal changes and recycle streams that will be generated within the WTP process. Although a Supplemental LAW feed simulant has previously been prepared, this feed composition differs from that simulant because those tests examined only the fully soluble aqueous solution at room temperature, not the composition formed after evaporation, including the insoluble solids that precipitate after it cools. The conceptual flow sheet for Supplemental LAW immobilization has an option for removal of {sup 99}Tc from the feed stream, if needed. Elutable ion exchange has been selected for that process. If implemented, the stream would need filtration to remove the insoluble solids prior to processing in an ion exchange column. The characteristics, chemical speciation, physical properties, and filterability of the solids are important to judge the feasibility of the concept, and to estimate the size and cost of a facility. The insoluble solids formed during these tests were primarily natrophosphate, natroxalate, and a sodium aluminosilicate compound. At the elevated temperature and 8 M [Na+], appreciable insoluble solids (1.39 wt%) were present. Cooling to room temperature and dilution of the slurry from 8 M to 5 M [Na+] resulted in a slurry containing 0.8 wt% insoluble solids. The solids (natrophosphate, natroxalate, sodium aluminum silicate, and a hydrated sodium phosphate) were relatively stable and settled quickly. Filtration rates were in the range of those observed with iron-based simulated Hanford tank sludge simulants, e.g., 6 M [Na+] Hanford tank 241-AN-102, even though their chemical speciation is considerably different. Chemical cleaning of the crossflow filter was readily accomplished with acid. As this simulant formulation was based on an average composition of a wide range of feeds using an integrated computer model, this exact composition may never be observed. But the test conditions were selected to enable comparison to the model to enable improving its chemical prediction capability.

  16. Enforcement Guidance Supplement 99-02: DOE Enforcement Activities of Internal Dosimetry Program Requirements

    Broader source: Energy.gov [DOE]

    Section 1.3 of the Operational Procedure entitled Enforcement of DOE Nuclear Safety Requirements under Price-Anderson Amendments Act of 1988, published in June 1998, provides the opportunity for the Office of Enforcement and Investigation (EH Enforcement) to issue clarifying guidance in a timely manner with respect to the processes used in its enforcement activities. The focus of this enforcement guidance clarifies internal dosimetry program requirements identified by the Department of Energy’s nuclear safety requirements in 10 CFR 835 (Occupational Radiation Protection Programs) and 10 CFR 830.120 (Quality Assurance Requirements). To develop the enforcement guidance, EH Enforcement convened a DOE working group which included representatives from the Field Office elements and the Office of Worker Protection Programs and Hazards Management, which is the office responsible for the content and technical clarifications of 10 CFR 835. The guide discusses the following areas: (1) prospective determination of employees that are “likely to receive” 100 millirem (mrem) or greater per 10 CFR 835.402, (Individual Monitoring); (2) application of enforcement policy in taking credit for respiratory protection in prospective determinations; (3) use of contractor’s policies regarding personnel internal exposure to radioactive material; (4) As Low As Reasonably Achievable (ALARA) programs; (5) clarification of enforcement with regard to internal dosimetry programs; and Final Comments.

  17. Load requirements for maintaining structural integrity of Hanford single-shell tanks during waste feed delivery and retrieval activities

    SciTech Connect (OSTI)

    JULYK, L.J.

    1999-09-22T23:59:59.000Z

    This document provides structural load requirements and their basis for maintaining the structural integrity of the Hanford Single-Shell Tanks during waste feed delivery and retrieval activities. The requirements are based on a review of previous requirements and their basis documents as well as load histories with particular emphasis on the proposed lead transfer feed tanks for the privatized vitrification plant.

  18. Advanced Vehicle Testing Activity (AVTA) ? Non-PHEV Evaluations...

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

    previously completed EoL battery testing on two Gen I Prius, two Gen I Civic, and two Honda Insight HEVs - Collected fuel economy, maintenance, depreciation, operations...

  19. PEA-15 Binding to ERK1/2 MAPKs Is Required for Its Modulation of Integrin Activation*

    E-Print Network [OSTI]

    Ramos, Joe W.

    PEA-15 Binding to ERK1/2 MAPKs Is Required for Its Modulation of Integrin Activation* Received and 2 (ERK1/2). However, bulk ERK1/2 activation does not correlate with suppression. PEA-15 reverses suppression of integrin activation and binds ERK1/2. Here we report that PEA-15 reversal of integrin

  20. Testing an Active Diesel Particulate Filter on a 2-Cycle Marine...

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

    an Active Diesel Particulate Filter on a 2-Cycle Marine Engine Testing an Active Diesel Particulate Filter on a 2-Cycle Marine Engine Presentation given at DEER 2006, August 20-24,...

  1. Webinar: Testing Oxygen Reduction Reaction Activity with the Rotating Disc Electrode Technique

    Broader source: Energy.gov [DOE]

    Video recording of the Fuel Cell Technologies Office webinar, Testing Oxygen Reduction Reaction Activity with the Rotating Disc Electrode Technique, originally presented on March 12, 2013.

  2. Tank Waste Remediation System tank waste pretreatment and vitrification process development testing requirements assessment

    SciTech Connect (OSTI)

    Howden, G.F.

    1994-10-24T23:59:59.000Z

    A multi-faceted study was initiated in November 1993 to provide assurance that needed testing capabilities, facilities, and support infrastructure (sampling systems, casks, transportation systems, permits, etc.) would be available when needed for process and equipment development to support pretreatment and vitrification facility design and construction schedules. This first major report provides a snapshot of the known testing needs for pretreatment, low-level waste (LLW) and high-level waste (HLW) vitrification, and documents the results of a series of preliminary studies and workshops to define the issues needing resolution by cold or hot testing. Identified in this report are more than 140 Hanford Site tank waste pretreatment and LLW/HLW vitrification technology issues that can only be resolved by testing. The report also broadly characterizes the level of testing needed to resolve each issue. A second report will provide a strategy(ies) for ensuring timely test capability. Later reports will assess the capabilities of existing facilities to support needed testing and will recommend siting of the tests together with needed facility and infrastructure upgrades or additions.

  3. NEUTRON ACTIVATION COOLDOWN OF THE TOKAMAK FUSION TEST REACTOR

    E-Print Network [OSTI]

    involved the safe handling and processing about 100g of tritium. This resulted in manageable long concrete Test Cell showing the relative locations of the vessel, neutral beam injection systems, the vacuum. INTRODUCTION The Tokamak Fusion Test Reactor (TFTR) began high power deuterium­tritium (D­T) fueled operations

  4. Advanced Vehicle Testing Activity Benchmark Testing of the Chevrolet Volt Onboard Charger

    SciTech Connect (OSTI)

    Richard Carlson

    2012-04-01T23:59:59.000Z

    This is a report for public consumption, for the AVTA website, detailing the testing and analysis of the benchmark testing conducted on the Chevrolet Volt on-board charger.

  5. Functional and operational requirements document : building 1012, Battery and Energy Storage Device Test Facility, Sandia National Laboratories, New Mexico.

    SciTech Connect (OSTI)

    Johns, William H.

    2013-11-01T23:59:59.000Z

    This report provides an overview of information, prior studies, and analyses relevant to the development of functional and operational requirements for electrochemical testing of batteries and energy storage devices carried out by Sandia Organization 2546, Advanced Power Sources R&D. Electrochemical operations for this group are scheduled to transition from Sandia Building 894 to a new Building located in Sandia TA-II referred to as Building 1012. This report also provides background on select design considerations and identifies the Safety Goals, Stakeholder Objectives, and Design Objectives required by the Sandia Design Team to develop the Performance Criteria necessary to the design of Building 1012. This document recognizes the Architecture-Engineering (A-E) Team as the primary design entity. Where safety considerations are identified, suggestions are provided to provide context for the corresponding operational requirement(s).

  6. TESTING GUIDELINES FOR TECHNETIUM-99 ABSORPTION ON ACTIVATED CARBON

    SciTech Connect (OSTI)

    BYRNES ME

    2010-09-08T23:59:59.000Z

    CH2M HILL Plateau Remediation Company (CHPRC) is currently evaluating the potential use of activated carbon adsorption for removing technetium-99 from groundwater as a treatment method for the Hanford Site's 200 West Area groundwater pump-and-treat system. The current pump-and-treat system design will include an ion-exchange (IX) system for selective removal of technetium-99 from selected wells prior to subsequent treatment of the water in the central treatment system. The IX resin selected for technetium-99 removal is Purolite A530E. The resin service life is estimated to be approximately 66.85 days at the design technetium-99 loading rate, and the spent resin must be replaced because it cannot be regenerated. The resulting operating costs associated with resin replacement every 66.85 days are estimated at $0.98 million/year. Activated carbon pre-treatment is being evaluated as a potential cost-saving measure to offset the high operating costs associated with frequent IX resin replacement. This document is preceded by the Literature Survey of Technetium-99 Groundwater Pre-Treatment Option Using Granular Activated Carbon (SGW-43928), which identified and evaluated prior research related to technetium-99 adsorption on activated carbon. The survey also evaluated potential operating considerations for this treatment approach for the 200 West Area. The preliminary conclusions of the literature survey are as follows: (1) Activated carbon can be used to selectively remove technetium-99 from contaminated groundwater. (2) Technetium-99 adsorption onto activated carbon is expected to vary significantly based on carbon types and operating conditions. For the treatment approach to be viable at the Hanford Site, activated carbon must be capable of achieving a designated minimum technetium-99 uptake. (3) Certain radionuclides known to be present in 200 West Area groundwater are also likely to adsorb onto activated carbon. (4) Organic solvent contaminants of concern (COCs) will load heavily onto activated carbon and should be removed from groundwater upstream of the activated carbon pre-treatment system. Unless removed upstream, the adsorbed loadings of these organic constituents could exceed the land disposal criteria for carbon.

  7. Testing Oxygen Reduction Reaction Activity with the Rotating Disc Electrode

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the.pdfBreakingMayDepartmentTest for Pumping System Efficiency TestMarkTechnique |

  8. Higher Order Mutation Testing Submitted in fulfilment of the requirements for the

    E-Print Network [OSTI]

    Harman, Mark

    and Analysis: MSR for App Stores" (short paper), in Proceedings of the 9th Work- ing Conference on Mining- posium and the 13th European conference on Foundations of software engineer- ing (ESEC/FSE '11), Szeged faults Using Higher Order Mutation Testing", in Proceedings of the 8th International Working Confer- ence

  9. A tropomyosin-related kinase B ligand is required for ERK activation, long-term synaptic facilitation,

    E-Print Network [OSTI]

    Sharma, Shiv K.

    A tropomyosin-related kinase B ligand is required for ERK activation, long-term synaptic of BDNF to the TrkB receptor initiates a wide range of downstream signaling events, including ERK in Aplysia, and that this enhancing effect of BDNF in LTF induction requires ERK signaling (Fig. 1A and ref

  10. Activation of ERK/MAP Kinase in the Amygdala Is Required for Memory Consolidation of Pavlovian Fear Conditioning

    E-Print Network [OSTI]

    Schafe, Glenn

    Activation of ERK/MAP Kinase in the Amygdala Is Required for Memory Consolidation of Pavlovian Fear-regulated kinase/mitogen-activated protein kinase (ERK/ MAPK) signaling cascade in the amygdala during Pavlovian fear conditioning. We first show that ERK/MAPK is transiently acti- vated

  11. Recovery Efficiency Test Project: Phase 1, Activity report

    SciTech Connect (OSTI)

    Overbey, W.K. Jr.; Carden, R.S.; Kirr, J.N.

    1987-04-01T23:59:59.000Z

    The recovery Efficiency Test well project addressed a number of technical issues. The primary objective was to determine the increased efficiency gas recovery of a long horizontal wellbore over that of a vertical wellbore and, more specifically, what improvements can be expected from inducing multiple hydraulic fractures from such a wellbore. BDM corporation located, planned, and drilled a long radius turn horizontal well in the Devonian shale Lower Huron section in Wayne County, West Virginia, demonstrating that state-of-the-art technology is capable of drilling such wells. BDM successfully tested drilling, coring, and logging in a horizontal well using air as the circulating medium; conducted reservoir modeling studies to protect flow rates and reserves in advance of drilling operations; observed two phase flow conditions in the wellbore not observed previously; cored a fracture zone which produced gas; observed that fractures in the core and the wellbore were not systematically spaced (varied from 5 to 68 feet in different parts of the wellbore); observed that highest gas show rates reported by the mud logger corresponded to zone with lowest fracture spacing (five feet) or high fracture frequency. Four and one-half inch casting was successfully installed in the borehole and was equipped to isolate the horizontal section into eight (8) zones for future testing and stimulation operations. 6 refs., 48 figs., 10 tabs.

  12. A Simple test for the existence of two accretion modes in active galactic nuclei

    SciTech Connect (OSTI)

    Jester, Sebastian; /Fermilab

    2005-02-01T23:59:59.000Z

    By analogy to the different accretion states observed in black-hole X-ray binaries (BHXBs), it appears plausible that accretion disks in active galactic nuclei (AGN) undergo a state transition between a radiatively efficient and inefficient accretion flow. If the radiative efficiency changes at some critical accretion rate, there will be a change in the distribution of black hole masses and bolometric luminosities at the corresponding transition luminosity. To test this prediction, the author considers the joint distribution of AGN black hole masses and bolometric luminosities for a sample taken from the literature. The small number of objects with low Eddington-scaled accretion rates m < 0.01 and black hole masses M{sub BH} < 10{sup 9} M{sub {circle_dot}} constitutes tentative evidence for the existence of such a transition in AGN. Selection effects, in particular those associated with flux-limited samples, systematically exclude objects in particular regions of the (M{sub BH}, L{sub bol}) plane. Therefore, they require particular attention in the analysis of distributions of black hole mass, bolometric luminosity, and derived quantities like the accretion rate. The author suggests further observational tests of the BHXB-AGN unification scheme which are based on the jet domination of the energy output of BHXBs in the hard state, and on the possible equivalence of BHXB in the very high (or steep power-law) state showing ejections and efficiently accreting quasars and radio galaxies with powerful radio jets.

  13. Summary Report on FY12 Small-Scale Test Activities High Temperature Electrolysis Program

    SciTech Connect (OSTI)

    James O'Brien

    2012-09-01T23:59:59.000Z

    This report provides a description of the apparatus and the single cell testing results performed at Idaho National Laboratory during January–August 2012. It is an addendum to the Small-Scale Test Report issued in January 2012. The primary program objectives during this time period were associated with design, assembly, and operation of two large experiments: a pressurized test, and a 4 kW test. Consequently, the activities described in this report represent a much smaller effort.

  14. Laboratory Evaporation Testing Of Hanford Waste Treatment Plant Low Activity Waste Off-Gas Condensate Simulant

    SciTech Connect (OSTI)

    Adamson, Duane J.; Nash, Charles A.; McCabe, Daniel J.; Crawford, Charles L.; Wilmarth, William R.

    2014-01-27T23:59:59.000Z

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream, LAW Off-Gas Condensate, from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of canistered glass waste forms. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to be within acceptable concentration ranges in the LAW glass. Diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task examines the impact of potential future disposition of this stream in the Hanford tank farms, and investigates auxiliary evaporation to enable another disposition path. Unless an auxiliary evaporator is used, returning the stream to the tank farms would require evaporation in the 242-A evaporator. This stream is expected to be unusual because it will be very high in corrosive species that are volatile in the melter (chloride, fluoride, sulfur), will have high ammonia, and will contain carryover particulates of glass-former chemicals. These species have potential to cause corrosion of tanks and equipment, precipitation of solids, release of ammonia gas vapors, and scale in the tank farm evaporator. Routing this stream to the tank farms does not permanently divert it from recycling into the WTP, only temporarily stores it prior to reprocessing. Testing is normally performed to demonstrate acceptable conditions and limits for these compounds in wastes sent to the tank farms. The primary parameter of this phase of the test program was measuring the formation of solids during evaporation in order to assess the compatibility of the stream with the evaporator and transfer and storage equipment. The origin of this LAW Off-Gas Condensate stream will be the liquids from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW facility melter offgas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover. The soluble components are expected to be mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet, and, thus, the composition will not be available until the WTP begins operation, but a simulant has been produced based on models, calculations, and comparison with pilot-scale tests. This report discusses results of evaporation testing of the simulant. Two conditions were tested, one with the simulant at near neutral pH, and a second at alkaline pH. The neutral pH test is comparable to the conditions in the Hanford Effluent Treatment Facility (ETF) evaporator, although that evaporator operates at near atmospheric pressure and tests were done under vacuum. For the alkaline test, the target pH was based on the tank farm corrosion control program requirements, and the test protocol and equipment was comparable to that used for routine evaluation of feed compatibility studies for the 242-A evaporator. One of the

  15. Design and Test of an Event Detector for the ReflectoActive Seals System

    SciTech Connect (OSTI)

    Stinson, Brad J [ORNL

    2006-05-01T23:59:59.000Z

    The purpose of this thesis was to research, design, develop and test a novel instrument for detecting fiber optic loop continuity and spatially locating fiber optic breaches. The work is for an active seal system called ReflectoActive Seals whose purpose is to provide real time container tamper indication. A Field Programmable Gate Array was used to implement a loop continuity detector and a spatial breach locator based on a high acquisition speed single photon counting optical time domain reflectometer. Communication and other control features were added in order to create a usable instrument that met defined requirements. A host graphical user interface was developed to illustrate system use and performance. The resulting device meets performance specifications by exhibiting a dynamic range of 27dB and a spatial resolution of 1.5 ft. The communication scheme used expands installation options and allows the device to communicate to a central host via existing Local Area Networks and/or the Internet.

  16. Design and Test of an Event Detector and Locator for the ReflectoActive Seals System

    SciTech Connect (OSTI)

    Stinson, Brad J [ORNL

    2006-06-01T23:59:59.000Z

    The purpose of this work was to research, design, develop and test a novel instrument for detecting fiber optic loop continuity and spatially locating fiber optic breaches. The work is for an active seal system called ReflectoActive{trademark} Seals whose purpose is to provide real time container tamper indication. A Field Programmable Gate Array was used to implement a loop continuity detector and a spatial breach locator based on a high acquisition speed single photon counting optical time domain reflectometer. Communication and other control features were added in order to create a usable instrument that met defined requirements. A host graphical user interface was developed to illustrate system use and performance. The resulting device meets performance specifications by exhibiting a dynamic range of 27dB and a spatial resolution of 1.5 ft. The communication scheme used expands installation options and allows the device to communicate to a central host via existing Local Area Networks and/or the Internet.

  17. Steam Reforming, 6-in. Bench-Scale Design and Testing Project -- Technical and Functional Requirements Description

    SciTech Connect (OSTI)

    Losinski, Sylvester John; Marshall, Douglas William

    2002-08-01T23:59:59.000Z

    Feasibility studies and technology development work are currently being performed on several processes to treat radioactive liquids and solids currently stored at the Idaho Nuclear Technology and Engineering Center (INTEC), located within the Idaho National Engineering and Environmental Laboratory (INEEL). These studies and development work will be used to select a treatment process for treatment of the radioactive liquids and solids to meet treatment milestones of the Settlement Agreement between the Department of Energy and the State of Idaho. One process under consideration for treating the radioactive liquids and solids, specifically Sodium-Bearing Waste (SBW) and tank heel solids, is fluid bed steam reforming (FBSR). To support both feasibility and development studies a bench-scale FBSR is being designed and constructed. This report presents the technical and functional requirements, experimental objectives, process flow sheets, and equipment specifications for the bench-scale FBSR.

  18. Hanford Immobilized Low-Activity Waste Product Acceptance Test Plan

    SciTech Connect (OSTI)

    Peeler, D.

    1999-06-22T23:59:59.000Z

    'The Hanford Site has been used to produce nuclear materials for the U.S. Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during Pu production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The DOE is proceeding with an approach to privatize the treatment and immobilization of Handord''s LAW and HLW.'

  19. Results of Active Test of Uranium-Plutonium Co-denitration Facility at Rokkasho Reprocessing Plant

    SciTech Connect (OSTI)

    Numao, Teruhiko; Nakayashiki, Hiroshi; Arai, Nobuyuki; Miura, Susumu; Takahashi, Yoshiharu [Denitration Section, Plant Operation Dept., Reprocessing Plant, Reprocessing Business Division, Japan Nuclear Fuel Limited Rokkasho-mura, Kamikita-gun, Aomori-ken (Japan); Nakamura, Hironobu; Tanaka, Izumi [Technical Support Dept., Reprocessing Plant, Reprocessing Business Division, Japan Nuclear Fuel Limited Rokkasho-mura, Kamikita-gun, Aomori-ken (Japan)

    2007-07-01T23:59:59.000Z

    In the U-Pu co-denitration facility at Rokkasho Reprocessing Plant (RRP), Active Test which composes of 5 steps was performed by using uranium-plutonium nitrate solution that was extracted from spent fuels. During Active Test, two kinds of tests were performed in parallel. One was denitration performance test in denitration ovens, and expected results were successfully obtained. The other was validation and calibration of non-destructive assay (NDA) systems, and expected performances were obtained and their effectiveness as material accountancy and safeguards system was validated. (authors)

  20. What are the required maintenance and consolidation activities to run at design performance levels (injectors and LHC) until 2035?

    E-Print Network [OSTI]

    Baird, S

    2014-01-01T23:59:59.000Z

    Assuming that Linac4 is connected to the PSB in LS2, we will outline the maintenance and basic consolidation works that will be needed to maintain design performance of the LHC and its Injector chain until 2035, with an overall reliability as good as that achieved in the first LHC operation period 2009 to 2013. Using these data we will estimate the shutdown schedule needed throughout this period to complete these maintenance and consolidation works. These estimates will also include the required radiation cool-down periods, time for system re-commissioning and testing as well as the time needed to restart the accelerator chain for LHC colliding beam operation. As some of the consolidation activities needed for the PS and SPS machines are related to the radia tion dose taken by the machine equipment (e.g., irradiated cable replacement and magnet renovation) the variation of these time estimates as a function of beam losses in the Injector chain will also be covered.

  1. Hybrid Electric and Plug-in Hybrid Electric Vehicle Testing Activities

    SciTech Connect (OSTI)

    Donald Karner

    2007-12-01T23:59:59.000Z

    The Advanced Vehicle Testing Activity (AVTA) conducts hybrid electric vehicle (HEV) and plug-in hybrid electric vehicle (PHEV) testing in order to provide benchmark data for technology modeling and research and development programs, and to be an independent source of test data for fleet managers and other early adaptors of advanced-technology vehicles. To date, the AVTA has completed baseline performance testing on 12 HEV models and accumulated 2.7 million fleet testing miles on 35 HEVs. The HEV baseline performance testing includes dynamometer and closed-track testing to document HEV performance in a controlled environment. During fleet testing, two of each HEV model accumulate 160,000 test miles within 36 months, during which maintenance and repair events and fuel use were recorded. Three models of PHEVs, from vehicle converters Energy CS and Hymotion and the original equipment manufacturer Renault, are currently in testing. The PHEV baseline performance testing includes 5 days of dynamometer testing with a minimum of 26 test drive cycles, including the Urban Dynamometer Driving Schedule, the Highway Fuel Economy Driving Schedule, and the US06 test cycle, in charge-depleting and charge-sustaining modes. The PHEV accelerated testing is conducted with dedicated drivers for 4,240 miles, over a series of 132 driving loops that range from 10 to 200 miles over various combinations of defined 10-mile urban and 10-mile highway loops, with 984 hours of vehicle charging. The AVTA is part of the U.S. Department of Energy’s FreedomCAR and Vehicle Technologies Program. These AVTA testing activities were conducted by the Idaho National Laboratory and Electric Transportation Applications, with dynamometer testing conducted at Argonne National Laboratory. This paper discusses the testing methods and results.

  2. Design of test bench apparatus and preliminary weight reduction strategy for an active knee prosthesis

    E-Print Network [OSTI]

    Lau, Jacky H. (Jacky Homing)

    2011-01-01T23:59:59.000Z

    This thesis presents the design and structural analyses of an experimental test bench for the characterization of an active biomimetic knee prosthesis currently being developed by the Biomechatronics research group at MIT ...

  3. Supplemental Immobilization of Hanford Low-Activity Waste: Cast Stone Screening Tests

    SciTech Connect (OSTI)

    Westsik, Joseph H.; Piepel, Gregory F.; Lindberg, Michael J.; Heasler, Patrick G.; Mercier, Theresa M.; Russell, Renee L.; Cozzi, Alex; Daniel, William E.; Eibling, Russell E.; Hansen, E. K.; Reigel, Marissa M.; Swanberg, David J.

    2013-09-30T23:59:59.000Z

    More than 56 million gallons of radioactive and hazardous waste are stored in 177 underground storage tanks at the U.S. Department of Energy’s (DOE’s) Hanford Site in southeastern Washington State. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the wastes and immobilize them in a glass waste form. The WTP includes a pretreatment facility to separate the wastes into a small volume of high-level waste (HLW) containing most of the radioactivity and a larger volume of low-activity waste (LAW) containing most of the nonradioactive chemicals. The HLW will be converted to glass in the HLW vitrification facility for ultimate disposal at an offsite federal repository. At least a portion (~35%) of the LAW will be converted to glass in the LAW vitrification facility and will be disposed of onsite at the Integrated Disposal Facility (IDF). The pretreatment and HLW vitrification facilities will have the capacity to treat and immobilize the wastes destined for each facility. However, a second LAW immobilization facility will be needed for the expected volume of LAW requiring immobilization. A cementitious waste form known as Cast Stone is being considered to provide the required additional LAW immobilization capacity. The Cast Stone waste form must be acceptable for disposal in the IDF. The Cast Stone waste form and immobilization process must be tested to demonstrate that the final Cast Stone waste form can comply with the waste acceptance criteria for the disposal facility and that the immobilization processes can be controlled to consistently provide an acceptable waste form product. Further, the waste form must be tested to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support risk assessment and performance assessment (PA) analyses of the long-term environmental impact of the waste disposal in the IDF. The PA is needed to satisfy both Washington State IDF Permit and DOE Order requirements. Cast Stone has been selected for solidification of radioactive wastes including WTP aqueous secondary wastes treated at the Effluent Treatment Facility (ETF) at Hanford. A similar waste form called Saltstone is used at the Savannah River Site (SRS) to solidify its LAW tank wastes.

  4. Current Activities at the ACRELab Renewable Energy Systems Test T.L. Pryor1

    E-Print Network [OSTI]

    of the Australian CRC for Renewable Energy (ACRE) on the Murdoch University campus in Perth, Western Australia is a testing laboratory for Renewable Energy (RE) Systems based at the ACRE headquarters in Perth, AustraliaCurrent Activities at the ACRELab Renewable Energy Systems Test Facility T.L. Pryor1 , E.S. Spooner

  5. High Heat Flux Exposure Tests on 10mm Beryllium Tiles Brazed on Actively Cooled Vapotron made from CUCRZR

    E-Print Network [OSTI]

    High Heat Flux Exposure Tests on 10mm Beryllium Tiles Brazed on Actively Cooled Vapotron made from CUCRZR

  6. Measurement and Verification Activities Required in the Energy Savings Performance Contract Process

    Broader source: Energy.gov [DOE]

    There are four major measurement and verification (M&V) activities in the energy savings performance contract (ESPC) procurement process.

  7. A review of two recent occurrences at the Advanced Test Reactor involving subcontractor activities

    SciTech Connect (OSTI)

    Dahlke, H.J.; Jensen, N.C.; Vail, J.A.

    1997-11-01T23:59:59.000Z

    This report documents the results of a brief, unofficial investigation into two incidents at the Idaho National Engineering and Environmental Laboratory (INEEL) Advanced Test Reactor (ATR) facility, reported on October 25 and 31, 1997. The first event was an unanticipated breach of confinement. The second involved reactor operation with an inoperable seismic scram subsystem, violating the reactor`s Technical Specifications. These two incidents have been found to be unrelated. A third event that occurred on December 16, 1996, is also discussed because of its similarities to the first event listed above. Both of these incidents were unanticipated breaches of confinement, and both involved the work of construction subcontractor personnel. The cause for the subcontractor related occurrences is a work control process that fails to effectively interface with LMITCO management. ATR Construction Project managers work sufficient close with construction subcontractor personnel to understand planned day-to-day activities. They also have sufficient training and understanding of reactor operations to ensure adherence to applicable administrative requirements. However, they may not be sufficiently involved in the work authorization and control process to bridge an apparent communications gap between subcontractor employees and Facility Operations/functional support personnel for work inside the reactor facility. The cause for the inoperable seismic scram switch (resulting from a disconnected lead) is still under investigation. It does not appear to be subcontractor related.

  8. U.S. Department of Energy FreedomCAR & Vehicle Technologies Program Advanced Vehicle Testing Activity, Hydrogen/CNG Blended Fuels Performance Testing in a Ford F-150

    SciTech Connect (OSTI)

    James E. Francfort

    2003-11-01T23:59:59.000Z

    Federal regulation requires energy companies and government entities to utilize alternative fuels in their vehicle fleets. To meet this need, several automobile manufacturers are producing compressed natural gas (CNG)-fueled vehicles. In addition, several converters are modifying gasoline-fueled vehicles to operate on both gasoline and CNG (Bifuel). Because of the availability of CNG vehicles, many energy company and government fleets have adopted CNG as their principle alternative fuel for transportation. Meanwhile, recent research has shown that blending hydrogen with CNG (HCNG) can reduce emissions from CNG vehicles. However, blending hydrogen with CNG (and performing no other vehicle modifications) reduces engine power output, due to the lower volumetric energy density of hydrogen in relation to CNG. Arizona Public Service (APS) and the U.S. Department of Energy’s Advanced Vehicle Testing Activity (DOE AVTA) identified the need to determine the magnitude of these effects and their impact on the viability of using HCNG in existing CNG vehicles. To quantify the effects of using various blended fuels, a work plan was designed to test the acceleration, range, and exhaust emissions of a Ford F-150 pickup truck operating on 100% CNG and blends of 15 and 30% HCNG. This report presents the results of this testing conducted during May and June 2003 by Electric Transportation Applications (Task 4.10, DOE AVTA Cooperative Agreement DEFC36- 00ID-13859).

  9. Amino acid nutrition of the red drum (Sciaenops ocellatus): development of an improved test diet and determination of the total sulfur amino acid requirement

    E-Print Network [OSTI]

    Moon, Hae Young

    1990-01-01T23:59:59.000Z

    AMINO ACID NUTRITION OF THE RED DRUM (SCIAENOPS OCELLATUS): DEVELOPMENT OF AN IMPROVED TEST DIET AND DETERMINATION OF THE TOTAL SULFUR AMINO ACID REQUIREMENT A Thesis by HAE YOUNG MOON Submitted to the Office of Graduate Studies of Texas A...&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE May 1990 Major Subject: Wildlife and Fisheries Sciences AMINO ACID NUTRITION OF THE RED DRUM (SCIAENOPS OCELLATUS): DEVELOPMENT OF AN IMPROVED TEST DIET...

  10. Experimental neutronics tests for a neutron activation system for the European ITER TBM

    SciTech Connect (OSTI)

    Klix, A.; Fischer, U. [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Gehre, D. [Technical University of Dresden, IKTP, Zellescher Weg 19, 01062 Dresden (Germany); Kleizer, G. [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany and Budapest University of Technology and Economics, M?egyetem rkp. 3-9. H-1111 Budapest (Hungary); Raj, P. [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany and Université Paris-Sud, 15 rue Georges Clemenceau, F-91405 Paris (France); Rovni, I. [Budapest University of Technology and Economics, M?egyetem rkp. 3-9. H-1111 Budapest (Hungary); Ruecker, Tom [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany and University of Applied Sciences Zittau-Goerlitz, Theodor-Körner-Allee 16, D-02754 Zittau (Germany)

    2014-08-21T23:59:59.000Z

    We are investigating methods for neutron flux measurement in the ITER TBM. In particular we have tested sets of activation materials leading to induced gamma activities with short half-lives of the order of tens of seconds up to minutes and standard activation materials. Packages of activation foils have been irradiated with the intense neutron generator of Technical University of Dresden in a pure DT neutron field as well as in a neutronics mock-up of the European ITER HCLL TBM. An important aim was to check whether the gamma activity induced in the activation foils in these packages could be measured simultaneously. It was indeed possible to identify gamma lines of interest in gamma-ray measurements immediately after extraction from the irradiation.

  11. Requirements Definition Stage

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

    1997-05-21T23:59:59.000Z

    This chapter addresses development of a Software Configuration Management Plan to track and control work products, analysis of the system owner/users' business processes and needs, translation of those processes and needs into formal requirements, and planning the testing activities to validate the performance of the software product.

  12. Engineering Scaling Requirements for Solid Breeder Blanket Testing A. Ying, S. Sharafat, M. Youssef, J. An, R. Hunt, P. Rainsberry, M. Abdou

    E-Print Network [OSTI]

    Abdou, Mohamed

    Engineering Scaling Requirements for Solid Breeder Blanket Testing A. Ying, S. Sharafat, M. Youssef@fusion.ucla.edu An engineering scaling process is applied to the solid breeder ITER TBM designs in accordance with the testing objectives of validating the design tools and the database, and evaluating blanket performance under

  13. Contract to coordinate on-going documentation requirements associated with Title X legislation for DOE active-solar activities. Final project technical report

    SciTech Connect (OSTI)

    Not Available

    1982-06-01T23:59:59.000Z

    The objectives of this work were to ensure that Title X Active Solar Program reports complied with all guidance regarding length, format, coverage, tone, tables and schedules; provide necessary Conservation and Renewable Energy Office background and back-up material; follow this activity through to its completion in January 1982; assess information requirements associated with on-going documentation of Federal Buildings Program and its predecessors; establish a method for collecting, maintaining and utilizing appropriate program data specifically related to the preparation of report due in June 1982. Work on this project has generally remained on schedule and within budget. DOE-SAN has been instrumental in keeping us on track, by providing timely guidance as needed. Attached are recommendations and methods for documenting solar heat technologies research and the Title X sunset policy, planning, and evaluation long report for Active Solar Heating and Cooling Program.

  14. Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

    SciTech Connect (OSTI)

    Michael Kruzic

    2007-09-01T23:59:59.000Z

    Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D&D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release.

  15. Requirements for Defining Utility Drive Cycles: An Exploratory Analysis of Grid Frequency Regulation Data for Establishing Battery Performance Testing Standards

    SciTech Connect (OSTI)

    Hafen, Ryan P.; Vishwanathan, Vilanyur V.; Subbarao, Krishnappa; Kintner-Meyer, Michael CW

    2011-10-19T23:59:59.000Z

    Battery testing procedures are important for understanding battery performance, including degradation over the life of the battery. Standards are important to provide clear rules and uniformity to an industry. The work described in this report addresses the need for standard battery testing procedures that reflect real-world applications of energy storage systems to provide regulation services to grid operators. This work was motivated by the need to develop Vehicle-to-Grid (V2G) testing procedures, or V2G drive cycles. Likewise, the stationary energy storage community is equally interested in standardized testing protocols that reflect real-world grid applications for providing regulation services. As the first of several steps toward standardizing battery testing cycles, this work focused on a statistical analysis of frequency regulation signals from the Pennsylvania-New Jersey-Maryland Interconnect with the goal to identify patterns in the regulation signal that would be representative of the entire signal as a typical regulation data set. Results from an extensive time-series analysis are discussed, and the results are explained from both the statistical and the battery-testing perspectives. The results then are interpreted in the context of defining a small set of V2G drive cycles for standardization, offering some recommendations for the next steps toward standardizing testing protocols.

  16. Charpy impact test results for low activation ferritic alloys irradiated to 30 dpa

    SciTech Connect (OSTI)

    Schubert, L.E.; Hamilton, M.L.; Gelles, D.S. [Pacific Northwest National Laboratory, Richland, WA (United States)

    1996-04-01T23:59:59.000Z

    Miniature specimens of six low activation ferritic alloys have been impact field tested following irradiation at 370{degrees}C to 30 dpa. Comparison of the results with those of control specimens and specimens irradiated to 10 dpa indicates that degradation in the impact behavior appears to have saturated by {approx}10 dpa in at least four of these alloys. The 7.5Cr-2W alloy referred to as GA3X appears most promising for further consideration as a candidate structural material in fusion reactor applications, although the 9Cr-1V alloy may also warrant further investigation.

  17. Field Testing of Activated Carbon Injection Options for Mercury Control at TXU's Big Brown Station

    SciTech Connect (OSTI)

    John Pavlish; Jeffrey Thompson; Christopher Martin; Mark Musich; Lucinda Hamre

    2009-01-07T23:59:59.000Z

    The primary objective of the project was to evaluate the long-term feasibility of using activated carbon injection (ACI) options to effectively reduce mercury emissions from Texas electric generation plants in which a blend of lignite and subbituminous coal is fired. Field testing of ACI options was performed on one-quarter of Unit 2 at TXU's Big Brown Steam Electric Station. Unit 2 has a design output of 600 MW and burns a blend of 70% Texas Gulf Coast lignite and 30% subbituminous Powder River Basin coal. Big Brown employs a COHPAC configuration, i.e., high air-to-cloth baghouses following cold-side electrostatic precipitators (ESPs), for particulate control. When sorbent injection is added between the ESP and the baghouse, the combined technology is referred to as TOXECON{trademark} and is patented by the Electric Power Research Institute in the United States. Key benefits of the TOXECON configuration include better mass transfer characteristics of a fabric filter compared to an ESP for mercury capture and contamination of only a small percentage of the fly ash with AC. The field testing consisted of a baseline sampling period, a parametric screening of three sorbent injection options, and a month long test with a single mercury control technology. During the baseline sampling, native mercury removal was observed to be less than 10%. Parametric testing was conducted for three sorbent injection options: injection of standard AC alone; injection of an EERC sorbent enhancement additive, SEA4, with ACI; and injection of an EERC enhanced AC. Injection rates were determined for all of the options to achieve the minimum target of 55% mercury removal as well as for higher removals approaching 90%. Some of the higher injection rates were not sustainable because of increased differential pressure across the test baghouse module. After completion of the parametric testing, a month long test was conducted using the enhanced AC at a nominal rate of 1.5 lb/Macf. During the time that enhanced AC was injected, the average mercury removal for the month long test was approximately 74% across the test baghouse module. ACI was interrupted frequently during the month long test because the test baghouse module was bypassed frequently to relieve differential pressure. The high air-to-cloth ratio of operations at this unit results in significant differential pressure, and thus there was little operating margin before encountering differential pressure limits, especially at high loads. This limited the use of sorbent injection as the added material contributes to the overall differential pressure. This finding limits sustainable injection of AC without appropriate modifications to the plant or its operations. Handling and storage issues were observed for the TOXECON ash-AC mixture. Malfunctioning equipment led to baghouse dust hopper plugging, and storage of the stagnant material at flue gas temperatures resulted in self-heating and ignition of the AC in the ash. In the hoppers that worked properly, no such problems were reported. Economics of mercury control at Big Brown were estimated for as-tested scenarios and scenarios incorporating changes to allow sustainable operation. This project was funded under the U.S. Department of Energy National Energy Technology Laboratory project entitled 'Large-Scale Mercury Control Technology Field Testing Program--Phase II'.

  18. Preliminary Glass Development and Testing for In-Container Vitrification of Hanford Low-Activity Waste

    SciTech Connect (OSTI)

    Vienna, John D.; Kim, Dong-Sang; Schweiger, Michael J.; Hrma, Pavel R.; Matyas, Josef; Crum, Jarrod V.; Smith, Donald E.

    2004-01-01T23:59:59.000Z

    Roughly 50 million gallons of high-level waste (HLW) are stored at the Hanford site. This waste will be separated into HLW and low-activity waste (LAW) fractions and each fraction will be immobilized for final storage/disposal. The US Department of Energy (DOE) Office of River Protection (ORP) is constructing a Waste Treatment and Immobilization Plant (WTP) which will be capable of separating the waste, vitrifying the entire HLW fraction of the waste and vitrifying roughly 50% the LAW fraction. The remaining fraction of LAW will be immobilized by one of a number of possible technologies. ORP is currently evaluating options for LAW immobilization. One possible option is In-Container Vitrification (ICV) of the LAW. ICV is a technology developed by AMEC, GeoMelt Division, for treatment of hazardous, radioactive, and mixed wastes. The ICV process, as applied to Hanford LAW, includes the blending of liquid waste with additives (primarily composed of local soil) and drying to a granular state. The dried material is loaded into a refractory lined steel box and melted by passing a current through the material between two graphite electrodes. The box containing the molten waste/additive mixture is cooled, backfilled, and disposed of. The purpose of the study was to develop a glass composition suitable for the demonstration of ICV on Hanford LAW at full scale. Testing included crucible-scale tests with simulants and actual Hanford LAW. Following the crucible-scale tests, engineering-scale and large-scale melts were performed with LAW simulants. This paper discusses the formulation and testing of glass compositions for ICV of Hanford LAW at crucible scale. The results from process scale-up test are reported elsewhere.

  19. Vehicle Technologies Office Merit Review 2014: Overview and Progress of the Battery Testing, Design and Analysis Activity

    Broader source: Energy.gov [DOE]

    Presentation given by the Department of Energy's Energy Storage area at 2014 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Office Annual Merit Review and Peer Evaluation Meeting about the battery testing, design, and analysis activity.

  20. A data base and a standard material for use in acceptance testing of low-activity waste products

    SciTech Connect (OSTI)

    Wolf, S.F.; Ebert, W.L.; Luo, J.S.; Strachan, D.M.

    1998-04-01T23:59:59.000Z

    The authors have conducted replicate dissolution tests following the product consistency test (PCT) procedure to measure the mean and standard deviation of the solution concentrations of B, Na, and Si at various combinations of temperature, duration, and glass/water mass ratio. Tests were conducted with a glass formulated to be compositionally similar to low-activity waste products anticipated for Hanford to evaluate the adequacy of test methods that have been designated in privatization contracts for use in product acceptance. An important finding from this set of tests is that the solution concentrations generated in tests at 20 C will likely be too low to measure the dissolution rates of waste products reliably. Based on these results, the authors recommend that the acceptance test be conducted at 40 C. Tests at 40 C generated higher solution concentrations, were more easily conducted, and the measured rates were easily related to those at 20 C. Replicate measurements of other glass properties were made to evaluate the possible use of LRM-1 as a standard material. These include its composition, homogeneity, density, compressive strength, the Na leachability index with the ANSI/ANS 16.1 leach test, and if the glass is characteristically hazardous with the toxicity characteristic leach procedure. The values of these properties were within the acceptable limits identified for Hanford low-activity waste products. The reproducibility of replicate tests and analyses indicates that the glass would be a suitable standard material.

  1. Coupled optical/thermal/fluid analysis and design requirements for operation and testing of a supercritical CO2 solar receiver.

    SciTech Connect (OSTI)

    Khivsara, Sagar [Indian Institute of Science, Bangalor (India)

    2015-01-01T23:59:59.000Z

    Recent studies have evaluated closed-loop supercritical carbon dioxide (s-CO2) Brayton cycles to be a higher energy-density system in comparison to conventional superheated steam Rankine systems. At turbine inlet conditions of 923K and 25 MPa, high thermal efficiency (~50%) can be achieved. Achieving these high efficiencies will make concentrating solar power (CSP) technologies a competitive alternative to current power generation methods. To incorporate a s-CO2 Brayton power cycle in a solar power tower system, the development of a solar receiver capable of providing an outlet temperature of 923 K (at 25 MPa) is necessary. To satisfy the temperature requirements of a s-CO2 Brayton cycle with recuperation and recompression, it is required to heat s-CO2 by a temperature of ~200 K as it passes through the solar receiver. Our objective was to develop an optical-thermal-fluid model to design and evaluate a tubular receiver that will receive a heat input ~1 MWth from a heliostat field. We also undertook the documentation of design requirements for the development, testing and safe operation of a direct s-CO2 solar receiver. The main purpose of this document is to serve as a reference and guideline for design and testing requirements, as well as to address the technical challenges and provide initial parameters for the computational models that will be employed for the development of s-CO2 receivers.

  2. Accumulation of operational history through emulation test to meet proven technology requirement for newly developed I and C technology

    SciTech Connect (OSTI)

    Yeong Cheol, Shin; Sung Kon, Kang [Nuclear Environment Technology Institute (NETEC), Korea Hydro and Nuclear Power(KHNP) P.O. Box Youseong-gu Daejeon (Korea, Republic of); Han Seong, Son [ENESYS Co., Ltd. 3F, Pianetta Bldg., 337-2, Jangdae-dong, Yuseong-gu, Daejeon (Korea, Republic of)

    2006-07-01T23:59:59.000Z

    As new advanced digital I and C technology with potential benefits of higher functionality and better cost effectiveness is available in the market, NPP (Nuclear Power Plant) operators are inclined to use the new technology for the construction of new plant and the upgrade of existing plants. However, this new technology poses risks to the NPP operators at the same time. These risks are mainly due to the poor reliability of newly developed technology. KHNP's past experiences with the new equipment shows many cases of reliability problems. And their consequences include unintended plant trips, lowered acceptance of the new digital technology by the plant I and C maintenance crew, and increased licensing burden in answering for questions from the nuclear regulatory body. Considering the fact that the risk of these failures in the nuclear plant operation is far greater than those in other industry, nuclear power plant operators want proven technology for I and C systems. This paper presents an approach for the emulation of operational history through which a newly developed technology becomes a proven technology. One of the essential elements of this approach is the feedback scheme of running the new equipment in emulated environment, gathering equipment failure, and correcting the design(and test bed). The emulation of environment includes normal and abnormal events of the new equipment such as reconfiguration of control system due to power failure, plant operation including full spectrum of credible scenarios in an NPP. Emulation of I and C equipment execution mode includes normal operation, initialization and termination, abnormal operation, hardware maintenance and maintenance of algorithm/software. Plant specific simulator is used to create complete profile of plant operational conditions that I and C equipment is to experience in the real plant. Virtual operating crew technology is developed to run the simulator scenarios without involvement of actual operators at the emulated environment. Verification and validation are performed for detecting problems of the new technology. Verification of the equipment is done in two ways, one is to evaluate the features of the equipment according to the criteria derived from good practices of well proven I and C products and the second is to evaluate the features of the equipment by I and C experts. Validations are done in two ways, one is to validate the functions and performance of the equipment and the other is to validate the robustness of the equipment by accumulation operational experience. (authors)

  3. Wind Tunnel and Flight Testing of Active Flow Control on a UAV

    E-Print Network [OSTI]

    Babbar, Yogesh

    2011-08-08T23:59:59.000Z

    Active flow control has been extensively explored in wind tunnel studies but successful in-flight implementation of an active flow control technology still remains a challenge. This thesis presents implementation of active flow control technology...

  4. Iodine Adsorption on Ion-Exchange Resins and Activated Carbons– Batch Testing

    SciTech Connect (OSTI)

    Parker, Kent E.; Golovich, Elizabeth C.; Wellman, Dawn M.

    2014-09-30T23:59:59.000Z

    Iodine sorption onto seven resins and six carbon materials was evaluated using water from well 299-W19-36 on the Hanford Site. These materials were tested using a range of solution-to-solid ratios. The test results are as follows: • The efficacy of the resin and granular activated carbon materials was less than predicted based on manufacturers’ performance data. It is hypothesized that this is due to the differences in speciation previously determined for Hanford groundwater. • The sorption of iodine is affected by the iodine species in the source water. Iodine loading on resins using source water ranged from 1.47 to 1.70 µg/g with the corresponding Kd values from 189.9 to 227.0 mL/g. The sorption values when the iodine is converted to iodide ranged from 2.75 to 5.90 µg/g with the corresponding Kd values from 536.3 to 2979.6 mL/g. It is recommended that methods to convert iodine to iodide be investigated in fiscal year (FY) 2015. • The chemicals used to convert iodine to iodate adversely affected the sorption of iodine onto the carbon materials. Using as-received source water, loading and Kd values ranged from 1.47 to 1.70 µg/g and 189.8 to 226.3 mL/g respectively. After treatment, loading and Kd values could not be calculated because there was little change between the initial and final iodine concentration. It is recommended the cause of the decrease in iodine sorption be investigated in FY15. • In direct support of CH2M HILL Plateau Remediation Company, Pacific Northwest National Laboratory has evaluated samples from within the 200W pump and treat bioreactors. As part of this analysis, pictures taken within the bioreactor reveal a precipitate that, based on physical properties and known aqueous chemistry, is hypothesized to be iron pyrite or chalcopyrite, which could affect iodine adsorption. It is recommended these materials be tested at different solution-to-solid ratios in FY15 to determine their effect on iodine sorption.

  5. Testing a model of variability of X-ray reprocessing features in Active Galactic Nuclei

    E-Print Network [OSTI]

    P. T. Zycki; A. Rozanska

    2001-02-13T23:59:59.000Z

    A number of recent results from X-ray observations of Active Galactic Nuclei involving the Fe K alpha line (reduction of line variability compared to the X-ray continuum variability, the X-ray ``Baldwin effect'') were attributed to a presence of a hot, ionized skin of an accretion disc, suppressing emission of the line. The ionized skin appears as a result of the thermal instability of X-ray irradiated plasma. We test this hypothesis by computing the Thomson thickness of the hot skin on top of the 'alpha P_tot' Shakura-Sunyaev disc, by simultaneously solving the vertical structure of both the hot skin and the disc. We then compute a number of relations between observable quantities, e.g. the hard X-ray flux, amplitude of the observed reprocessed component, relativistic smearing of the K alpha line, the r.m.s. variability of the hard X-rays. These relations can be compared to present and future observations. We point out that this mechanism is unlikely to explain the behaviour of the X-ray source in MCG-6-30-15, where there is a number of arguments against the existence of a thick hot skin, but it can work for some other Seyfert 1 galaxies.

  6. Mechanism and Site Requirements for Activation and Chemical Conversion of Methane on Supported Pt Clusters and Turnover Rate Comparisons among Noble Metals

    E-Print Network [OSTI]

    Iglesia, Enrique

    Mechanism and Site Requirements for Activation and Chemical Conversion of Methane on Supported Pt smaller than the rate of methane chemical conversion in CO2 and H2O reforming reactions; thus, C-H bond and Pt2,3,8-32 lead to H2/CO mixtures useful as precursors to fuels and petrochemicals. Pt appears

  7. Purification of soluble and active RaxH, a transmembrane histidine protein kinase from Xanthomonas oryzae pv. oryzae required for AvrXa21 activity.

    E-Print Network [OSTI]

    Stolov, Avital; Valverde, Angel; Ronald, Pamela; Burdman, Saul

    2007-01-01T23:59:59.000Z

    to multiple Xanthomonas oryzae pv. oryzae isolates insystem in Xanthomonas oryzae pv. oryzae required for AvrXa21genes from Xanthomonas oryzae pv. oryzae. Mol. Plant–Microbe

  8. Reactor Room Experimental SF6 Tests to Determine Probable Stack Activity Response to Radioactive Releases

    SciTech Connect (OSTI)

    Cooper, R.E.

    2002-08-19T23:59:59.000Z

    This study was performed to obtain information that could be useful for obtaining an early estimate of the probable total stack activity monitor response in the event of an accidental release of radioactive activity in the process room.

  9. Activity report

    SciTech Connect (OSTI)

    Yu, S W

    2008-08-11T23:59:59.000Z

    This report is aimed to show the author's activities to support the LDRD. The title is 'Investigation of the Double-C Behavior in the Pu-Ga Time-Temperature-Transformation Diagram' The sections are: (1) Sample Holder Test; (2) Calculation of x-ray diffraction patterns; (3) Literature search and preparing publications; (4) Tasks Required for APS Experiments; and (5) Communications.

  10. NEUTRON ACTIVATION COOL-DOWN OF THE TOKAMAK FUSION TEST REACTOR

    E-Print Network [OSTI]

    involved the safe handling and processing about 100g of tritium. This resulted in manageable long concrete Test Cell showing the relative locations of the vessel, neutral beam injection systems, the vacuum. INTRODUCTION The Tokamak Fusion Test Reactor (TFTR) began high power deuterium-tritium (D-T) fueled operations

  11. A Regression Test Selection Technique for Graphical User Interfaces

    E-Print Network [OSTI]

    Chesser, Carl

    2012-08-31T23:59:59.000Z

    Regression testing is a quality control measure to ensure that the newly modified part of the software still complies with its specified requirements and that the unmodified part has not been affected by the maintenance activity. Regression testing...

  12. Title: Analytic Evolutions in the Digital Ocean Until recently, the collection of data regarding the activity of learners typically required

    E-Print Network [OSTI]

    of tests. The high cost of data collection and manipulation led to a relative paucity of data we referTitle: Analytic Evolutions in the Digital Ocean Abstract: Until recently, the collection of data performance data. This leads to a potential wealth of informative data we call the digital ocean. The two eras

  13. Direct Contacts Between Extracellular Membrane-Proximal Domains are Required for VEGF Receptor Activation and Cell Signaling

    SciTech Connect (OSTI)

    Yang, Y.; Xie, P; Opatowsky, Y; Schlessinger, J

    2010-01-01T23:59:59.000Z

    Structural analyses of the extracellular region of stem cell factor (SCF) receptor (also designated KIT) in complex with SCF revealed a sequence motif in a loop in the fourth Ig-like domain (D4) that is responsible for forming homotypic receptor contacts and for ligand-induced KIT activation and cell signaling. An identical motif was identified in the most membrane-proximal seventh Ig-like domain (D7) of vascular endothelial growth factor receptor 1 (VEGFR1), VEGFR2, and VEGFR3. In this report we demonstrate that ligand-induced tyrosine autophosphorylation and cell signaling via VEGFR1 or VEGFR2 harboring mutations in critical residues (Arg726 or Asp731) in D7 are strongly impaired. We also describe the crystal structure of D7 of VEGFR2 to a resolution of 2.7 {angstrom}. The structure shows that homotypic D7 contacts are mediated by salt bridges and van der Waals contacts formed between Arg726 of one protomer and Asp731 of the other protomer. The structure of D7 dimer is very similar to the structure of D4 dimers seen in the crystal structure of KIT extracellular region in complex with SCF. The high similarity between VEGFR D7 and KIT D4 in both structure and function provides further evidence for common ancestral origins of type III and type V RTKs. It also reveals a conserved mechanism for RTK activation and a novel target for pharmacological intervention of pathologically activated RTKs.

  14. Activity testing of fine-particle size, iron catalysts for coal liquefaction

    SciTech Connect (OSTI)

    Stohl, F.V.; Diegert, K.V.; Gugliotta, T.P.

    1993-10-01T23:59:59.000Z

    The use of fine-particle size (< 40 nm) unsupported catalysts in direct coal liquefaction may result in improved economics due to possible enhanced yields of desired products, the potential for decreasing reaction severity, and the possibility of using less catalyst. Sandia has developed a standard testing procedure for evaluating and comparing the fine-particle catalysts. The test procedure uses phenanthrene as the reaction solvent, the DECS-17 Blind Canyon Coal, and a statistical experimental design to enable evaluation of the catalysts over ranges of temperature (350 to 400{degrees}C), time (20 to 60 minutes), and catalyst loading (0 to 1 wt % on a dmmf coal basis). Product analyses include tetrahydrofuran (THF) conversion, heptane conversion, solvent recovery, and gas analyses. Phenanthrene as the solvent in the testing procedure yielded significant differences between thermal and catalytic reactions, whereas using a good hydrogen donor such as 9,10-dihydrophenanthrene (DHP) showed no catalytic effects.

  15. USING A DIFFERENTIAL EMISSION MEASURE AND DENSITY MEASUREMENTS IN AN ACTIVE REGION CORE TO TEST A STEADY HEATING MODEL

    SciTech Connect (OSTI)

    Winebarger, Amy R. [NASA Marshall Space Flight Center, VP 62, Huntsville, AL 35812 (United States); Schmelz, Joan T. [Physics Department, University of Memphis, Memphis, TN 38152 (United States); Warren, Harry P. [Space Science Division, Naval Research Laboratory, Washington, DC 20375 (United States); Saar, Steve H.; Kashyap, Vinay L., E-mail: amy.r.winebarger@nasa.gov [Harvard-Smithsonian Center for Astrophysics, Cambridge, MA 02138 (United States)

    2011-10-10T23:59:59.000Z

    The frequency of heating events in the corona is an important constraint on the coronal heating mechanisms. Observations indicate that the intensities and velocities measured in active region cores are effectively steady, suggesting that heating events occur rapidly enough to keep high-temperature active region loops close to equilibrium. In this paper, we couple observations of active region (AR) 10955 made with the X-Ray Telescope and the EUV Imaging Spectrometer on board Hinode to test a simple steady heating model. First we calculate the differential emission measure (DEM) of the apex region of the loops in the active region core. We find the DEM to be broad and peaked around 3 MK. We then determine the densities in the corresponding footpoint regions. Using potential field extrapolations to approximate the loop lengths and the density-sensitive line ratios to infer the magnitude of the heating, we build a steady heating model for the active region core and find that we can match the general properties of the observed DEM for the temperature range of 6.3 < log T < 6.7. This model, for the first time, accounts for the base pressure, loop length, and distribution of apex temperatures of the core loops. We find that the density-sensitive spectral line intensities and the bulk of the hot emission in the active region core are consistent with steady heating. We also find, however, that the steady heating model cannot address the emission observed at lower temperatures. This emission may be due to foreground or background structures, or may indicate that the heating in the core is more complicated. Different heating scenarios must be tested to determine if they have the same level of agreement.

  16. Modeling and Field Test Planning Activities in Support of Disposal of Heat-Generating Waste in Salt

    SciTech Connect (OSTI)

    Rutqvist, Jonny; Blanco Martin, Laura; Mukhopadhyay, Sumit; Houseworth, Jim; Birkholzer, Jens

    2014-09-26T23:59:59.000Z

    The modeling efforts in support of the field test planning conducted at LBNL leverage on recent developments of tools for modeling coupled thermal-hydrological-mechanical-chemical (THMC) processes in salt and their effect on brine migration at high temperatures. This work includes development related to, and implementation of, essential capabilities, as well as testing the model against relevant information and published experimental data related to the fate and transport of water. These are modeling capabilities that will be suitable for assisting in the design of field experiment, especially related to multiphase flow processes coupled with mechanical deformations, at high temperature. In this report, we first examine previous generic repository modeling results, focusing on the first 20 years to investigate the expected evolution of the different processes that could be monitored in a full-scale heater experiment, and then present new results from ongoing modeling of the Thermal Simulation for Drift Emplacement (TSDE) experiment, a heater experiment on the in-drift emplacement concept at the Asse Mine, Germany, and provide an update on the ongoing model developments for modeling brine migration. LBNL also supported field test planning activities via contributions to and technical review of framework documents and test plans, as well as participation in workshops associated with field test planning.

  17. Loch Linnhe `94: Test operations description and on-site analysis, US activities

    SciTech Connect (OSTI)

    Mantrom, D.D.

    1994-11-01T23:59:59.000Z

    A field experiment named Loch Linnhe `94 (LL94) is described. This experiment was conducted in upper Loch Linnhe, Scotland, in September 1994, as an exercise involving UK and US investigators, under the Joint UK/US Radar Ocean Imaging Program. This experiment involved a dual-frequency, dual-polarization hillside real aperture radar operated by the UK, Lawrence Livermore National Laboratory`s (LLNL) current meter array (CMA), in-water hydrodynamic sensors, and meteorological measurements. The primary measurements involved imaging ship-generated and ambient internal waves by the radar and the CMA. This report documents test operations from a US perspective and presents on-site analysis results derived by US investigators. The rationale underlying complementary radar and CMA measurements is described. Descriptions of the test site, platforms, and major US instrument systems are given. A summary of test operations and examples of radar, CMA, water column profile, and meteorological data are provided. A description of the rather extensive analysis of these data performed at the LL94 test site is presented. The products of this analysis are presented and some implications for further analysis and future experiments are discussed. All experimental objectives were either fully or partially met. Powerful on-site analysis capabilities generated many useful products and helped improve subsequent data collection. Significant further data analysis is planned.

  18. Development and results of experimental testing of electromembrane process for liquid active waste purification

    SciTech Connect (OSTI)

    Martinov, B.V.; Smirnov, V.V.; Tugolukov, B.B.; Belyakov, Y.A. [A.A. Bochvar All Russian Scientific Research, Moscow (Russian Federation). Inst. of Inorganic Materials

    1993-12-31T23:59:59.000Z

    This paper discusses the results of studies on electromembrane purification. The concentration of salts in active wastes arising from decontamination is more than 3--5 g/l. For these investigations a solution was chosen that had arisen from the decontamination of metallic items by a two-bath method using permanganate-alkali in the first stage and nitrogen oxalic acid in the second stage. The total salt content of mixed acid and alkaline solutions was 3.0 g/l, with a pH of 8.5 and total beta-activity of 6 {times} 10{sup {minus}8} Ci/l.

  19. INL Active Interrogation Testing In Support of the GNEP Safeguards Campaign

    SciTech Connect (OSTI)

    David L. Chichester

    2008-04-01T23:59:59.000Z

    Active interrogation, a measurement technique which uses a radiation source to probe materials and generate unique signatures useful for characterizing those materials, is a powerful tool for assaying special nuclear material. Work at Idaho National Laboratory (INL) in the area of active interrogation, using neutron and photon sources, has been under way for many years to develop methods for detecting and quantifying nuclear material for national and homeland security research areas. This research knowledge base is now being extended to address nuclear safeguards and process monitoring issues related to the Global Nuclear Energy Partnership (GNEP). As a first step in this area preliminary scoping studies have been performed to investigate the usefulness of using active neutron interrogation, with a low-power electronic neutron generator, to assay Department of Transportation 6M shipping drums containing uranium oxide fuel rodlets from INL’s zero power physics reactor. Using the paired-counting technique during the die-away time period of interrogation, a lower detection limit of approximately 4.2 grams of enriched uranium (40% 235U) was calculated for a 40 minute measurement using a field portable 2.5 MeV neutron source and an array of 16 moderated helium-3 neutron tubes. Future work in this area, including the use of a more powerful neutron source and a better tailored detector array, would likely improve this limit to a much lower level. Further development work at INL will explore the applicability of active interrogation in association with the nuclear safeguards and process monitoring needs of the advanced GNEP facilities under consideration. This work, which will include both analyses and field demonstrations, will be performed in collaboration with colleagues at INL and elsewhere that have expertise in nuclear fuel reprocessing as well as active interrogation and its use for nuclear material analyses.

  20. Further Charpy impact test results of low activation ferritic alloys, irradiated at 430{degrees}C to 67 dpa

    SciTech Connect (OSTI)

    Schubert, L.E.; Hamilton, M.L.; Gelles, D.S. [Pacific Northwest National Lab., Richland, WA (United States)

    1997-04-01T23:59:59.000Z

    Miniature CVN specimens of four ferritic alloys, GA3X, F82H, GA4X and HT9, have been impact tested following irradiation at 430{degrees}C to 67 dpa. Comparison of the results with those of the previously tested lower dose irradiation condition indicates that the GA3X and F82H alloys, two primary candidate low activation alloys, exhibit virtually identical behavior following irradiation at 430{degrees}C to {approximately}67 dpa and at 370{degrees}C to {approximately}15 dpa. Very little shift is observed in either DBTT or USE relative to the unirradiated condition. The shifts in DBTT and USE observed in both GA4X and HT9 were smaller after irradiation at 430{degrees}C to {approximately}67 dpa than after irradiation at 370{degrees}C to {approximately}15 dpa.

  1. Testing Oxygen Reduction Reaction Activity with the Rotating Disc Electrode Technique

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOriginEducationVideoStrategic| DepartmentDepartment ofTankTest Site SwedenEnergy

  2. Testing an Active Diesel Particulate Filter on a 2-Cycle Marine Engine |

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOriginEducationVideoStrategic| DepartmentDepartment ofTankTest Site2009 DOE Hydrogen Program

  3. Charpy impact test results of four low activation ferritic alloys irradiated at 370{degrees}C to 15 DPA

    SciTech Connect (OSTI)

    Schubert, L.E.; Hamilton, M.L.; Gelles, D.S. [Pacific Northwest National Lab., Richland, WA (United States)

    1996-10-01T23:59:59.000Z

    Miniature CVN specimens of four low activation ferritic alloys have been impact tested following irradiation at 370{degrees}C to 15 dpa. Comparison of the results with those of control specimens indicates that degradation in the impact behavior occurs in each of these four alloys. The 9Cr-2W alloy referred to as GA3X and the similar alloy F82H with 7.8Cr-2W appear most promising for further consideration as candidate structural materials in fusion energy system applications. These two alloys exhibit a small DBTT shift to higher temperatures but show increased absorbed energy on the upper shelf.

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

    SciTech Connect (OSTI)

    B.D. Estes

    2009-04-24T23:59:59.000Z

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

  5. Standard Test Method for Oxygen Content Using a 14-MeV Neutron Activation and Direct-Counting Technique

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2007-01-01T23:59:59.000Z

    1.1 This test method covers the measurement of oxygen concentration in almost any matrix by using a 14-MeV neutron activation and direct-counting technique. Essentially, the same system may be used to determine oxygen concentrations ranging from over 50 % to about 10 g/g, or less, depending on the sample size and available 14-MeV neutron fluence rates. Note 1 - The range of analysis may be extended by using higher neutron fluence rates, larger samples, and higher counting efficiency detectors. 1.2 This test method may be used on either solid or liquid samples, provided that they can be made to conform in size, shape, and macroscopic density during irradiation and counting to a standard sample of known oxygen content. Several variants of this method have been described in the technical literature. A monograph is available which provides a comprehensive description of the principles of activation analysis using a neutron generator (1). 1.3 The values stated in either SI or inch-pound units are to be regarded...

  6. Testing and Commissioning of a Multifunctional Tool for the Dismantling of the Activated Internals of the KNK Reactor Shaft - 13524

    SciTech Connect (OSTI)

    Rothschmitt, Stefan; Graf, Anja [WAK Rueckbau- und Entsorgungs- GmbH, P.O.Box 12 63, 76339 Eggenstein-Leopoldshafen (Germany)] [WAK Rueckbau- und Entsorgungs- GmbH, P.O.Box 12 63, 76339 Eggenstein-Leopoldshafen (Germany); Bauer, Stefan; Klute, Stefan; Koselowski, Eiko [Siempelkamp Nukleartechnik GmbH, Am Taubenfeld 25/1, 69123 Heidelberg (Germany)] [Siempelkamp Nukleartechnik GmbH, Am Taubenfeld 25/1, 69123 Heidelberg (Germany); Hendrich, Klaus [Ingenieurbuero Hendrich, Moerikeweg 14, 75015 Bretten (Germany)] [Ingenieurbuero Hendrich, Moerikeweg 14, 75015 Bretten (Germany)

    2013-07-01T23:59:59.000Z

    The Compact Sodium Cooled Reactor Facility Karlsruhe (KNK), a prototype reactor to demonstrate the Fast Breeder Reactor Technology in Germany, was in operation from 1971 to 1991. The dismantling activities started in 1991. The project aim is the green field in 2020. Most of the reactor internals as well as the primary and secondary cooling loops are already dismantled. The total contaminated sodium inventory has already been disposed of. Only the high activated reactor vessel shielding structures are remaining. Due to the high dose rates these structures must be dismantled remotely. For the dismantling of the primary shielding of the reactor vessel, 12 stacked cast iron blocks with a total mass of 90 Mg and single masses up to 15.5 Mg, a remote-controlled multifunctional dismantling device (HWZ) was designed, manufactured and tested in a mock-up. After successful approval of the test sequences by the authorities, the HWZ was implemented into the reactor building containment for final assembling of the auxiliary equipment and subsequent hot commissioning in 2012. Dismantling of the primary shielding blocks is scheduled for early 2013. (authors)

  7. Activation of p115-RhoGEF Requires Direct Association of G[alpha subscript 13] and the Dbl Homology Domain

    SciTech Connect (OSTI)

    Chen, Zhe; Guo, Liang; Hadas, Jana; Gutowski, Stephen; Sprang, Stephen R.; Sternweis, Paul C. (IIT); (UTSMC); (Montana)

    2012-09-05T23:59:59.000Z

    RGS-containing RhoGEFs (RGS-RhoGEFs) represent a direct link between the G{sub 12} class of heterotrimeric G proteins and the monomeric GTPases. In addition to the canonical Dbl homology (DH) and pleckstrin homology domains that carry out the guanine nucleotide exchange factor (GEF) activity toward RhoA, these RhoGEFs also possess RGS homology (RH) domains that interact with activated {alpha} subunits of G{sub 12} and G{sub 13}. Although the GEF activity of p115-RhoGEF (p115), an RGS-RhoGEF, can be stimulated by G{alpha}{sub 13}, the exact mechanism of the stimulation has remained unclear. Using combined studies with small angle x-ray scattering, biochemistry, and mutagenesis, we identify an additional binding site for activated G{alpha}{sub 13} in the DH domain of p115. Small angle x-ray scattering reveals that the helical domain of G{alpha}{sub 13} docks onto the DH domain, opposite to the surface of DH that binds RhoA. Mutation of a single tryptophan residue in the {alpha}3b helix of DH reduces binding to activated G{alpha}{sub 13} and ablates the stimulation of p115 by G{alpha}{sub 13}. Complementary mutations at the predicted DH-binding site in the {alpha}B-{alpha}C loop of the helical domain of G{alpha}{sub 13} also affect stimulation of p115 by G{alpha}{sub 13}. Although the GAP activity of p115 is not required for stimulation by G{alpha}{sub 13}, two hydrophobic motifs in RH outside of the consensus RGS box are critical for this process. Therefore, the binding of G{alpha}{sub 13} to the RH domain facilitates direct association of G{alpha}{sub 13} to the DH domain to regulate its exchange activity. This study provides new insight into the mechanism of regulation of the RGS-RhoGEF and broadens our understanding of G protein signaling.

  8. Active dc filter for HVDC system--A test installation in the Konti-Skan DC link at Lindome converter station

    SciTech Connect (OSTI)

    Zhang, Wenyan; Asplund, G. (ABB Power Systems, Ludvika (Sweden). HVDC Division); Aberg, A. (ABB Corporate Research, Lund (Sweden). Dept. of Man-Machine Communication); Jonsson, U. (Svenska Kraftnaet, Vaellingby (Sweden)); Loeoef, O. (Vattenfall AB, Trollhaettan (Sweden). Region Vaestsverige)

    1993-07-01T23:59:59.000Z

    The purpose of introducing active dc filters is to meet the more and more stringent requirement from power utilities on limiting telephone interference caused by harmonic currents from HVdc transmission lines, without unnecessarily increasing the cost of HVdc stations. An active dc filter installed in the Konti-Skan HVdc link is described. The active dc filter is connected at the bottom of an existing passive dc filter at the Lindome station. The active dc filter includes optic harmonic current measuring unit, control system, protection and supervision system, PWM power amplifier, high-frequency transformer, surge arrester, and coupling apparatuses. The active dc filter has small physical size and occupies small ground area. The performance of the active dc filter for eliminating the disturbing harmonics is excellent. To achieve comparable results by passive filters would require something like ten times more high voltage equipment.

  9. Breathing air trailer acceptance test report

    SciTech Connect (OSTI)

    Kostelnik, A.J.

    1996-02-12T23:59:59.000Z

    This Acceptance Test Report documents compliance with the requirements of specification WHC-S-0251, Rev.0 and ECNs 613530 and 606113. The equipment was tested according to WHC-SD-WM-ATP-104. The equipment tested is a Breathing Air Supply Trailer purchased as a design and fabrication procurement activity. The ATP was written by the Seller and was performed by the Seller with representatives of the Westinghouse Hanford Company witnessing portions of the test at the Seller`s location.

  10. Test Plan for Field Experiments to Support the Immobilized Low-Activity Waste Disposal Performance Assessment at the Hanford Site

    SciTech Connect (OSTI)

    Meyer, Philip D.; McGrail, B. Peter; Bacon, Diana H.

    2001-09-01T23:59:59.000Z

    Much of the data collected to support the Immobilized Low-Activity Waste Performance Assessment (ILAW PA) simulations have been obtained in the laboratory on a relatively small scale (less than 10 cm). In addition, the PA simulations themselves are currently the only means available to integrate the chemical and hydrologic processes involved in the transport of contaminants from the disposal facility into the environment. This report describes the test plan for field experiments to provide data on the hydraulic, transport, and geochemical characteristics of the near-field materials on a more representative (i.e., larger) scale than the laboratory data currently available. The experiments will also provide results that encompass a variety of transport processes likely to occur within the actual disposal facility. These experiments will thus provide the first integrated data on the ILAW facility performance and will provide a crucial dataset to evaluate the simulation-based estimates of overall facility performance used in the PA.

  11. Intrusion detection sensor testing tools

    SciTech Connect (OSTI)

    Hayward, D.R.

    1994-08-01T23:59:59.000Z

    Intrusion detection sensors must be frequently tested to verify that they are operational, and they must be periodically tested to verify that they are functioning at required performance levels. Concerns involving this testing can include: The significant amount of manpower required, inconsistent results due to variability in methods and personnel, exposure of personnel to hazardous environments, and difficulty in obtaining access to the areas containing some of the intrusion sensors. To address these concerns, the Department of Energy directed Sandia National Labs. to develop intrusion detection sensor testing tools. Over the past two years Sandia has developed several sensor testing tool prototypes. This paper describes the evolution of an exterior intrusion detection sensor tester and automatic data logger, and also describes various interior intrusion detection sensor test fixtures that can be remotely activated to simulate an intruder.

  12. Promulgating Nuclear Safety Requirements

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

    1996-05-15T23:59:59.000Z

    Applies to all Nuclear Safety Requirements Adopted by the Department to Govern the Conduct of its Nuclear Activities. Cancels DOE P 410.1. Canceled by DOE N 251.85.

  13. Verification Testing Test Driven Development Testing with JUnit Verification

    E-Print Network [OSTI]

    Peters, Dennis

    Verification Testing Test Driven Development Testing with JUnit Verification Any activity should be verified. #12;Verification Testing Test Driven Development Testing with JUnit Approaches to verification 1 Testing 2 Static Analysis · Peer review · Insepction/Walk-through/Structured review · Formal

  14. Field Test and Performance Verification: Integrated Active Desiccant Rooftop Hybrid System Installed in a School - Final Report: Phase 4A

    SciTech Connect (OSTI)

    Fischer, J

    2005-12-21T23:59:59.000Z

    This report summarizes the results of a field verification pilot site investigation that involved the installation of a hybrid integrated active desiccant/vapor-compression rooftop heating, ventilation, and air-conditioning (HVAC) unit at an elementary school in the Atlanta Georgia area. For years, the school had experienced serious humidity and indoor air quality (IAQ) problems that had resulted in occupant complaints and microbial (mold) remediation. The outdoor air louvers of the original HVAC units had been closed in an attempt to improve humidity control within the space. The existing vapor compression variable air volume system was replaced by the integrated active desiccant rooftop (IADR) system that was described in detail in an Oak Ridge National Laboratory (ORNL) report published in 2004 (Fischer and Sand 2004). The IADR system and all space conditions have been monitored remotely for more than a year. The hybrid system was able to maintain both the space temperature and humidity as desired while delivering the outdoor air ventilation rate required by American Society of Heating, Refrigerating and Air-Conditioning Engineers Standard 62. The performance level of the IADR unit and the overall system energy efficiency was measured and found to be very high. A comprehensive IAQ investigation was completed by the Georgia Tech Research Institute before and after the system retrofit. Before-and-after data resulting from this investigation confirmed a significant improvement in IAQ, humidity control, and occupant comfort. These observations were reported by building occupants and are echoed in a letter to ORNL from the school district energy manager. The IADR system was easily retrofitted in place of the original rooftop system using a custom curb adapter. All work was completed in-house by the school's maintenance staff over one weekend. A subsequent cost analysis completed for the school district by the design engineer of record concluded that the IADR system being investigated was actually less expensive to install than other less-efficient options, most of which were unable to deliver the required ventilation while maintaining the desired space humidity levels.

  15. LABORATORY OPTIMIZATION TESTS OF TECHNETIUM DECONTAMINATION OF HANFORD WASTE TREATMENT PLANT LOW ACTIVITY WASTE OFF-GAS CONDENSATE SIMULANT

    SciTech Connect (OSTI)

    Taylor-Pashow, K.; Nash, C.; McCabe, D.

    2014-09-29T23:59:59.000Z

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of glass waste. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task examines the potential treatment of this stream to remove radionuclides and subsequently disposition the decontaminated stream elsewhere, such as the Effluent Treatment Facility (ETF), for example. The treatment process envisioned is very similar to that used for the Actinide Removal Process (ARP) that has been operating for years at the Savannah River Site (SRS), and focuses on using mature radionuclide removal technologies that are also compatible with longterm tank storage and immobilization methods. For this new application, testing is needed to demonstrate acceptable treatment sorbents and precipitating agents and measure decontamination factors for additional radionuclides in this unique waste stream. The origin of this LAW Off-Gas Condensate stream will be the liquids from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover. The soluble components are expected to be mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet and will not be available until the WTP begins operation, but a simulant has been produced based on models, calculations, and comparison with pilot-scale tests. One of the radionuclides that is volatile and expected to be in greatest abundance in this LAW Off-Gas Condensate stream is Technetium-99 ({sup 99}Tc). Technetium will not be removed from the aqueous waste in the Hanford WTP, and will primarily end up immobilized in the LAW glass by repeated recycle of the off-gas condensate into the LAW melter. Other radionuclides that are low but are also expected to be in measurable concentration in the LAW Off-Gas Condensate are {sup 129}I, {sup 90}Sr, {sup 137}Cs, {sup 241}Pu, and {sup 241}Am. These are present due to their partial volatility and some entrainment in the off-gas system. This report discusses results of optimized {sup 99}Tc decontamination testing of the simulant. Testing examined use of inorganic reducing agents for {sup 99}Tc. Testing focused on minimizing the quantity of sorbents/reactants added, and minimizing mixing time to reach the decontamination targets in this simulant formulation. Stannous chloride and ferrous sulfate were tested as reducing agents to determine the minimum needed to convert soluble pertechnetate to the insoluble technetium dioxide. The reducing agents were tried with and without sorbents.

  16. A Proposed Framework For Planning Deactivation And Decommissioning Engineering And Design Activities To Meet The Requirements Of DOE Order 413.3A, Program And Project Management For The Acquisition Of Capital Assets

    SciTech Connect (OSTI)

    Santos, J.K.; Gladden, J.B. [Savannah River National Laboratory (SRNL), Savannah River Site, Aiken, SC (United States); Szilagyi, A.P. [United States Department of Energy (DOE), Washington, DC (United States); Negin, C.; Urland, C. [Project Enhancement Corporation, Germantown, MD (United States)

    2008-07-01T23:59:59.000Z

    This paper applies the DOE O 413.3A Design/Engineering requirements to Deactivation and Decommissioning (D and D) projects. A list of 41 activities for which Design/Engineering is generally required and which are relevant and common to many D and D projects was generated. For several activities in this list, examples of the level of development and/or types of deliverables that might be expected at the completion of the conceptual, preliminary and final project design phases described in the Order are provided. This paper also discusses tailoring the application of the Order to a facility based on the complexity of the facility's engineered systems and the hazards existing in the facility. DOE D and D projects are expected to meet the requirements of DOE O 413.3A. For D and D engineering and design activities only, this paper provides guidance for applying these requirements to the Order. A list of 41 typical D and D engineering and design activities has been provided. The Order divides projects into conceptual, preliminary and final design phases. Development of each of the 41 activities can also be organized in conceptual, preliminary and final levels. In general, at the conceptual level project engineers should be determining the what (i.e., the scope) for each activity. At the preliminary level they should be resolving how the activity will be accomplished. At the final level, all the engineering and design details for the activity should be completed so that the activity is ready to implement in the field. It may not be appropriate that development of each individual activity correspond to the current phase of the project. For example, at CD-2 (end of the preliminary design phase) not all activities need be developed to the same level of detail. Only those that are truly significant to the project baseline must be developed to the level of detail necessary to create a reliable project baseline. (authors)

  17. Development And Initial Testing Of Off-Gas Recycle Liquid From The WTP Low Activity Waste Vitrification Process - 14333

    SciTech Connect (OSTI)

    McCabe, Daniel J.; Wilmarth, William R.; Nash, Charles A.; Taylor-Pashow, Kathryn M.; Adamson, Duane J.; Crawford, Charles L.; Morse, Megan M.

    2014-01-07T23:59:59.000Z

    The Waste Treatment and Immobilization Plant (WTP) process flow was designed to pre-treat feed from the Hanford tank farms, separate it into a High Level Waste (HLW) and Low Activity Waste (LAW) fraction and vitrify each fraction in separate facilities. Vitrification of the waste generates an aqueous condensate stream from the off-gas processes. This stream originates from two off-gas treatment unit operations, the Submerged Bed Scrubber (SBS) and the Wet Electrospray Precipitator (WESP). Currently, the baseline plan for disposition of the stream from the LAW melter is to recycle it to the Pretreatment facility where it gets evaporated and processed into the LAW melter again. If the Pretreatment facility is not available, the baseline disposition pathway is not viable. Additionally, some components in the stream are volatile at melter temperatures, thereby accumulating to high concentrations in the scrubbed stream. It would be highly beneficial to divert this stream to an alternate disposition path to alleviate the close-coupled operation of the LAW vitrification and Pretreatment facilities, and to improve long-term throughput and efficiency of the WTP system. In order to determine an alternate disposition path for the LAW SBS/WESP Recycle stream, a range of options are being studied. A simulant of the LAW Off-Gas Condensate was developed, based on the projected composition of this stream, and comparison with pilot-scale testing. The primary radionuclide that vaporizes and accumulates in the stream is Tc-99, but small amounts of several other radionuclides are also projected to be present in this stream. The processes being investigated for managing this stream includes evaporation and radionuclide removal via precipitation and adsorption. During evaporation, it is of interest to investigate the formation of insoluble solids to avoid scaling and plugging of equipment. Key parameters for radionuclide removal include identifying effective precipitation or ion adsorption chemicals, solid-liquid separation methods, and achievable decontamination factors. Results of the radionuclide removal testing indicate that the radionuclides, including Tc-99, can be removed with inorganic sorbents and precipitating agents. Evaporation test results indicate that the simulant can be evaporated to fairly high concentration prior to formation of appreciable solids, but corrosion has not yet been examined.

  18. Test procedure for boxed waste assay system

    SciTech Connect (OSTI)

    Wachter, J. [Los Alamos National Lab., NM (United States)

    1994-12-07T23:59:59.000Z

    This document, prepared by Los Alamos National Laboratory`s NMT-4 group, details the test methodology and requirements for Acceptance/Qualification testing of a Boxed Waste Assay System (BWAS) designed and constructed by Pajarito Scientific Corporation. Testing of the BWAS at the Plutonium Facility (TA55) at Los Alamos National Laboratory will be performed to ascertain system adherence to procurement specification requirements. The test program shall include demonstration of conveyor handling capabilities, gamma ray energy analysis, and imaging passive/active neutron accuracy and sensitivity. Integral to these functions is the system`s embedded operating and data reduction software.

  19. Test quality

    SciTech Connect (OSTI)

    Hartley, R.S. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Keller, A.E. [Nuclear Regulatory Commission, Washington, DC (United States)

    1992-09-01T23:59:59.000Z

    This document discusses inservice testing of safety-related components at nuclear power plants which is performed under the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (the Code). Subsections IWP and IWV of Section XI of the Code state test method and frequency requirements for pumps and valves respectively. Tests vary greatly in quality and frequency. This paper explores the concept of test quality and its relationship with operational readiness and preventive maintenance. This paper also considers the frequencies of component testing. Test quality is related to a test`s ability to detect degradation that can cause component failure. The quality of the test depends on several factors, including specific parameters measured, system or component conditions, and instrument accuracy. The quality of some currently required tests for check valves, motor-operated valves, and pumps is also discussed. Suggestions are made to improve test quality by measuring different parameters, testing valves under load, and testing positive displacement pumps at high pressure and centrifugal pumps at high flow rate conditions. These suggestions can help to improve the level of assurance of component operational readiness gained from testing.

  20. Environmental Assessment: Geothermal Energy Geopressure Subprogram. Gulf Coast Well Drilling and Testing Activity (Frio, Wilcox, and Tuscaloosa Formations, Texas and Louisiana)

    SciTech Connect (OSTI)

    None

    1981-09-01T23:59:59.000Z

    The Department of Energy (DOE) has initiated a program to evaluate the feasibility of developing the geothermal-geopressured energy resources of the Louisiana-Texas Gulf Coast. As part of this effort, DOE is contracting for the drilling of design wells to define the nature and extent of the geopressure resource. At each of several sites, one deep well (4000-6400 m) will be drilled and flow tested. One or more shallow wells will also be drilled to dispose of geopressured brines. Each site will require about 2 ha (5 acres) of land. Construction and initial flow testing will take approximately one year. If initial flow testing is successful, a continuous one-year duration flow test will take place at a rate of up to 6400 m{sup 3} (40,000 bbl) per day. Extensive tests will be conducted on the physical and chemical composition of the fluids, on their temperature and flow rate, on fluid disposal techniques, and on the reliability and performance of equipment. Each project will require a maximum of three years to complete drilling, testing, and site restoration.

  1. Test quality

    SciTech Connect (OSTI)

    Hartley, R.S. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Keller, A.E. (Nuclear Regulatory Commission, Washington, DC (United States))

    1992-01-01T23:59:59.000Z

    This document discusses inservice testing of safety-related components at nuclear power plants which is performed under the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (the Code). Subsections IWP and IWV of Section XI of the Code state test method and frequency requirements for pumps and valves respectively. Tests vary greatly in quality and frequency. This paper explores the concept of test quality and its relationship with operational readiness and preventive maintenance. This paper also considers the frequencies of component testing. Test quality is related to a test's ability to detect degradation that can cause component failure. The quality of the test depends on several factors, including specific parameters measured, system or component conditions, and instrument accuracy. The quality of some currently required tests for check valves, motor-operated valves, and pumps is also discussed. Suggestions are made to improve test quality by measuring different parameters, testing valves under load, and testing positive displacement pumps at high pressure and centrifugal pumps at high flow rate conditions. These suggestions can help to improve the level of assurance of component operational readiness gained from testing.

  2. YUCCA Mountain Project - Argonne National Laboratory, Annual Progress Report, FY 1997 for activity WP 1221 unsaturated drip condition testing of spent fuel and unsaturated dissolution tests of glass.

    SciTech Connect (OSTI)

    Bates, J. K.; Buck, E. C.; Emery, J. W.; Finch, R. J.; Finn, P. A.; Fortner, J.; Hoh, J. C.; Mertz, C.; Neimark, L. A.; Wolf, S. F.; Wronkiewicz, D. J.

    1998-09-18T23:59:59.000Z

    This document reports on the work done by the Nuclear Waste Management Section of the Chemical Technology Division of Argonne National Laboratory in the period of October 1996 through September 1997. Studies have been performed to evaluate the behavior of nuclear waste glass and spent fuel samples under the unsaturated conditions (low-volume water contact) that are likely to exist in the Yucca Mountain environment being considered as a potential site for a high-level waste repository. Tests with actinide-doped waste glasses, in progress for over 11 years, indicate that the transuranic element release is dominated by colloids that continuously form and span from the glass surface. The nature of the colloids that form in the glass and spent fuel testing programs is being investigated by dynamic light scattering to determine the size distribution, by autoradiography to determine the chemistry, and by zeta potential to measure the electrical properties of the colloids. Tests with UO{sub 2} have been ongoing for 12 years. They show that the oxidation of UO{sub 2} occurs rapidly, and the resulting paragenetic sequence of secondary phases forming on the sample surface is similar to that observed for uranium found in natural oxidizing environments. The reaction of spent fuel samples in conditions similar to those used with UO{sub 2} have been in progress for over six years, and the results suggest that spent fuel forms many of the same alteration products as UO{sub 2}. With spent fuel, the bulk of the reaction occurs via a through-grain reaction process, although grain boundary attack is sufficient to have reacted all of the grain boundary regions in the samples. New test methods are under development to evaluate the behavior of spent fuel samples with intact cladding: the rate at which alteration and radionuclide release occurs when water penetrates fuel sections and whether the reaction causes the cladding to split. Alteration phases have been formed on fine grains of UO{sub 2} in contact with small volumes of water within a several month period when the radiolysis product H{sub 2}O{sub 2} is added to the groundwater solution. The test setup has been mocked up for operation with spent fuel in the hot-cell.

  3. Laboratory Scoping Tests Of Decontamination Of Hanford Waste Treatment Plant Low Activity Waste Off-Gas Condensate Simulant

    SciTech Connect (OSTI)

    Taylor-Pashow, Kathryn M.; Nash, Charles A.; Crawford, Charles L.; McCabe, Daniel J.; Wilmarth, William R.

    2014-01-21T23:59:59.000Z

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of glass waste. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task seeks to examine the potential treatment of this stream to remove radionuclides and subsequently disposition the decontaminated stream elsewhere, such as the Effluent Treatment Facility (ETF), for example. The treatment process envisioned is very similar to that used for the Actinide Removal Process (ARP) that has been operating for years at the Savannah River Site (SRS), and focuses on using mature radionuclide removal technologies that are also compatible with longterm tank storage and immobilization methods. For this new application, testing is needed to demonstrate acceptable treatment sorbents and precipitating agents and measure decontamination factors for additional radionuclides in this unique waste stream. The origin of this LAW Off-Gas Condensate stream will be the liquids from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover. The soluble components are expected to be mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet and will not be available until the WTP begins operation, but a simulant has been produced based on models, calculations, and comparison with pilot-scale tests. One of the radionuclides that is volatile and expected to be in high concentration in this LAW Off-Gas Condensate stream is Technetium-99 ({sup 99}Tc). Technetium will not be removed from the aqueous waste in the Hanford WTP, and will primarily end up immobilized in the LAW glass by repeated recycle of the off-gas condensate into the LAW melter. Other radionuclides that are also expected to be in appreciable concentration in the LAW Off-Gas Condensate are {sup 129}I, {sup 90}Sr, {sup 137}Cs, and {sup 241}Am. This report discusses results of preliminary radionuclide decontamination testing of the simulant. Testing examined use of Monosodium Titanate (MST) to remove {sup 90}Sr and actinides, inorganic reducing agents for {sup 99}Tc, and zeolites for {sup 137}Cs. Test results indicate that excellent removal of {sup 99}Tc was achieved using Sn(II)Cl{sub 2} as a reductant, coupled with sorption onto hydroxyapatite, even in the presence of air and at room temperature. This process was very effective at neutral pH, with a Decontamination Factor (DF) >577 in two hours. It was less effective at alkaline pH. Conversely, removal of the cesium was more effective at alka

  4. The Resonating Arm Exerciser: design and pilot testing of a mechanically passive rehabilitation device that mimics robotic active assistance

    E-Print Network [OSTI]

    Zondervan, Daniel K; Palafox, Lorena; Hernandez, Jorge; Reinkensmeyer, David J

    2013-01-01T23:59:59.000Z

    device that mimics robotic active assistance Daniel K1,3 Abstract Background: Robotic arm therapy devices thatin the development of robotic and computer-based devices for

  5. Cage assembly of DegP protease is not required for substrate-dependent regulation of proteolytic activity or high-temperature cell survival

    E-Print Network [OSTI]

    Kim, Seokhee

    DegP, a member of the highly conserved HtrA family, performs quality-control degradation of misfolded proteins in the periplasm of Gram-negative bacteria and is required for high-temperature survival of Escherichia coli. ...

  6. Test Automation Test Automation

    E-Print Network [OSTI]

    Mousavi, Mohammad

    Test Automation Test Automation Mohammad Mousavi Eindhoven University of Technology, The Netherlands Software Testing 2013 Mousavi: Test Automation #12;Test Automation Outline Test Automation Mousavi: Test Automation #12;Test Automation Why? Challenges of Manual Testing Test-case design: Choosing inputs

  7. Differential requirement for NMDAR activity in SAP97 -mediated regulation of the number and strength of glutamatergic AMPAR-containing synapses

    E-Print Network [OSTI]

    Liu, Mingna

    PSD-95-like, disc-large (DLG) family membrane-associated guanylate kinase proteins (PSD/DLG-MAGUKs) are essential for regulating synaptic AMPA receptor (AMPAR) function and activity-dependent trafficking of AMPARs. Using ...

  8. Estradiol-Induced Object Memory Consolidation in Middle-Aged Female Mice Requires Dorsal Hippocampal Extracellular Signal-Regulated Kinase and Phosphatidylinositol 3-Kinase Activation

    E-Print Network [OSTI]

    Lewis, Michael C.

    We previously demonstrated that dorsal hippocampal extracellular signal-regulated kinase (ERK) activation is necessary for 17?[beta]-estradiol (E2[E subscript 2]) to enhance novel object recognition in young ovariectomized ...

  9. Phased Startup Initiative Phases 3 and 4 Test Plan and Test Specification (OCRWM)

    SciTech Connect (OSTI)

    PITNER, A.L.

    2000-02-28T23:59:59.000Z

    Construction for the Spent Nuclear Fuel (SNF) Project facilities is continuing per the Level III Baseline Schedule, and installation of the Fuel Retrieval System (FRS) and Integrated Water Treatment System (IWTS) in K West Basin is now complete. In order to accelerate the project, a phased start up strategy to initiate testing of the FRS and IWTS early in the overall project schedule was proposed (Williams 1999). Wilkinson (1999) expands the definition of the original proposal into four functional testing phases of the Phased Startup Initiative (PSI). Phases 1 and 2 are based on performing functional tests using dummy fuel. These tests are described in separate planning documents. This test plan provides overall guidance for Phase 3 and 4 tests, which are performed using actual irradiated N fuel assemblies. The overall objective of the Phase 3 and 4 testing is to verify how the FRS and IWTS respond while processing actual fuel. Conducting these tests early in the project schedule will allow identification and resolution of equipment and process problems before they become activities on the start-up critical path. The specific objectives of this test plan are to: (1) Define the test scope for the FRS and IWTS; (2) Provide detailed test requirements that can be used to write the specific test procedures; (3) Define data required and measurements to be taken. Where existing methods to obtain these do not exist, enough detail will be provided to define required additional equipment; and (4) Define specific test objectives and acceptance criteria.

  10. Environmental, Health and Safety Assessment: ATS 7H Program (Phase 3R) Test Activities at the GE Power Systems Gas Turbine Manufacturing Facility, Greenville, SC

    SciTech Connect (OSTI)

    None

    1998-11-17T23:59:59.000Z

    International Technology Corporation (IT) was contracted by General Electric Company (GE) to assist in the preparation of an Environmental, Health and Safety (HI&3) assessment of the implementation of Phase 3R of the Advanced Turbine System (ATS) 7H program at the GE Gas Turbines facility located in Greenville, South Carolina. The assessment was prepared in accordance with GE's contractual agreement with the U.S. Department of Energy (GE/DOE Cooperative Agreement DE-FC21-95MC3 1176) and supports compliance with the requirements of the National Environmental Policy Act of 1970. This report provides a summary of the EH&S review and includes the following: General description of current site operations and EH&S status, Description of proposed ATS 7H-related activities and discussion of the resulting environmental, health, safety and other impacts to the site and surrounding area. Listing of permits and/or licenses required to comply with federal, state and local regulations for proposed 7H-related activities. Assessment of adequacy of current and required permits, licenses, programs and/or plans.

  11. Open test assembly (OTA) shear demonstration testing work/test plan

    SciTech Connect (OSTI)

    Hiller, S.W.

    1998-07-16T23:59:59.000Z

    This document describes the development testing phase associated with the OTA Shear activity and defines the controls to be in place throughout the testing. The purpose of the OTA Shear Program was to provide equipment that is needed for the processing of 40 foot long, sodium wetted, irradiated core components previously used in the FFTF reactor to monitor fuel and materials tests. There are currently 15 of these OTA test stalks located in the Test Assembly Conditioning Station (TACS) inerted vault. These need to be dispositioned for a shutdown mission to eliminate this highly activated, high dose inventory prior to turnover to the ERC since they must be handled by remote operations. These would also need to be dispositioned for a restart mission to free up the vault they currently reside in. The waste handling and cleaning equipment in the J33M Cell was designed and built for the handling of reactor components up to the standard 12 foot length. This program will provide the equipment to the IEM Cell to remotely section the OTAS into pieces less than 12 feet in length to allow for the necessary handling and cleaning operations required for proper disposition. Due to the complexity of all operations associated with remote handling, the availability of the IEM Cell training facility, and the major difficulty with reworking contaminated equipment, it was determined that preliminary testing of the equipment was desirable, This testing activity would provide the added assurance that the equipment will operate as designed prior to performance of the formal Acceptance Test Procedure (ATP) at the IEM Cell, This testing activity will also allow for some operator familiarity and procedure checkout prior to actual installation into the IEM Cell. This development testing will therefore be performed at the conclusion of equipment fabrication and prior to transfer of the equipment to the 400 Area.

  12. Requirement of T-lymphokine-activated killer cell-originated protein kinase for TRAIL resistance of human HeLa cervical cancer cells

    SciTech Connect (OSTI)

    Kwon, Hyeok-Ran [Department of Biochemistry, College of Medicine, Konyang University, 685 Gasuwon-dong, Seo-gu, Daejeon 302-718 (Korea, Republic of)] [Department of Biochemistry, College of Medicine, Konyang University, 685 Gasuwon-dong, Seo-gu, Daejeon 302-718 (Korea, Republic of); Lee, Ki Won [Department of Bioscience and Biotechnology, Konkuk University, 1 Hwayang-dong, Gwangjin-gu, Seoul 143-701 (Korea, Republic of)] [Department of Bioscience and Biotechnology, Konkuk University, 1 Hwayang-dong, Gwangjin-gu, Seoul 143-701 (Korea, Republic of); Dong, Zigang [Hormel Institute, University of Minnesota, 801 16th Avenue NE, Austin, MN 55912 (United States)] [Hormel Institute, University of Minnesota, 801 16th Avenue NE, Austin, MN 55912 (United States); Lee, Kyung Bok [Department of Biochemistry, College of Medicine, Konyang University, 685 Gasuwon-dong, Seo-gu, Daejeon 302-718 (Korea, Republic of)] [Department of Biochemistry, College of Medicine, Konyang University, 685 Gasuwon-dong, Seo-gu, Daejeon 302-718 (Korea, Republic of); Oh, Sang-Muk, E-mail: sangmuk_oh@konyang.ac.kr [Department of Biochemistry, College of Medicine, Konyang University, 685 Gasuwon-dong, Seo-gu, Daejeon 302-718 (Korea, Republic of)] [Department of Biochemistry, College of Medicine, Konyang University, 685 Gasuwon-dong, Seo-gu, Daejeon 302-718 (Korea, Republic of)

    2010-01-01T23:59:59.000Z

    T-lymphokine-activated killer cell-originated protein kinase (TOPK) appears to be highly expressed in various cancer cells and to play an important role in maintaining proliferation of cancer cells. However, the underlying mechanism by which TOPK regulates growth of cancer cells remains elusive. Here we report that upregulated endogenous TOPK augments resistance of cancer cells to apoptosis induced by tumor necrosis factor-related apoptosis inducing ligand (TRAIL). Stable knocking down of TOPK markedly increased TRAIL-mediated apoptosis of human HeLa cervical cancer cells, as compared with control cells. Caspase 8 or caspase 3 activities in response to TRAIL were greatly incremented in TOPK-depleted cells. Ablation of TOPK negatively regulated TRAIL-mediated NF-{kappa}B activity. Furthermore, expression of NF-{kappa}B-dependent genes, FLICE-inhibitory protein (FLIP), inhibitor of apoptosis protein 1 (c-IAP1), or X-linked inhibitor of apoptosis protein (XIAP) was reduced in TOPK-depleted cells. Collectively, these findings demonstrated that TOPK contributed to TRAIL resistance of cancer cells via NF-{kappa}B activity, suggesting that TOPK might be a potential molecular target for successful cancer therapy using TRAIL.

  13. TEST STATION SALE OF PERFORMANCE TESTED BULLS

    E-Print Network [OSTI]

    Tennessee, University of

    in the test had to meet minimum performance requirements. Those were: CREEP NON-CREEP Adj 205 day wt. 560 520AS-B428 U T BULL TEST STATION SALE OF PERFORMANCE TESTED BULLS THURSDAY, MARCH 8, 2012 12:00 NOON IN GREENEVILLE AND KNOXVILLE LIVESTOCK CENTER http://animalscience.ag.utk.edu/ (For video) #12;UT BULL TEST

  14. Phase Startup Initiative Phases 3 and 4 Test Plan and Test Specification ( OCRWM)

    SciTech Connect (OSTI)

    PAJUNEN, A.L.; LANGEVIN, M.J.

    2000-08-07T23:59:59.000Z

    Construction for the Spent Nuclear Fuel (SNF) Project facilities is continuing per the Level III Baseline Schedule, and installation of the Fuel Retrieval System (FRS) and Integrated Water Treatment System (IWTS) in K West Basin is now complete. In order to accelerate the project, a phased start up strategy to initiate testing of the FRS and IWTS early in the overall project schedule was proposed (Williams 1999). Wilkinson (1999) expands the definition of the original proposal into four functional testing phases of the Phased Startup Initiative (PSI). Phases 1 and 2 are based on performing functional tests using dummy fuel. This test plan provides overall guidance for Phase 3 and 4 tests, which are performed using actual irradiated N fuel assemblies. The overall objective of the Phase 3 and 4 testing is to verify how the FRS and IWTS respond while processing actual fuel. Conducting these tests early in the project schedule will allow identification and resolution of equipment and process problems before they become activities on the start-up critical path. The specific objectives of this test plan are to: Define the Phase 3 and 4 test scope for the FRS and IWTS; Provide detailed test requirements that can be used to write the specific test procedures; Define data required and measurements to be taken. Where existing methods to obtain these do not exist, enough detail will be provided to define required additional equipment; and Define specific test objectives and acceptance criteria.

  15. Recovery Efficiency Test Project: Phase 1, Activity report. Volume 1: Site selection, drill plan preparation, drilling, logging, and coring operations

    SciTech Connect (OSTI)

    Overbey, W.K. Jr.; Carden, R.S.; Kirr, J.N.

    1987-04-01T23:59:59.000Z

    The recovery Efficiency Test well project addressed a number of technical issues. The primary objective was to determine the increased efficiency gas recovery of a long horizontal wellbore over that of a vertical wellbore and, more specifically, what improvements can be expected from inducing multiple hydraulic fractures from such a wellbore. BDM corporation located, planned, and drilled a long radius turn horizontal well in the Devonian shale Lower Huron section in Wayne County, West Virginia, demonstrating that state-of-the-art technology is capable of drilling such wells. BDM successfully tested drilling, coring, and logging in a horizontal well using air as the circulating medium; conducted reservoir modeling studies to protect flow rates and reserves in advance of drilling operations; observed two phase flow conditions in the wellbore not observed previously; cored a fracture zone which produced gas; observed that fractures in the core and the wellbore were not systematically spaced (varied from 5 to 68 feet in different parts of the wellbore); observed that highest gas show rates reported by the mud logger corresponded to zone with lowest fracture spacing (five feet) or high fracture frequency. Four and one-half inch casting was successfully installed in the borehole and was equipped to isolate the horizontal section into eight (8) zones for future testing and stimulation operations. 6 refs., 48 figs., 10 tabs.

  16. Baseline LAW Glass Formulation Testing

    SciTech Connect (OSTI)

    Kruger, Albert A. [USDOE Office of River Protection, Richland, WA (United States); Mooers, Cavin [The Catholic University of America, Washington, DC (United States). Vitreous State Lab.; Bazemore, Gina [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Pegg, Ian L. [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Hight, Kenneth [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Lai, Shan Tao [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Buechele, Andrew [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Rielley, Elizabeth [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Gan, Hao [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Muller, Isabelle S. [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Cecil, Richard [The Catholic University of America, Washington, DC (United States). Vitreous State Lab

    2013-06-13T23:59:59.000Z

    The major objective of the baseline glass formulation work was to develop and select glass formulations that are compliant with contractual and processing requirements for each of the LAW waste streams. Other objectives of the work included preparation and characterization of glasses with respect to the properties of interest, optimization of sulfate loading in the glasses, evaluation of ability to achieve waste loading limits, testing to demonstrate compatibility of glass melts with melter materials of construction, development of glass formulations to support ILAW qualification activities, and identification of glass formulation issues with respect to contract specifications and processing requirements.

  17. Independent Verification and Validation Of SAPHIRE 8 Software Acceptance Test Plan Project Number: N6423 U.S. Nuclear Regulatory Commission

    SciTech Connect (OSTI)

    Kent Norris

    2010-03-01T23:59:59.000Z

    The purpose of the Independent Verification and Validation (IV&V) role in the evaluation of the SAPHIRE 8 Software Acceptance Test Plan is to assess the approach to be taken for intended testing activities. The plan typically identifies the items to be tested, the requirements being tested, the testing to be performed, test schedules, personnel requirements, reporting requirements, evaluation criteria, and any risks requiring contingency planning. The IV&V team began this endeavor after the software engineering and software development of SAPHIRE had already been in production.

  18. Summary of Construction Activities and Results from Six Initial Accelerated Pavement Tests Conducted on Asphalt Concrete Pavement Section for Modified-Binder Overlay

    E-Print Network [OSTI]

    Bejarano, Manuel O.; Morton, Bruce S.; Scheffy, Clark

    2005-01-01T23:59:59.000Z

    Testing on the Asphalt Concrete FWD testing was conducted onin asphalt concrete modulus after HVS testing for Sectionsconcrete pavements under accelerated pavement testing. This

  19. Mineral Requirements of Sheep.

    E-Print Network [OSTI]

    Fraps, G. S. (George Stronach)

    1918-01-01T23:59:59.000Z

    constituents in feed, residues, and excrements were estimated. In connection with other digestion experiments, estimates were made of certain ash constituents in feeds, excrements and urine. The results of this work throw light upon the mineral requirements...,11 grams phosphoric acid. The ratio of lime to phosphoric acid in tri- calcium phosphate is 1 :0.80. Table 7.-Average magnesia eaten and digested. BALANCE EXPEBIMENTS In twenty tests with ten rations, the urine was analyzed in addition to the feeds...

  20. Requirements for GNEP Transmutation Fuels

    SciTech Connect (OSTI)

    D. C. Crawford; M. K. Meyer; S. L. Hayes

    2007-03-01T23:59:59.000Z

    The purpose of this document is to provide a baseline set of requirements to guide fuel fabrication development and irradiation testing performed as part of the AFCRD Transmutation Fuel Development Program. This document can be considered a supplement to the GNEP TRU Fuel Development and Qualification Plan, and will be revised as necessary to maintain a documented set of fuel testing objectives and requirements consistent with programmatic decisions and advances in technical knowledge.

  1. Defect Prevention and Detection in Software for Automated Test Equipment

    SciTech Connect (OSTI)

    E. Bean

    2006-11-30T23:59:59.000Z

    Software for automated test equipment can be tedious and monotonous making it just as error-prone as other software. Active defect prevention and detection are also important for test applications. Incomplete or unclear requirements, a cryptic syntax used for some test applications—especially script-based test sets, variability in syntax or structure, and changing requirements are among the problems encountered in one tester. Such problems are common to all software but can be particularly problematic in test equipment software intended to test another product. Each of these issues increases the probability of error injection during test application development. This report describes a test application development tool designed to address these issues and others for a particular piece of test equipment. By addressing these problems in the development environment, the tool has powerful built-in defect prevention and detection capabilities. Regular expressions are widely used in the development tool as a means of formally defining test equipment requirements for the test application and verifying conformance to those requirements. A novel means of using regular expressions to perform range checking was developed. A reduction in rework and increased productivity are the results. These capabilities are described along with lessons learned and their applicability to other test equipment software. The test application development tool, or “application builder”, is known as the PT3800 AM Creation, Revision and Archiving Tool (PACRAT).

  2. Practical Experiences from the USE of a Method for Active Functional Tests and Optimization of Coil Energy Recovery Loop Systems in AHUs

    E-Print Network [OSTI]

    Eriksson, J.

    2004-01-01T23:59:59.000Z

    PRACTICAL EXPERIENCES FROM THE USE OF A METHOD FOR ACTIVE FUNCTIONAL TESTS AND OPTIMIZATION OF COIL ENERGY RECOVERY LOOP SYSTEMS IN AHUS. J?rgen Eriksson* * ?F-Installation AB, Box 1551 SE 401 51 G?teborg, Sweden. Summary A method...-commissioning, ventilation, energy, efficiency, EES INTRODUCTION The reason to study coil energy recovery loop systems is that they are very common in Sweden and mainly used in cases with high air flow rates such as in hospitals and pharmaceutical industries. The heat...

  3. Test of electron beam technology on Savannah River Laboratory low-activity aqueous waste for destruction of benzene, benzene derivatives, and bacteria

    SciTech Connect (OSTI)

    Dougal, R.A. [Univ. of South Carolina, Columbia, SC (United States). Dept. of Electrical and Computer Engineering

    1993-08-01T23:59:59.000Z

    High energy radiation was studied as a means for destroying hazardous organic chemical wastes. Tests were conducted at bench scale with a {sup 60}Co source, and at full scale (387 l/min) with a 1.5 MV electron beam source. Bench scale tests for both benzene and phenol included 32 permutations of water quality factors. For some water qualities, as much as 99.99% of benzene or 90% of phenol were removed by 775 krads of {sup 60}Co irradiation. Full scale testing for destruction of benzene in a simulated waste-water mix showed loss of 97% of benzene following an 800 krad dose and 88% following a 500 krad dose. At these loss rates, approximately 5 Mrad of electron beam irradiation is required to reduce concentrations from 100 g/l to drinking water quality (5 {mu}g/l). Since many waste streams are also inhabited by bacterial populations which may affect filtering operations, the effect of irradiation on those populations was also studied. {sup 60}Co and electron beam irradiation were both lethal to the bacteria studied at irradiation levels far lower than were necessary to remove organic contaminants.

  4. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

    SciTech Connect (OSTI)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

    2005-07-01T23:59:59.000Z

    This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal.

  5. Mining Test Cases To Improve Software Maintenance

    E-Print Network [OSTI]

    Ziftci, Celal

    Chapter 6 Automatically Mining Requirements Relationships6.4 R EQ R EL E X : Mining Requirements Relationships fromTest Cases . . . . 6.4.1 Mining Requirements

  6. RCRA Part A Permit Application for Waste Management Activities at the Nevada Test Site, Part B Permit Application Hazardous Waste Storage Unit, Nevada Test Site, and Part B Permit Application - Explosives Ordnance Disposal Unit (EODU)

    SciTech Connect (OSTI)

    NSTec Environmental Programs

    2010-06-17T23:59:59.000Z

    The Area 5 Hazardous Waste Storage Unit (HWSU) was established to support testing, research, and remediation activities at the Nevada Test Site (NTS), a large-quantity generator of hazardous waste. The HWSU, located adjacent to the Area 5 Radioactive Waste Management Site (RWMS), is a prefabricated, rigid steel-framed, roofed shelter used to store hazardous nonradioactive waste generated on the NTS. No offsite generated wastes are managed at the HWSU. Waste managed at the HWSU includes the following categories: Flammables/Combustibles; Acid Corrosives; Alkali Corrosives; Oxidizers/Reactives; Toxics/Poisons; and Other Regulated Materials (ORMs). A list of the regulated waste codes accepted for storage at the HWSU is provided in Section B.2. Hazardous wastes stored at the HWSU are stored in U.S. Department of Transportation (DOT) compliant containers, compatible with the stored waste. Waste transfer (between containers) is not allowed at the HWSU and containers remain closed at all times. Containers are stored on secondary containment pallets and the unit is inspected monthly. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational Resource Conservation and Recovery Act (RCRA) units at the NTS and their respective regulatory status.

  7. In-service Inspection Ultrasonic Testing of Reactor Pressure Vessel Welds for Assessing Flaw Density and Size Distribution per 10 CFR 50.61a, Alternate Fracture Toughness Requirements

    SciTech Connect (OSTI)

    Sullivan, Edmund J.; Anderson, Michael T.; Norris, Wallace

    2012-09-17T23:59:59.000Z

    Pressurized thermal shock (PTS) events are system transients in a pressurized water reactor (PWR) in which there is a rapid operating temperature cool-down that results in cold vessel temperatures with or without repressurization of the vessel. The rapid cooling of the inside surface of the reactor pressure vessel (RPV) causes thermal stresses that can combine with stresses caused by high pressure. The aggregate effect of these stresses is an increase in the potential for fracture if a pre-existing flaw is present in a material susceptible to brittle failure. The ferritic, low alloy steel of the reactor vessel beltline adjacent to the core, where neutron radiation gradually embrittles the material over the lifetime of the plant, can be susceptible to brittle fracture. The PTS rule, described in the Code of Federal Regulations, Title 10, Section 50.61 (§50.61), “Fracture Toughness Requirements for Protection against Pressurized Thermal Shock Events,” adopted on July 23, 1985, establishes screening criteria to ensure that the potential for a reactor vessel to fail due to a PTS event is deemed to be acceptably low. The U.S. Nuclear Regulatory Commission (NRC) completed a research program that concluded that the risk of through-wall cracking due to a PTS event is much lower than previously estimated. The NRC subsequently developed a rule, §50.61a, published on January 4, 2010, entitled “Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events” (75 FR 13). Use of the new rule by licensees is optional. The §50.61a rule differs from §50.61 in that it requires licensees who choose to follow this alternate method to analyze the results from periodic volumetric examinations required by the ASME Code, Section XI, Rules for Inservice Inspection (ISI) of Nuclear Power Plants. These analyses are intended to determine if the actual flaw density and size distribution in the licensee’s reactor vessel beltline welds are bounded by the flaw density and size distribution values used in the PTS technical basis. Under a contract with the NRC, Pacific Northwest National Laboratory (PNNL) has been working on a program to assess the ability of current inservice inspection (ISI)-ultrasonic testing (UT) techniques, as qualified through ASME Code, Appendix VIII, Supplements 4 and 6, to detect small fabrication or inservice-induced flaws located in RPV welds and adjacent base materials. As part of this effort, the investigators have pursued an evaluation, based on the available information, of the capability of UT to provide flaw density/distribution inputs for making RPV weld assessments in accordance with §50.61a. This paper presents the results of an evaluation of data from the 1993 Browns Ferry Nuclear Plant, Unit 3, Spirit of Appendix VIII reactor vessel examination, a comparison of the flaw density/distribution from this data with the distribution in §50.61a, possible reasons for differences, and plans and recommendations for further work in this area.

  8. RCRA Part A and Part B Permit Application for Waste Management Activities at the Nevada Test Site: Proposed Mixed Waste Disposal Unit (MWSU)

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2010-07-19T23:59:59.000Z

    The proposed Mixed Waste Storage Unit (MWSU) will be located within the Area 5 Radioactive Waste Management Complex (RWMC). Existing facilities at the RWMC will be used to store low-level mixed waste (LLMW). Storage is required to accommodate offsite-generated LLMW shipped to the Nevada Test Site (NTS) for disposal in the new Mixed Waste Disposal Unit (MWDU) currently in the design/build stage. LLMW generated at the NTS (onsite) is currently stored on the Transuranic (TRU) Pad (TP) in Area 5 under a Mutual Consent Agreement (MCA) with the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). When the proposed MWSU is permitted, the U.S. Department of Energy (DOE) will ask that NDEP revoke the MCA and onsite-generated LLMW will fall under the MWSU permit terms and conditions. The unit will also store polychlorinated biphenyl (PCB) waste and friable and non-friable asbestos waste that meets the acceptance criteria in the Waste Analysis Plan (Exhibit 2) for disposal in the MWDU. In addition to Resource Conservation and Recovery Act (RCRA) requirements, the proposed MWSU will also be subject to Department of Energy (DOE) orders and other applicable state and federal regulations. Table 1 provides the metric conversion factors used in this application. Table 2 provides a list of existing permits. Table 3 lists operational RCRA units at the NTS and their respective regulatory status.

  9. Laboratory and Field Testing of Commercially Available Detectors for the Identification of Chemicals of Interest in the Nuclear Fuel Cycle for the Detection of Undeclared Activities

    SciTech Connect (OSTI)

    Carla Miller; Mary Adamic; Stacey Barker; Barry Siskind; Joe Brady; Warren Stern; Heidi Smartt; Mike McDaniel; Mike Stern; Rollin Lakis

    2014-07-01T23:59:59.000Z

    Traditionally, IAEA inspectors have focused on the detection of nuclear indicators as part of infield inspection activities. The ability to rapidly detect and identify chemical as well as nuclear signatures can increase the ability of IAEA inspectors to detect undeclared activities at a site. Identification of chemical indicators have been limited to use in the analysis of environmental samples. Although IAEA analytical laboratories are highly effective, environmental sample processing does not allow for immediate or real-time results to an IAEA inspector at a facility. During a complementary access inspection, under the Additional Protocol, the use of fieldable technologies that can quickly provide accurate information on chemicals that may be indicative of undeclared activities can increase the ability of IAEA to effectively and efficiently complete their mission. The Complementary Access Working Group (CAWG) is a multi-laboratory team with members from Brookhaven National Laboratory, Idaho National Laboratory, Los Alamos National Laboratory, and Sandia National Laboratory. The team identified chemicals at each stage of the nuclear fuel cycle that may provide IAEA inspectors with indications that proliferation activities may be occurring. The group eliminated all indicators related to equipment, technology and training, developing a list of by-products/effluents, non-nuclear materials, nuclear materials, and other observables. These proliferation indicators were prioritized based on detectability from a conduct of operations (CONOPS) perspective of a CA inspection (for example, whether an inspector actually can access the S&O or whether it is in process with no physical access), and the IAEA’s interest in the detection technology in conjunction with radiation detectors. The list was consolidated to general categories (nuclear materials from a chemical detection technique, inorganic chemicals, organic chemicals, halogens, and miscellaneous materials). The team then identified commercial off the shelf (COTS) chemical detectors that may detect the chemicals of interest. Three chemical detectors were selected and tested both in laboratory settings and in field operations settings at Idaho National Laboratory. The instruments selected are: Thermo Scientific TruDefender FT (FTIR), Thermo Scientific FirstDefender RM (Raman), and Bruker Tracer III SD (XRF). Functional specifications, operability, and chemical detectability, selectivity, and limits of detection were determined. Results from the laboratory and field tests will be presented. This work is supported by the Next Generation Safeguards Initiative, Office of Nonproliferation and International Security, National Nuclear Security Administration.

  10. Supervisory Training Requirements | Department of Energy

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

    Requirements The Office of Learning and Workforce Development has developed an inventory of training and developmental activities that will meet the supervisory training...

  11. Test profiles for stationary energy storage applications

    SciTech Connect (OSTI)

    Butler, P.C. [Sandia National Labs., Albuquerque, NM (United States); Cole, J.F. [International Lead Zinc Research Organization, Research Triangle Park, NC (United States); Taylor, P.A. [Energetics, Inc., Columbia, MD (United States)

    1998-09-01T23:59:59.000Z

    Evaluation of battery and other energy storage technologies for stationary uses is progressing rapidly toward application-specific testing that uses computer-based data acquisition and control equipment, active electronic loads and power supplies, and customized software, to enable sophisticated test regimes that simulate actual use conditions. These simulated-use tests provide more accurate performance and life evaluations than simple constant resistance or current testing regimes. Some of the tests use stepped constant-power charge and discharge regimes to simulate conditions created by electric utility applications such as frequency regulation and spinning reserve. Other test profiles under development simulate conditions for the energy storage component of Remote Area Power Supplies (RAPS) that include renewable and/or fossil-fueled generators. Various RAPS applications have unique sets of service conditions that require specialized test profiles. However, almost all RAPS tests and many tests that represent other stationary applications need to simulate significant time periods during which storage devices operate at low-to-medium states-of-charge without full recharge. Consideration of these and similar issues in simulated-use test regimes is necessary to effectively predict the responses of the various types of batteries in specific stationary applications. This paper describes existing and evolving stationary applications for energy storage technologies and test regimes that are designed to simulate them. The paper also discusses efforts to develop international testing standards.

  12. Graduation Requirements and Procedures Graduation Requirements and

    E-Print Network [OSTI]

    /Degree Audit (DARS) or contact the department offering the major. Graduation Average Requirement The minimum

  13. LEGACY MANAGEMENT REQUIRES INFORMATION

    SciTech Connect (OSTI)

    CONNELL, C.W.; HILDEBRAND, R.D.

    2006-12-14T23:59:59.000Z

    ''Legacy Management Requires Information'' describes the goal(s) of the US Department of Energy's Office of Legacy Management (LM) relative to maintaining critical records and the way those goals are being addressed at Hanford. The paper discusses the current practices for document control, as well as the use of modern databases for both storing and accessing the data to support cleanup decisions. In addition to the information goals of LM, the Hanford Federal Facility Agreement and Consent Order, known as the ''Tri-Party Agreement'' (TPA) is one of the main drivers in documentation and data management. The TPA, which specifies discrete milestones for cleaning up the Hanford Site, is a legally binding agreement among the US Department of Energy (DOE), the Washington State Department of Ecology (Ecology), and the US Environmental Protection Agency (EPA). The TPA requires that DOE provide the lead regulatory agency with the results of analytical laboratory and non-laboratory tests/readings to help guide them in making decisions. The Agreement also calls for each signatory to preserve--for at least ten years after the Agreement has ended--all of the records in its or its contractors, possession related to sampling, analysis, investigations, and monitoring conducted. The tools used at Hanford to meet TPA requirements are also the tools that can satisfy the needs of LM.

  14. Managing System of Systems Requirements with a Requirements Screening Group

    SciTech Connect (OSTI)

    Ronald R. Barden

    2012-07-01T23:59:59.000Z

    Figuring out an effective and efficient way to manage not only your Requirement’s Baseline, but also the development of all your individual requirements during a Program’s/Project’s Conceptual and Development Life Cycle Stages can be both daunting and difficult. This is especially so when you are dealing with a complex and large System of Systems (SoS) Program with potentially thousands and thousands of Top Level Requirements as well as an equal number of lower level System, Subsystem and Configuration Item requirements that need to be managed. This task is made even more overwhelming when you have to add in integration with multiple requirements’ development teams (e.g., Integrated Product Development Teams (IPTs)) and/or numerous System/Subsystem Design Teams. One solution for tackling this difficult activity on a recent large System of Systems Program was to develop and make use of a Requirements Screening Group (RSG). This group is essentially a Team made up of co-chairs from the various Stakeholders with an interest in the Program of record that are enabled and accountable for Requirements Development on the Program/Project. The RSG co-chairs, often with the help of individual support team, work together as a Program Board to monitor, make decisions on, and provide guidance on all Requirements Development activities during the Conceptual and Development Life Cycle Stages of a Program/Project. In addition, the RSG can establish and maintain the Requirements Baseline, monitor and enforce requirements traceability across the entire Program, and work with other elements of the Program/Project to ensure integration and coordination.

  15. RMOTC - Testing - Environmental

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

    oilfield activities and facilities offers opportunities for testing new technologies for environmental protection and restoration in a real-world environment. Examples include pit...

  16. Special Nuclear Material Portal Monitoring at the Nevada Test Site

    SciTech Connect (OSTI)

    DeAnn Long; Michael Murphy

    2008-07-01T23:59:59.000Z

    Prior to April 2007, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program.

  17. DOE Underground-Coal-Conversion-Program field-test activities for 1979 and 1980. [Pricetown 1, Hoe Creek 3, Hanna IV, and SDB 1

    SciTech Connect (OSTI)

    Bartke, T.C.

    1983-08-01T23:59:59.000Z

    Under the US Department of Energy's Underground-Coal-Conversion program, four field tests were completed in 1979 and preparations were begun in 1980 for two additional field tests to be operated in 1981. The Laramie Energy Technology Center (LETC) and Sandia National Laboratories (SNL) completed Hanna IV, an air gasification test in Wyoming subbituminous coal. The Morgantown Energy Technology Center (METC) completed Pricetown 1, an air gasification test in West Virginia bituminous coal. Lawrence Livermore National Laboratory (LLNL) completed Hoe Creek 3, a steam-oxygen gasification test in Wyoming subbituminous coal. Gulf Research and Development Co. completed Steeply Dipping Beds (SDB) Test 1, primarily an air gasification test in Wyoming subbituminous coal and the first SDB test in the US. In 1980, Gulf R and D Co. began preparation of SDB Test 2, scheduled for operation in the fall of 1981. The DOE project teams at LETC, METC, LLNL, and SNL, in association with the Washington Irrigation and Development Co. (WIDCo), Washington Water Power (WWP), and the State of Washington, are preparing a field test site in the Centralia-Chehalis coal district of Washington. A series of large coal block tests will be completed prior to the field test, scheduled for operation in 1982 or 1983. This field test will utilize a directionally drilled link and steam-oxygen gasification system. This paper summarizes the results of the four recently completed field tests and the plans for additional tests.

  18. The selenium-75-homocholic acid taurine test reevaluated: combined measurement of fecal selenium-75 activity and 3 alpha-hydroxy bile acids in 211 patients

    SciTech Connect (OSTI)

    van Tilburg, A.J.; de Rooij, F.W.; van den Berg, J.W.; Kooij, P.P.; van Blankenstein, M. (Department of Internal Medicine II, University Hospital Dijkzigt, Rotterdam (Netherlands))

    1991-06-01T23:59:59.000Z

    The recommended reference values for the selenium-75-homocholic acid taurine (75SeHCAT) test, used in the analysis of chronic diarrhea, were evaluated in 211 patients by comparing simultaneous measurements of 3 alpha-hydroxy bile acids and 75Se activity in daily collected stools. An initial evaluation in 11 patients showed that the fecal collection method, which allows inspection and additional analysis of stools, was equivalent to the abdominal retention method. Selenium-75-HCAT whole-body retention half-life (WBR50) was greater than 2.8 days in less than 10% of the patients with bile acid malabsorption and less than 1.7 days in less than 10% of the normals. We recommend that a 75SeHCAT WBR50 less than 1.7 days is abnormal, a WBR50 greater than 2.8 days is normal, and a WBR50 in the range 1.7-2.8 days is equivocal, which was the case in 48% (94/195) of the patients in this study.

  19. Postirradiation Testing Laboratory (327 Building)

    SciTech Connect (OSTI)

    Kammenzind, D.E.

    1997-05-28T23:59:59.000Z

    A Standards/Requirements Identification Document (S/RID) is the total list of the Environment, Safety and Health (ES and H) requirements to be implemented by a site, facility, or activity. These requirements are appropriate to the life cycle phase to achieve an adequate level of protection for worker and public health and safety, and the environment during design, construction, operation, decontamination and decommissioning, and environmental restoration. S/RlDs are living documents, to be revised appropriately based on change in the site`s or facility`s mission or configuration, a change in the facility`s life cycle phase, or a change to the applicable standards/requirements. S/RIDs encompass health and safety, environmental, and safety related safeguards and security (S and S) standards/requirements related to the functional areas listed in the US Department of Energy (DOE) Environment, Safety and Health Configuration Guide. The Fluor Daniel Hanford (FDH) Contract S/RID contains standards/requirements, applicable to FDH and FDH subcontractors, necessary for safe operation of Project Hanford Management Contract (PHMC) facilities, that are not the direct responsibility of the facility manager (e.g., a site-wide fire department). Facility S/RIDs contain standards/requirements applicable to a specific facility that are the direct responsibility of the facility manager. S/RlDs are prepared by those responsible for managing the operation of facilities or the conduct of activities that present a potential threat to the health and safety of workers, public, or the environment, including: Hazard Category 1 and 2 nuclear facilities and activities, as defined in DOE 5480.23. Selected Hazard Category 3 nuclear, and Low Hazard non-nuclear facilities and activities, as agreed upon by RL. The Postirradiation Testing Laboratory (PTL) S/RID contains standards/ requirements that are necessary for safe operation of the PTL facility, and other building/areas that are the direct responsibility of the specific facility manager. The specific DOE Orders, regulations, industry codes/standards, guidance documents and good industry practices that serve as the basis for each element/subelement are identified and aligned with each subelement.

  20. Clean Air Act Requirements: Uranium Mill Tailings

    E-Print Network [OSTI]

    EPA'S Clean Air Act Requirements: Uranium Mill Tailings Radon Emissions Rulemaking Reid J. Rosnick requirements for operating uranium mill tailings (Subpart W) Status update on Subpart W activities Outreach/Communications #12;3 EPA Regulatory Requirements for Operating Uranium Mill Tailings (Clean Air Act) · 40 CFR 61

  1. OM Code Requirements For MOVs -- OMN-1 and Appendix III

    SciTech Connect (OSTI)

    Kevin G. DeWall

    2011-08-01T23:59:59.000Z

    The purpose or scope of the ASME OM Code is to establish the requirements for pre-service and in-service testing of nuclear power plant components to assess their operational readiness. For MOVs this includes those that perform a specific function in shutting down a reactor to the safe shutdown condition, maintaining the safe shutdown condition, and mitigating the consequences of an accident. This paper will present a brief history of industry and regulatory activities related to MOVs and the development of Code requirements to address weaknesses in earlier versions of the OM Code. The paper will discuss the MOV requirements contained in the 2009 version of ASME OM Code, specifically Mandatory Appendix III and OMN-1, Revision 1.

  2. Coaxial test fixture

    DOE Patents [OSTI]

    Praeg, W.F.

    1984-03-30T23:59:59.000Z

    This invention pertains to arrangements for performing electrical tests on contact material samples, and in particular for testing contact material test samples in an evacuated environment under high current loads. Frequently, it is desirable in developing high-current separable contact material, to have at least a preliminary analysis of selected candidate conductor materials. Testing of material samples will hopefully identify materials unsuitable for high current electrical contact without requiring incorporation of the materials into a completed and oftentimes complex structure.

  3. SPECTR System Operational Test Report

    SciTech Connect (OSTI)

    W.H. Landman Jr.

    2011-08-01T23:59:59.000Z

    This report overviews installation of the Small Pressure Cycling Test Rig (SPECTR) and documents the system operational testing performed to demonstrate that it meets the requirements for operations. The system operational testing involved operation of the furnace system to the design conditions and demonstration of the test article gas supply system using a simulated test article. The furnace and test article systems were demonstrated to meet the design requirements for the Next Generation Nuclear Plant. Therefore, the system is deemed acceptable and is ready for actual test article testing.

  4. Nevada Test Site Radiation Protection Program

    SciTech Connect (OSTI)

    Radiological Control Managers' Council, Nevada Test Site

    2007-08-09T23:59:59.000Z

    Title 10 Code of Federal Regulations (CFR) 835, 'Occupational Radiation Protection', establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada Test Site (NTS), related (onsite or offsite) DOE National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration offsite projects.

  5. Advanced Thermal Simulator Testing: Thermal Analysis and Test Results

    SciTech Connect (OSTI)

    Bragg-Sitton, Shannon M.; Dickens, Ricky; Dixon, David; Reid, Robert; Adams, Mike; Davis, Joe [NASA Marshall Space Flight Center, Nuclear Systems Branch/ER24, MSFC, AL 35812 (United States)

    2008-01-21T23:59:59.000Z

    Work at the NASA Marshall Space Flight Center seeks to develop high fidelity, electrically heated thermal simulators that represent fuel elements in a nuclear reactor design to support non-nuclear testing applicable to the potential development of a space nuclear power or propulsion system. Comparison between the fuel pins and thermal simulators is made at the outer fuel clad surface, which corresponds to the outer sheath surface in the thermal simulator. The thermal simulators that are currently being tested correspond to a liquid metal cooled reactor design that could be applied for Lunar surface power. These simulators are designed to meet the geometric and power requirements of a proposed surface power reactor design, accommodate testing of various axial power profiles, and incorporate imbedded instrumentation. This paper reports the results of thermal simulator analysis and testing in a bare element configuration, which does not incorporate active heat removal, and testing in a water-cooled calorimeter designed to mimic the heat removal that would be experienced in a reactor core.

  6. The requirements discovery process

    SciTech Connect (OSTI)

    Bahill, A.T. [Univ. of Arizona, Tucson, AZ (United States). Systems and Industrial Engineering; Dean, F.F. [Sandia National Lab., Albuquerque, NM (United States)

    1997-02-01T23:59:59.000Z

    Cost and schedule overruns are often caused by poor requirements that are produced by people who do not understand the requirement process. This paper provides a high-level overview of the requirements discovery process.

  7. Evaluation on the Feasibility of Using Ultrasonic Testing of Reactor Pressure Vessel Welds for Assessing Flaw Density/Distribution per 10 CFR 50.61a, Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock

    SciTech Connect (OSTI)

    Sullivan, Edmund J.; Anderson, Michael T.

    2014-06-10T23:59:59.000Z

    This technical letter report provides the status of an assessment undertaken by PNNL at the request of the NRC to verify the capability of periodic ASME-required volumetric examinations of reactor vessels to characterize the density and distribution of flaws of interest for applying §50.61a on a plant-by-plant basis. The PTS rule, described in the Code of Federal Regulations, Title 10, Section 50.61 (§50.61), "Fracture Toughness Requirements for Protection against Pressurized Thermal Shock Events," establishes screening criteria to ensure that the potential for a reactor vessel to fail due to a PTS event is deemed to be acceptably low. Recently, the NRC completed a research program that concluded that the risk of through-wall cracking due to a PTS event is much lower than previously estimated. The NRC subsequently developed and promulgated an alternate PTS rule, §50.61a, that can be implemented by PWR licensees. The §50.61a rule differs from §50.61 in that it requires licensees who choose to follow this alternate method to analyze the results from periodic volumetric examinations required by the ASME Code, Section XI, Rules for Inservice Inspection (ISI) of Nuclear Power Plants.

  8. BER Requirements Review 2015

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

    Attendees 2015 ASCR Requirements Review 2015 Previous Reviews Requirements Review Reports Case Studies News & Publications ESnet News Publications and Presentations Galleries ESnet...

  9. ASCR Requirements Review 2015

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

    Requirements Review 2015 ASCR Attendees 2015 Previous Reviews Requirements Review Reports Case Studies News & Publications ESnet News Publications and Presentations Galleries ESnet...

  10. NREL Battery Thermal and Life Test Facility (Presentation)

    SciTech Connect (OSTI)

    Keyser, M.

    2011-05-01T23:59:59.000Z

    This presentation describes NREL's Battery Thermal Test Facility and identifies test requirements and equipment and planned upgrades to the facility.

  11. Blade Testing Trends (Presentation)

    SciTech Connect (OSTI)

    Desmond, M.

    2014-08-01T23:59:59.000Z

    As an invited guest speaker, Michael Desmond presented on NREL's NWTC structural testing methods and capabilities at the 2014 Sandia Blade Workshop held on August 26-28, 2014 in Albuquerque, NM. Although dynamometer and field testing capabilities were mentioned, the presentation focused primarily on wind turbine blade testing, including descriptions and capabilities for accredited certification testing, historical methodology and technology deployment, and current research and development activities.

  12. Test Series 2. 3 detailed test plan

    SciTech Connect (OSTI)

    Not Available

    1983-12-01T23:59:59.000Z

    Test Series 2.3 is chronologically the second of the five sub-series of tests which comprise Test Series 2, the second major Test Series as part of the combustion research phase to be carried out at the Grimethorpe Experimental Pressurised Fluidised Bed Combustion Facility. Test Series 2.3 will consist of 700 data gathering hours which is expected to require some 1035 coal burning hours. The tests will be performed using US supplied coal and dolomite. This will be the first major series of tests on the Facility with other than the UK datum coal and dolomite. The document summarises the background to the facility and the experimental program. Described are modifications which have been made to the facility following Test Series 2.1 and a series of Screening Tests. Detailed test objectives are specified as are the test conditions for the experiments which comprise the test series. The test results will provide information on the effects of the bed temperature, excess air level, Ca/S ratio, number of coal feed lines, and combustion efficiency and sulphur retention. A significant aspect of the test series will be part load tests which will investigate the performance of the facility under conditions of turn down which simulate load following concepts specified for two combined cycle concepts, i.e., their CFCC combined cycle and a turbo charged combined cycle. The material test plan is also presented. The principal feature of the materials programme is the planned exposure of a set of static turbine blade specimens in a cascade test loop to the high temperature, high pressure flue gas. A schedule for the programme is presented as are contingency plans.

  13. Federal Substance Abuse Testing Program

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

    2014-01-30T23:59:59.000Z

    The Order establishes the requirements and responsibilities for the DOE Federal Substance Abuse Testing Program which covers drug and alcohol testing. Cancels DOE O 3792.3 Chg 1.

  14. 3. MATERIAL CERTIFICATIONS REQUIRED NO RADIOGRAPHY REQUIRED.

    E-Print Network [OSTI]

    McDonald, Kirk

    SHALL BE DYE PENETRANT INSPECTED. ASME SECTION IX. NO CODE STAMP REQUIRED. 1. WELDING TO BE PERFORMED is property of 1. ALL DIMENSIONS ARE IN INCHES 2. INTERPRET DIMENSIONS AND TOLERANCES PER ASME Y14.5M 3

  15. Pressure tube testing test plan document production assurance program

    SciTech Connect (OSTI)

    Zaloudek, F.R. [Pacific Northwest Lab., Richland, WA (United States); Ruff, E.S. [UNC Nuclear Industries, Richland, WA (United States)

    1986-04-01T23:59:59.000Z

    UNC Nuclear Industries (UNC) has initiated a plan for the manufacture of zirconium alloy pressure tubes required for the future operation of N-Reactor. As part of this plan, UNC is establishing a program to qualify and develop a manufacturing process capable of fabricating these pressure tubes to the requirements of UNC specification HWS 6502, REV 4, Amendment 1. The objective of the task described in this test plan is to support the UNC program by performing physical/chemical testing on prototype tubes sections produced or procured during FY-1986, 1987 and 1988 and to test samples from production runs after 1988 as may be required. The types of tests included in this pressure tube testing task will be as follows: (1) Tensile tests; (2) Burst testing; (3) Tests to evaluate fracture properties; (4) Corrosion tests; (5) Spectrographic analysis of chemical composition; (6) Metallographic evaluation of grain size and oxide layer thickness.

  16. Standard test method for creep-fatigue crack growth testing

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 This test method covers the determination of creep-fatigue crack growth properties of nominally homogeneous materials by use of pre-cracked compact type, C(T), test specimens subjected to uniaxial cyclic forces. It concerns fatigue cycling with sufficiently long loading/unloading rates or hold-times, or both, to cause creep deformation at the crack tip and the creep deformation be responsible for enhanced crack growth per loading cycle. It is intended as a guide for creep-fatigue testing performed in support of such activities as materials research and development, mechanical design, process and quality control, product performance, and failure analysis. Therefore, this method requires testing of at least two specimens that yield overlapping crack growth rate data. The cyclic conditions responsible for creep-fatigue deformation and enhanced crack growth vary with material and with temperature for a given material. The effects of environment such as time-dependent oxidation in enhancing the crack growth ra...

  17. Technical requirements specification for tank waste retrieval

    SciTech Connect (OSTI)

    Lamberd, D.L.

    1996-09-26T23:59:59.000Z

    This document provides the technical requirements specification for the retrieval of waste from the underground storage tanks at the Hanford Site. All activities covered by this scope are conducted in support of the Tank Waste Remediation System (TWRS) mission.

  18. FES Requirements Review 2014

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

    Review 2014 FES Attendees 2014 BES Requirements Review 2014 Requirements Review Reports Case Studies Contact Us Technical Assistance: 1 800-33-ESnet (Inside US) 1 800-333-7638...

  19. BES Requirements Review 2014

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

    Review 2014 BES Requirements Review 2014 BES Attendees 2014 Requirements Review Reports Case Studies Contact Us Technical Assistance: 1 800-33-ESnet (Inside US) 1 800-333-7638...

  20. Automated particulate sampler field test model operations guide

    SciTech Connect (OSTI)

    Bowyer, S.M.; Miley, H.S.

    1996-10-01T23:59:59.000Z

    The Automated Particulate Sampler Field Test Model Operations Guide is a collection of documents which provides a complete picture of the Automated Particulate Sampler (APS) and the Field Test in which it was evaluated. The Pacific Northwest National Laboratory (PNNL) Automated Particulate Sampler was developed for the purpose of radionuclide particulate monitoring for use under the Comprehensive Test Ban Treaty (CTBT). Its design was directed by anticipated requirements of small size, low power consumption, low noise level, fully automatic operation, and most predominantly the sensitivity requirements of the Conference on Disarmament Working Paper 224 (CDWP224). This guide is intended to serve as both a reference document for the APS and to provide detailed instructions on how to operate the sampler. This document provides a complete description of the APS Field Test Model and all the activity related to its evaluation and progression.

  1. Allocating Reserve Requirements (Presentation)

    SciTech Connect (OSTI)

    Milligan, M.; Kirby, B.; King, J.

    2011-07-01T23:59:59.000Z

    This presentation provides an overview of present and possible future ways to allocate and assign benefits for reserve requirements.

  2. BER Science Network Requirements

    E-Print Network [OSTI]

    Dart, Eli

    2011-01-01T23:59:59.000Z

    Management and analysis of geospatial data involvingmanipulation, analysis, and display of geospatial data,Analysis and interpretation require mapping geospatial

  3. Improvements to Technical Specifications surveillance requirements

    SciTech Connect (OSTI)

    Lobel, R.; Tjader, T.R.

    1992-12-01T23:59:59.000Z

    In August 1983 an NRC task group was formed to investigate problems with surveillance testing required by Technical Specifications, and to recommend approaches to effect improvements. NUREG-1024 ( Technical Specifications-Enhancing Safety Impact'') resulted, and it contained recommendations to review the basis for test frequencies; to ensure that the tests promote safety and do not degrade equipment; and to review surveillance tests so that they do not unnecessarily burden personnel. The Technical Specifications Improvement Program (TSIP) was established in December 1984 to provide the framework for rewriting and improving the Technical Specifications. As an element of the TSIP, all Technical Specifications surveillance requirements were comprehensively examined as recommended in NUREG-1024. The results of that effort are presented in this report. The study found that while some testing at power is essential to verify equipment and system operability, safety can be improved, equipment degradation decreased, and unnecessary personnel burden relaxed by reducing the amount of testing at power.

  4. U.S. Department of Energy FreedomCAR and Vehicle Technologies Program Advanced Vehicle Testing Activity Federal Fleet Use of Electric Vehicles

    SciTech Connect (OSTI)

    Mindy Kirpatrick; J. E. Francfort

    2003-11-01T23:59:59.000Z

    Per Executive Order 13031, “Federal Alternative Fueled Vehicle Leadership,” the U.S. Department of Energy’s (DOE’s) Advanced Vehicle Testing Activity provided $998,300 in incremental funding to support the deployment of 220 electric vehicles in 36 Federal fleets. The 145 electric Ford Ranger pickups and 75 electric Chrysler EPIC (Electric Powered Interurban Commuter) minivans were operated in 14 states and the District of Columbia. The 220 vehicles were driven an estimated average of 700,000 miles annually. The annual estimated use of the 220 electric vehicles contributed to 39,000 fewer gallons of petroleum being used by Federal fleets and the reduction in emissions of 1,450 pounds of smog-forming pollution. Numerous attempts were made to obtain information from all 36 fleets. Information responses were received from 25 fleets (69% response rate), as some Federal fleet personnel that were originally involved with the Incremental Funding Project were transferred, retired, or simply could not be found. In addition, many of the Department of Defense fleets indicated that they were supporting operations in Iraq and unable to provide information for the foreseeable future. It should be noted that the opinions of the 25 fleets is based on operating 179 of the 220 electric vehicles (81% response rate). The data from the 25 fleets is summarized in this report. Twenty-two of the 25 fleets reported numerous problems with the vehicles, including mechanical, traction battery, and charging problems. Some of these problems, however, may have resulted from attempting to operate the vehicles beyond their capabilities. The majority of fleets reported that most of the vehicles were driven by numerous drivers each week, with most vehicles used for numerous trips per day. The vehicles were driven on average from 4 to 50 miles per day on a single charge. However, the majority of the fleets reported needing gasoline vehicles for missions beyond the capabilities of the electric vehicles, usually because of range limitations. Twelve fleets reported experiencing at least one charge depletion while driving, whereas nine fleets reported not having this problem. Twenty-four of the 25 fleets responded that the electric vehicles were easy to use and 22 fleets indicated that the payload was adequate. Thirteen fleets reported charging problems; eleven fleets reported no charging problems. Nine fleets reported the vehicles broke down while driving; 14 fleets reported no onroad breakdowns. Some of the breakdowns while driving, however, appear to include normal flat tires and idiot lights coming on. In spite of operation and charging problems, 59% of the fleets responded that they were satisfied, very satisfied, or extremely satisfied with the performance of the electric vehicles. As of September 2003, 74 of the electric vehicles were still being used and 107 had been returned to the manufacturers because the leases had concluded.

  5. FES Science Network Requirements

    E-Print Network [OSTI]

    Geddes, Cameron Guy Robinson

    FES Science Network Requirements Report of the Fusion Energy Sciences Network Requirements Workshop Conducted March 13 and 14, 2008 #12;FES Science Network Requirements Workshop Fusion Energy Sciences Program Office, DOE Office of Science Energy Sciences Network Gaithersburg, MD ­ March 13 and 14, 2008 ESnet

  6. Material Testing of Coated Alloys in a Syngas Combustion Environment Year 6 - Activity 1.13 - Development of a National Center for Hydrogen Technology

    SciTech Connect (OSTI)

    Swanson, Michael

    2011-09-01T23:59:59.000Z

    Modifications were made to the inlet of the existing Energy & Environmental Research Center (EERC) thermal oxidizer to accommodate side-by-side coupon holders for exposure testing. Two 5-day tests with over 200 hours of total exposure time were completed. The first week of testing was conducted in enriched air-blown mode, with coupon temperatures ranging from 128° to 272°F. Carbonyl sampling was conducted, but it was discovered after the fact that the methodology used was producing very low recoveries of iron and nickel carbonyl. Therefore, the data generated during this week of testing were not considered accurate. The second week of testing was conducted in oxygen-blown mode, with coupon temperatures ranging from 220° to 265°F. Two improved methods were used to measure carbonyl concentration during this week of testing. These methods produced results closer to equilibrium calculations. Since both weeks of testing mostly produced a product gas with approximately 15%–18% carbon monoxide, it was felt that actual carbonyl concentrations for Week 1 should be very similar to those measured during Week 2. The revised carbonyl sampling methodology used during the second week of testing greatly improved the recovery of iron and nickel carbonyl in the sample. Even though the sampling results obtained from the first week were inaccurate, the results from the second week can be used as an estimate for the periods during which the gasifier was operating under similar conditions and producing similar product gas compositions. Specifically, Test Periods 2 and 3 from the first week were similar to the conditions run during the second week. For a product gas containing roughly 15%–18% CO and a coupon temperature of approximately 220°–270°F, the nickel carbonyl concentration should be about 0.05–0.1 ppm and the iron carbonyl concentration should be about 0.1–0.4 ppm. After each week of testing the coupons were recovered from the coupon holder, weighed, and shipped back to Siemens for analysis.

  7. U.S. Department of Energy Vehicle Technologies Program -- Advanced Vehicle Testing Activity -- Plug-in Hybrid Electric Vehicle Charging Infrastructure Review

    SciTech Connect (OSTI)

    Kevin Morrow; Donald Darner; James Francfort

    2008-11-01T23:59:59.000Z

    Plug-in hybrid electric vehicles (PHEVs) are under evaluation by various stake holders to better understand their capability and potential benefits. PHEVs could allow users to significantly improve fuel economy over a standard HEV and in some cases, depending on daily driving requirements and vehicle design, have the ability to eliminate fuel consumption entirely for daily vehicle trips. The cost associated with providing charge infrastructure for PHEVs, along with the additional costs for the on-board power electronics and added battery requirements associated with PHEV technology will be a key factor in the success of PHEVs. This report analyzes the infrastructure requirements for PHEVs in single family residential, multi-family residential and commercial situations. Costs associated with this infrastructure are tabulated, providing an estimate of the infrastructure costs associated with PHEV deployment.

  8. ASCR Science Network Requirements

    SciTech Connect (OSTI)

    Dart, Eli; Tierney, Brian

    2009-08-24T23:59:59.000Z

    The Energy Sciences Network (ESnet) is the primary provider of network connectivity for the US Department of Energy Office of Science, the single largest supporter of basic research in the physical sciences in the United States. In support of the Office of Science programs, ESnet regularly updates and refreshes its understanding of the networking requirements of the instruments, facilities, scientists, and science programs that it serves. This focus has helped ESnet to be a highly successful enabler of scientific discovery for over 20 years. In April 2009 ESnet and the Office of Advanced Scientific Computing Research (ASCR), of the DOE Office of Science, organized a workshop to characterize the networking requirements of the programs funded by ASCR. The ASCR facilities anticipate significant increases in wide area bandwidth utilization, driven largely by the increased capabilities of computational resources and the wide scope of collaboration that is a hallmark of modern science. Many scientists move data sets between facilities for analysis, and in some cases (for example the Earth System Grid and the Open Science Grid), data distribution is an essential component of the use of ASCR facilities by scientists. Due to the projected growth in wide area data transfer needs, the ASCR supercomputer centers all expect to deploy and use 100 Gigabit per second networking technology for wide area connectivity as soon as that deployment is financially feasible. In addition to the network connectivity that ESnet provides, the ESnet Collaboration Services (ECS) are critical to several science communities. ESnet identity and trust services, such as the DOEGrids certificate authority, are widely used both by the supercomputer centers and by collaborations such as Open Science Grid (OSG) and the Earth System Grid (ESG). Ease of use is a key determinant of the scientific utility of network-based services. Therefore, a key enabling aspect for scientists beneficial use of high performance networks is a consistent, widely deployed, well-maintained toolset that is optimized for wide area, high-speed data transfer (e.g. GridFTP) that allows scientists to easily utilize the services and capabilities that the network provides. Network test and measurement is an important part of ensuring that these tools and network services are functioning correctly. One example of a tool in this area is the recently developed perfSONAR, which has already shown its usefulness in fault diagnosis during the recent deployment of high-performance data movers at NERSC and ORNL. On the other hand, it is clear that there is significant work to be done in the area of authentication and access control - there are currently compatibility problems and differing requirements between the authentication systems in use at different facilities, and the policies and mechanisms in use at different facilities are sometimes in conflict. Finally, long-term software maintenance was of concern for many attendees. Scientists rely heavily on a large deployed base of software that does not have secure programmatic funding. Software packages for which this is true include data transfer tools such as GridFTP as well as identity management and other software infrastructure that forms a critical part of the Open Science Grid and the Earth System Grid.

  9. Cylinder Test Specification

    SciTech Connect (OSTI)

    Richard Catanach; Larry Hill; Herbert Harry; Ernest Aragon; Don Murk

    1999-10-01T23:59:59.000Z

    The purpose of the cylinder testis two-fold: (1) to characterize the metal-pushing ability of an explosive relative to that of other explosives as evaluated by the E{sub 19} cylinder energy and the G{sub 19} Gurney energy and (2) to help establish the explosive product equation-of-state (historically, the Jones-Wilkins-Lee (JWL) equation). This specification details the material requirements and procedures necessary to assemble and fire a typical Los Alamos National Laboratory (LANL) cylinder test. Strict adherence to the cylinder. material properties, machining tolerances, material heat-treatment and etching processes, and high explosive machining tolerances is essential for test-to-test consistency and to maximize radial wall expansions. Assembly and setup of the cylinder test require precise attention to detail, especially when placing intricate pin wires on the cylinder wall. The cylinder test is typically fired outdoors and at ambient temperature.

  10. AVTA: Transit Vehicle Specifications and Test Procedures

    Broader source: Energy.gov [DOE]

    All Advanced Vehicle Testing Activity transit projects follow a rigorous data collection and analysis protocol. Refer to "General Evaluation Plan: Fleet Test and Evaluation Projects" for...

  11. Nevada Test Site Environmental Summary Report 2006

    SciTech Connect (OSTI)

    Cathy Wills

    2007-10-01T23:59:59.000Z

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada Test Site (NTS). The NTS is the nation's historical testing site for nuclear weapons from 1951 through 1992 and is currently the nation's unique site for ongoing national-security related missions and high-risk operations. NNSA/NSO strives to provide to the public an understanding of the current activities on the NTS, including environmental monitoring and compliance activities aimed at protecting the public and the environment from radiation hazards and from nonradiological impacts. This document is a summary of the Nevada Test Site Environmental Report (NTSER) for calendar year 2006 (see attached compact disc on inside back cover). The NTSER is a comprehensive report of environmental activities performed at the NTS and its satellite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. To provide an abbreviated and more readable version of the NTSER, this summary report is produced. This summary does not include detailed data tables, monitoring methods or design, a description of the NTS environment, or a discussion of all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

  12. Nevada Test Site Summary 2006 (Volume 2)

    SciTech Connect (OSTI)

    Cathy Wills

    2007-10-01T23:59:59.000Z

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada Test Site (NTS). The NTS is the nation's historical testing site for nuclear weapons from 1951 through 1992 and is currently the nation's unique site for ongoing national-security-related missions and high-risk operations. NNSA/NSO strives to provide to the public an understanding of the current activities on the NTS, including environmental monitoring and compliance activities aimed at protecting the public and the environment from radiation hazards and from nonradiological impacts. This document is a summary of the Nevada Test Site Environmental Report (NTSER) for calendar year 2006 (see attached compact disc on inside back cover). The NTSER is a comprehensive report of environmental activities performed at the NTS and its satellite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. To provide an abbreviated and more readable version of the NTSER, this summary report is produced. This summary does not include detailed data tables, monitoring methods or design, a description of the NTS environment, or a discussion of all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

  13. Nevada Test Site Environmental Report 2007 Summary

    SciTech Connect (OSTI)

    Cathy Wills

    2008-09-01T23:59:59.000Z

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada Test Site (NTS). The NTS is the nation's historical testing site for nuclear weapons from 1951 through 1992 and is currently the nation's unique site for ongoing national-security related missions and high-risk operations. NNSA/NSO strives to provide to the public an understanding of the current activities on the NTS, including environmental monitoring and compliance activities aimed at protecting the public and the environment from radiation hazards and from nonradiological impacts. This document is a summary of the Nevada Test Site Environmental Report (NTSER) for calendar year 2007 (see attached compact disc on inside back cover). The NTSER is a comprehensive report of environmental activities performed at the NTS and offsite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. To provide an abbreviated and more readable version of the NTSER, this summary report is produced. This summary does not include detailed data tables, monitoring methods or design, a description of the NTS environment, or a discussion of all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

  14. Double tracks test site characterization report

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    This report presents the results of site characterization activities performed at the Double Tracks Test Site, located on Range 71 North, of the Nellis Air Force Range (NAFR) in southern Nevada. Site characterization activities included reviewing historical data from the Double Tracks experiment, previous site investigation efforts, and recent site characterization data. The most recent site characterization activities were conducted in support of an interim corrective action to remediate the Double Tracks Test Site to an acceptable risk to human health and the environment. Site characterization was performed using a phased approach. First, previously collected data and historical records sere compiled and reviewed. Generalized scopes of work were then prepared to fill known data gaps. Field activities were conducted and the collected data were then reviewed to determine whether data gaps were filled and whether other areas needed to be investigated. Additional field efforts were then conducted, as required, to adequately characterize the site. Characterization of the Double Tracks Test Site was conducted in accordance with the US Department of Energy`s (DOE) Streamlined Approach for Environmental Restoration (SAFER).

  15. Pendulum detector testing device

    DOE Patents [OSTI]

    Gonsalves, John M. (Modesto, CA)

    1997-01-01T23:59:59.000Z

    A detector testing device which provides consistent, cost-effective, repeatable results. The testing device is primarily constructed of PVC plastic and other non-metallic materials. Sensitivity of a walk-through detector system can be checked by: 1) providing a standard test object simulating the mass, size and material content of a weapon or other contraband, 2) suspending the test object in successive positions, such as head, waist and ankle levels, simulating where the contraband might be concealed on a person walking through the detector system; and 3) swinging the suspended object through each of the positions, while operating the detector system and observing its response. The test object is retained in a holder in which the orientation of the test device or target can be readily changed, to properly complete the testing requirements.

  16. Pendulum detector testing device

    DOE Patents [OSTI]

    Gonsalves, J.M.

    1997-09-30T23:59:59.000Z

    A detector testing device is described which provides consistent, cost-effective, repeatable results. The testing device is primarily constructed of PVC plastic and other non-metallic materials. Sensitivity of a walk-through detector system can be checked by: (1) providing a standard test object simulating the mass, size and material content of a weapon or other contraband, (2) suspending the test object in successive positions, such as head, waist and ankle levels, simulating where the contraband might be concealed on a person walking through the detector system; and (3) swinging the suspended object through each of the positions, while operating the detector system and observing its response. The test object is retained in a holder in which the orientation of the test device or target can be readily changed, to properly complete the testing requirements. 5 figs.

  17. Nutritional requirements of sesame

    E-Print Network [OSTI]

    Eller, Joe C

    1958-01-01T23:59:59.000Z

    L)&RARYi ~st t~6~ 0F TEXACO NUTRITIONAL REQUIREMENTS OF SESAME A Thesis By JOE C. ELLER Submitted to the Graduate School of the Agricultural and Mechanical College of Texas in. partial fulfillment of the requirements for the degree of M... AS TER 0 F SCIENC E January 1958 Major Subject: Agronomy NUTRITIONAL REQUIREMENTS OF SESAME A Thesis JOE C. ELLER Approved. as to style and content by. ' Chairman of Committee Head qg Department January 1958 ACKNOWLEDGEMENT The author wishes...

  18. RPAM & Energy Order Requirements

    Energy Savers [EERE]

    430.1C, Real Property Asset Management and DOE O 430.2B, Departmental Energy, Renewable Energy and Transportation Management Requirements, Overlap & Differences Office of...

  19. Required Annual Notices

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

    Required Annual Notices The Women's Health and Cancer Rights Act of 1998 (WHCRA) The medical programs sponsored by LANS will not restrict benefits if you or your dependent...

  20. Transuranic Waste Requirements

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

    1999-07-09T23:59:59.000Z

    The guide provides criteria for determining if a waste is to be managed in accordance with DOE M 435.1-1, Chapter III, Transuranic Waste Requirements.

  1. CH2M Hill Hanford Group, Inc. Standards and Requirements Identification Document (SRID) Requirements Management System and Requirements Specification

    SciTech Connect (OSTI)

    JOHNSON, A.L.

    2000-11-30T23:59:59.000Z

    The current Tank Farm Contractor (TFC) for the U. S. Department of Energy, Office of River Protection (ORP), River Protection Project (RPP), CH2M Hill Hanford Group, Inc. (CHG), will use a computer based requirements management system. The system will serve as a tool to assist in identifying, capturing, and maintaining the Standards/Requirements Identification Document (S/RID) requirements and links to implementing procedures and other documents. By managing requirements as one integrated set, CHG will be able to carry out its mission more efficiently and effectively. CHG has chosen the Dynamic Object Oriented Requirements System (DOORS{trademark}) as the preferred computer based requirements management system. Accordingly, the S/RID program will use DOORS{trademark}. DOORS{trademark} will replace the Environmental Requirements Management Interface (ERMI) system as the tool for S/RID data management. The DOORS{trademark} S/RID test project currently resides on the DOORSTM test server. The S/RID project will be migrated to the DOORS{trademark} production server. After the migration the S/RID project will be considered a production project and will no longer reside on the test server.

  2. AVTA: 2010 Volkswagon Golf Diesel Start-Stop Testing Results...

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

    Volkswagon Golf Diesel Start-Stop Testing Results AVTA: 2010 Volkswagon Golf Diesel Start-Stop Testing Results The Vehicle Technologies Office's Advanced Vehicle Testing Activity...

  3. General Responsibilities and Requirements

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

    1999-07-09T23:59:59.000Z

    The material presented in this guide provides suggestions and acceptable ways of implementing DOE M 435.1-1 and should not be viewed as additional or mandatory requirements. The objective of the guide is to ensure that responsible individuals understand what is necessary and acceptable for implementing the requirements of DOE M 435.1-1.

  4. RMOTC - Testing

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

    Sale of Equipment and Materials DOE to Sell NPR-3 Testing Tomorrow's Technology Today RMOTC - Testing - From Lab to Industry, Moving Your Ideas Forward RMOTC provides a neutral,...

  5. Other Requirements - DOE Directives, Delegations, and Requirements

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)IntegratedSpeeding access toTest andOptimize carbonOther File Systems Other FileAbout

  6. Heuristic Search with Reachability Tests for Automated Generation of Test Programs

    E-Print Network [OSTI]

    Leow, Wee Kheng

    Heuristic Search with Reachability Tests for Automated Generation of Test Programs Wee Kheng Leow specification-based soft- ware testing has focused on the automated generation of test cases. Before a software system can be tested, it must be set up according to the input requirements of the test cases. This setup

  7. Psychrometric Testing Facility Restoration and Cooling Capacity Testing 

    E-Print Network [OSTI]

    Cline, Vincent E.

    2010-10-12T23:59:59.000Z

    .................................................................. 15 Table 3 Specified test tolerances for cooling capacity testing according to ASHRAE 210/240 .................................................................. 16 Table 4 Required test condition variations not covered in Table 2... throughout the test while maintaining the room conditions [2]. The air conditioning system and psychrometric rooms are run for at least 1.5 hours before data is recorded in order to allow the rooms to reach and maintain steady state conditions. Data...

  8. BES Science Network Requirements

    E-Print Network [OSTI]

    Dart, Eli

    2011-01-01T23:59:59.000Z

    the Directors of the Office of Science, Office of AdvancedOffice of Basic Energy Sciences. This is LBNL report LBNL-BES Science Network Requirements Report of the Basic Energy

  9. Timeline for Net Requirements

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

    x By July 31 of each Forecast Year, BPA publishes all Load Following customers' Net Requirements data for the two years of the upcoming Rate Period. 17.6.1 7312010 Yes...

  10. Conditions Required by Law

    E-Print Network [OSTI]

    Khan, Javed I.

    No No Sto H 2 NoIs it required by law "Violence on children"?164.512 (c) (1) H CE may disclose to government to LEO HCE may not disclose to LEO H No Yes No Required by law: "reporting certain type of injuries"? H disclose to LEO H 164.512 (f) (1) (ii) (C)(2) It provides that the request is specific and limited in scope

  11. Requirements | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative JC3 RSS September 9,Award RecipientsActMission to ChinaRequirements Requirements

  12. Mobile Energy Laboratory energy-efficiency testing programs

    SciTech Connect (OSTI)

    Parker, G.B.; Currie, J.W.

    1991-09-01T23:59:59.000Z

    This report summarizes energy-efficiency testing activities applying the Mobile Energy Laboratory (MEL) testing capabilities during the first and second quarters of fiscal year (FY) 1991. The MELs, developed by the US Department of Energy (DOE) Federal Energy Management Program (FEMP), are administered by Pacific Northwest Laboratory (PNL) and the Naval Energy and Environmental Support Activity (NEESA) for energy testing and energy conservation program support functions at federal facilities. The using agencies principally fund MEL applications, while DOE/FEMP funds program administration and capability enhancement activities. This report fulfills the requirements established in Section 8 of the MEL Use Plan (PNL-6861) for semiannual reporting on energy-efficiency testing activities using the MEL capabilities. The MEL Use Committee, formally established in 1989, developed the MEL Use Plan and meets semiannually to establish priorities for energy-efficient testing applications using the MEL capabilities. The MEL Use Committee is composed of one representative each of the US Department of Energy, US Army, US Air Force, US Navy, and other federal agencies.

  13. Gas Test Loop Booster Fuel Hydraulic Testing

    SciTech Connect (OSTI)

    Gas Test Loop Hydraulic Testing Staff

    2006-09-01T23:59:59.000Z

    The Gas Test Loop (GTL) project is for the design of an adaptation to the Advanced Test Reactor (ATR) to create a fast-flux test space where fuels and materials for advanced reactor concepts can undergo irradiation testing. Incident to that design, it was found necessary to make use of special booster fuel to enhance the neutron flux in the reactor lobe in which the Gas Test Loop will be installed. Because the booster fuel is of a different composition and configuration from standard ATR fuel, it is necessary to qualify the booster fuel for use in the ATR. Part of that qualification is the determination that required thermal hydraulic criteria will be met under routine operation and under selected accident scenarios. The Hydraulic Testing task in the GTL project facilitates that determination by measuring flow coefficients (pressure drops) over various regions of the booster fuel over a range of primary coolant flow rates. A high-fidelity model of the NW lobe of the ATR with associated flow baffle, in-pile-tube, and below-core flow channels was designed, constructed and located in the Idaho State University Thermal Fluids Laboratory. A circulation loop was designed and constructed by the university to provide reactor-relevant water flow rates to the test system. Models of the four booster fuel elements required for GTL operation were fabricated from aluminum (no uranium or means of heating) and placed in the flow channel. One of these was instrumented with Pitot tubes to measure flow velocities in the channels between the three booster fuel plates and between the innermost and outermost plates and the side walls of the flow annulus. Flow coefficients in the range of 4 to 6.5 were determined from the measurements made for the upper and middle parts of the booster fuel elements. The flow coefficient for the lower end of the booster fuel and the sub-core flow channel was lower at 2.3.

  14. Thermal test options

    SciTech Connect (OSTI)

    Koski, J.A.; Keltner, N.R.; Sobolik, K.B.

    1993-02-01T23:59:59.000Z

    Shipping containers for radioactive materials must be qualified to meet a thermal accident environment specified in regulations, such at Title 10, Code of Federal Regulations, Part 71. Aimed primarily at the shipping container design, this report discusses the thermal testing options available for meeting the regulatory requirements, and states the advantages and disadvantages of each approach. The principal options considered are testing with radiant heat, furnaces, and open pool fires. The report also identifies some of the facilities available and current contacts. Finally, the report makes some recommendations on the appropriate use of these different testing methods.

  15. Velocity requirements for causality violation

    E-Print Network [OSTI]

    Giovanni Modanese

    2015-01-18T23:59:59.000Z

    We re-examine the "Regge-Tolman paradox" with reference to some recent experimental results. It is straightforward to find a formula for the velocity v of the moving system required to produce causality violation. This formula typically yields a velocity very close to the speed of light (for instance, v/c > 0.97 for X-shaped microwaves), which raises some doubts about the real physical observability of the violations. We then compute the velocity requirement introducing a delay between the reception of the primary signal and the emission of the secondary. It turns out that in principle for any delay it is possible to find moving observers able to produce active causal violation. This is mathematically due to the singularity of the Lorentz transformations for beta to 1. For a realistic delay due to the propagation of a luminal precursor, we find that causality violations in the reported experiments are still more unlikely (v/c > 0.989), and even in the hypothesis that the superluminal propagation velocity goes to infinity, the velocity requirement is bounded by v/c > 0.62. We also prove that if two macroscopic bodies exchange energy and momentum through superluminal signals, then the swap of signal source and target is incompatible with the Lorentz transformations; therefore it is not possible to distinguish between source and target, even with reference to a definite reference frame.

  16. An Assessment of Fault Current Limiter Testing Requirements | Department of

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently20,000 RussianBy:Whether you're a16-17,2-13) All OtherDepartmentEnergy The U.S.

  17. An Assessment of Fault Current Limiter Testing Requirements | Department of

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny: The Future of1Albuquerque, NMPerformance | Department of Energy An Approach

  18. Entry/Exit Port testing, test report

    SciTech Connect (OSTI)

    Winkelman, R.H.

    1993-05-01T23:59:59.000Z

    The Waste Receiving and Processing Module I (WRAP-1) facility must have the ability to allow 55-gallon drums to enter and exit glovebox enclosures. An Entry/Exit Port (Appendix 1, Figure 1), designed by United Engineers and Constructors (UE&C), is one method chosen for drum transfer. The Entry/Exit Port is to be used for entry of 55-gallon drums into both process entry gloveboxes, exit of 55-gallon drum waste pucks from the low-level waste (LLW) glovebox, and loadout of waste from the restricted waste management glovebox. The Entry/Exit Port relies on capture velocity air flow and a neoprene seal to provide alpha confinement when the Port is in the open and closed positions, respectively. Since the glovebox is in a slight vacuum, air flow is directed into the glovebox through the space between the overpack drum and glovebox floor. The air flow is to direct any airborne contamination into the glovebox. A neoprene seal is used to seal the Port door to the glovebox floor, thus maintaining confinement in the closed position. Entry/Exit Port testing took place February 17, 1993, through April 14, 1993, in the 305 building of Westinghouse Hanford Company. Testing was performed in accordance with the Entry/Exit Port Testing Test Plan, document number WHC-SD-WO26-TP-005. A prototype Entry/Exit Port built at the Hanford Site was tested using fluorescent paint pigment and smoke candles as simulant contaminants. This test report is an interim test report. Further developmental testing is required to test modifications made to the Port as the original design of the Port did not provide complete confinement during all stages of operation.

  19. Test Images

    E-Print Network [OSTI]

    Test Images. I hope to have a set of test images for the course soon. Some images are available now; some will have to wait until I can find another 100-200

  20. Characterizing guayule rubber transferase activity

    SciTech Connect (OSTI)

    Cornish, K.; Backhaus, R.A. (Arizona State Univ., Tempe (USA))

    1989-04-01T23:59:59.000Z

    Rubber transferase (RuT) activity, measured as incorporation of {sup 14}C(isopentenyl pyrophosphate) (IPP) into rubber, was assayed in suspensions of rubber particles purified from bark tissue of Parthenium argentatum, Gray. Rubber particle suspensions (RSP) have high RuT activity which is not diminished by repeated washing of the particles, demonstrating the firm association of the enzyme system with the particles. RuT activity varied with line: 11591 yielded more rubber particles with a greater activity per particle, than did other lines tested. Variation in activity also varied with bark age and season. Activity rapidly declined at temperatures above 16{degree}C in line 593, but was more stable in RSP isolated form line 11591. IPP-incorporation depends upon the concentration of two substrates, IPP and the starter molecule farnesyl pyrophosphate (FPP). In lines 593 and 11591, 20 uM FPP saturated the enzyme present in 6 {times} 10{sup 10} particles {times} cm{sup {minus}3}, whereas about 1 mM IPP was required for saturation. Under saturating FPP, the apparent K{sub m} of RuT was about 250 uM.

  1. Idaho National Laboratory Testing of Advanced Technology Vehicles

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

    * PEV infrastructure requirements and impacts are not yet understood * Development of codes and standards for products and testing is required Budget FY 2012 project funding...

  2. Requirements for Xenon International

    SciTech Connect (OSTI)

    Hayes, James C.; Ely, James H.

    2013-09-26T23:59:59.000Z

    This document defines the requirements for the new Xenon International radioxenon system. The output of this project will be a Pacific Northwest National Laboratory (PNNL) developed prototype and a manufacturer-developed production prototype. The two prototypes are intended to be as close to matching as possible; this will be facilitated by overlapping development cycles and open communication between PNNL and the manufacturer.

  3. THE REQUIREMENTS OF A FUSION DEMONSTRATION

    E-Print Network [OSTI]

    Najmabadi, Farrokh

    and will analyze the strategies, facilities, and prior testing requirements needed to demonstrate electric power Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes constitute or imply its endorsement, recommendation, or favoring by the United States Government or any

  4. Airbus Toulouse Flight test data centre. Diagnosis and treatment of noisy vibration flight test data.

    E-Print Network [OSTI]

    Dobigeon, Nicolas

    Airbus Toulouse ­ Flight test data centre. Diagnosis and treatment of noisy vibration flight test data. The trainee will work within flight test vibration analysis team.The main missions and activities on flight test vibration data; - Implement and test in LMS Test.Lab (vibration data processing software

  5. Evaluation of testing and reservoir parameters in geothermal...

    Open Energy Info (EERE)

    tests require information on the geology, geochemistry, surficial and borehole geophysics, and well construction and development methods. Nonideal test conditions and a...

  6. application test reactor: Topics by E-print Network

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

    flow reactors (OFRs). A micro-bioreactor (working (more) Reis, N. 2006-01-01 4 Web Application Testing with Customized Test Requirements Computer Technologies and...

  7. TESTING THE UNIFICATION MODEL FOR ACTIVE GALACTIC NUCLEI IN THE INFRARED: ARE THE OBSCURING TORI OF TYPE 1 AND 2 SEYFERTS DIFFERENT?

    SciTech Connect (OSTI)

    Ramos Almeida, C. [Department of Physics and Astronomy, University of Sheffield, S3 7RH (United Kingdom); Levenson, N. A.; Radomski, J. T. [Gemini Observatory, Casilla 603, La Serena (Chile); Alonso-Herrero, A. [Centro de Astrobiologia, INTA-CSIC, E-28850 Madrid (Spain); Asensio Ramos, A.; Rodriguez Espinosa, J. M.; Perez Garcia, A. M. [Instituto de Astrofisica de Canarias (IAC), C/VIa Lactea, s/n, E-38205 La Laguna, Tenerife (Spain); Packham, C. [Astronomy Department, University of Florida, 211 Bryant Space Science Center, P.O. Box 112055, Gainesville, FL 32611-2055 (United States); Mason, R. [Gemini Observatory, Northern Operations Center, 670 North Aohoku Place, Hilo, HI 96720 (United States); DIaz-Santos, T., E-mail: C.Ramos@sheffield.ac.es [Department of Physics, University of Crete, GR-71003 Heraklion (Greece)

    2011-04-20T23:59:59.000Z

    We present new mid-infrared imaging data for three Type-1 Seyfert galaxies obtained with T-ReCS on the Gemini-South Telescope at subarcsecond resolution. Our aim is to enlarge the sample studied in a previous work to compare the properties of Type-1 and Type-2 Seyfert tori using clumpy torus models and a Bayesian approach to fit the infrared (IR) nuclear spectral energy distributions. Thus, the sample considered here comprises 7 Type-1, 11 Type-2, and 3 intermediate-type Seyferts. The unresolved IR emission of the Seyfert 1 galaxies can be reproduced by a combination of dust heated by the central engine and direct active galactic nucleus (AGN) emission, while for the Seyfert 2 nuclei only dust emission is considered. These dusty tori have physical sizes smaller than 6 pc radius, as derived from our fits. Unification schemes of AGN account for a variety of observational differences in terms of viewing geometry. However, we find evidence that strong unification may not hold and that the immediate dusty surroundings of Type-1 and Type-2 Seyfert nuclei are intrinsically different. The Type-2 tori studied here are broader, have more clumps, and these clumps have lower optical depths than those of Type-1 tori. The larger the covering factor of the torus, the smaller the probability of having a direct view of the AGN, and vice versa. In our sample, Seyfert 2 tori have larger covering factors (C{sub T} = 0.95 {+-} 0.02) and smaller escape probabilities (P{sub esc} = 0.05% {+-} {sup 0.08}{sub 0.03}%) than those of Seyfert 1 (C{sub T} = 0.5 {+-} 0.1; P{sub esc} = 18% {+-} 3%). All the previous differences are significant according to the Kullback-Leibler divergence. Thus, on the basis of the results presented here, the classification of a Seyfert galaxy as a Type-1 or Type-2 depends more on the intrinsic properties of the torus rather than on its mere inclination toward us, in contradiction with the simplest unification model.

  8. Background information on RSO Test Deeming Guidance

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

    information on RSO Test Deeming Guidance BPA has now had over two years of experience implementing Slice under the Regional Dialogue contract. Slice product customers are required...

  9. Nevada Test Site Waste Acceptance Criteria

    SciTech Connect (OSTI)

    U.S. Department of Energy, Nevada Operations Office, Waste Acceptance Criteria

    1999-05-01T23:59:59.000Z

    This document provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the Nevada Test Site.

  10. Sandia Inverter Performance Test Protocol Efficiency Weighting

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

    products having been tested to meet CEC incentive requirements, in 2014 a large number of inverters have publically-reported test results at three DC voltages and six power levels...

  11. BER Science Network Requirements

    SciTech Connect (OSTI)

    Dart, Eli; Tierney, Brian

    2010-11-01T23:59:59.000Z

    The Energy Sciences Network (ESnet) is the primary provider of network connectivity for the US Department of Energy Office of Science, the single largest supporter of basic research in the physical sciences in the United States. In support of the Office of Science programs, ESnet regularly updates and refreshes its understanding of the networking requirements of the instruments, facilities, scientists, and science programs that it serves. This focus has helped ESnet to be a highly successful enabler of scientific discovery for over 20 years. In April 2010 ESnet and the Office of Biological and Environmental Research, of the DOE Office of Science, organized a workshop to characterize the networking requirements of the science programs funded by BER. The requirements identified at the workshop are summarized and described in more detail in the case studies and the Findings section. A number of common themes emerged from the case studies and workshop discussions. One is that BER science, like many other disciplines, is becoming more and more distributed and collaborative in nature. Another common theme is that data set sizes are exploding. Climate Science in particular is on the verge of needing to manage exabytes of data, and Genomics is on the verge of a huge paradigm shift in the number of sites with sequencers and the amount of sequencer data being generated.

  12. HEV Fleet Testing Advanced Vehicle Testing Activities - 2010...

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

    DU5A0006063 Date Mileage Description Cost 8192009 5,090 Changed oil and filter and rotated tires 39.28 9162009 14,484 Changed oil and filter and replaced flat tire 152.58 10...

  13. Advanced Vehicle Testing Activity (AVTA) - Vehicle Testing and...

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

    Program: Pat Davis, Lee Slezak, Dave Howell http:avt.inl.gov or http:www1.eere.energy.govvehiclesandfuelsavta Additional Information INLCON-09-15561 Acknowledgement...

  14. Advanced Vehicle Testing Activity (AVTA) - Vehicle Testing and

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China 2015ofDepartmentDepartment of2Partners in the SpotlightEnergy

  15. Nevada Test Site Environmental Report Summary 2009

    SciTech Connect (OSTI)

    Cathy Wills, ed.

    2010-09-13T23:59:59.000Z

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada Test Site (NTS). NNSA/NSO prepares the Nevada Test Site Environmental Report (NTSER) to provide the public an understanding of the environmental monitoring and compliance activities that are conducted on the NTS to protect the public and the environment from radiation hazards and from nonradiological impacts. The NTSER is a comprehensive report of environmental activities performed at the NTS and offsite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. This summary provides an abbreviated and more readable version of the NTSER. It does not contain detailed descriptions or presentations of monitoring designs, data collection methods, data tables, the NTS environment, or all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

  16. Siphon breaker design requirements

    SciTech Connect (OSTI)

    Neill, D.T.; Stephens, A.G.

    1990-01-01T23:59:59.000Z

    This project was intended to provide experimental data on siphon flow effects. The system was to be modeled with the RELAP code and the predicted and measured performances compared. The experimental system consists of a 500-gallon upper tank, a 4-inch downcomer pipe, a lower catch tank, a return pump and associated piping. The downcomer pipe is made of 4-inch clear acrylic pipe so the flow patterns could be observed and video taped during the test runs.

  17. Radioisotope Thermoelectric Generator Transportation System licensed hardware second certification test series and package shock mount system test

    SciTech Connect (OSTI)

    Ferrell, P.C.; Moody, D.A. [Westinghouse Hanford Company, P.O. Box 1970, Richland, Washington 99352 (United States)

    1996-03-01T23:59:59.000Z

    This paper presents a summary of two separate drop test activities that were performed in support of the Radioisotope Thermoelectric Generator (RTG) Transportation System (RTGTS). The first portion of this paper presents the second series of drop testing required to demonstrate that the RTG package design meets the requirements of {ital Title} 10, {ital Code} {ital of} {ital Federal} {ital Regulations}, {open_quote}{open_quote}Part 71{close_quote}{close_quote} (10 CFR 71). Results of the first test series, performed in July 1994, demonstrated that some design changes were necessary. The package design was modified to improve test performance and the design changes were incorporated into the Safety Analysis Report for Packaging (SARP). The second full-size certification test article (CTA-2) incorporated the modified design and was tested at the U.S. Department of Energy{close_quote}s (DOE) Hanford Site near Richland, Washington. With the successful completion of the test series, and pending DOE Office of Facility Safety Analysis approval of the SARP, a certificate of compliance will be issued for the RTG package allowing its use. The second portion of this paper presents the design and testing of the RTG Package Mount System. The RTG package mount was designed to protect the RTG from excessive vibration during transport, provide shock protection during on/off loading, and provide a mechanism for moving the RTG package with a forklift. Military Standard (MIL-STD) 810E, {ital Transit} {ital Drop} {ital Procedure} (DOE 1989), was used to verify that the shock limiting system limited accelerations in excess of 15 G{close_quote}s at frequencies below 150 Hz. Results of the package mount drop tests indicate that an impact force of 15 G{close_quote}s was not exceeded in any test from a free drop height of 457 mm (18 in.). {copyright} {ital 1996 American Institute of Physics.}

  18. DOE nuclear material packaging manual: storage container requirements for plutonium oxide materials

    SciTech Connect (OSTI)

    Veirs, D Kirk [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

    Loss of containment of nuclear material stored in containers such as food-pack cans, paint cans, or taped slip lid cans has generated concern about packaging requirements for interim storage of nuclear materials in working facilities such as the plutonium facility at Los Alamos National Laboratory (LANL). In response, DOE has recently issued DOE M 441.1 'Nuclear Material Packaging Manual' with encouragement from the Defense Nuclear Facilities Safety Board. A unique feature compared to transportation containers is the allowance of filters to vent flammable gases during storage. Defining commonly used concepts such as maximum allowable working pressure and He leak rate criteria become problematic when considering vented containers. Los Alamos has developed a set of container requirements that are in compliance with 441.1 based upon the activity of heat-source plutonium (90% Pu-238) oxide, which bounds the requirements for weapons-grade plutonium oxide. The pre and post drop-test He leak rates depend upon container size as well as the material contents. For containers that are routinely handled, ease of handling and weight are a major consideration. Relatively thin-walled containers with flat bottoms are desired yet they cannot be He leak tested at a differential pressure of one atmosphere due to the potential for plastic deformation of the flat bottom during testing. The He leak rates and He leak testing configuration for containers designed for plutonium bearing materials will be presented. The approach to meeting the other manual requirements such as corrosion and thermal degradation resistance will be addressed. The information presented can be used by other sites to evaluate if their conditions are bounded by LANL requirements when considering procurement of 441.1 compliant containers.

  19. Requirements for Predictive Analytics

    SciTech Connect (OSTI)

    Troy Hiltbrand

    2012-03-01T23:59:59.000Z

    It is important to have a clear understanding of how traditional Business Intelligence (BI) and analytics are different and how they fit together in optimizing organizational decision making. With tradition BI, activities are focused primarily on providing context to enhance a known set of information through aggregation, data cleansing and delivery mechanisms. As these organizations mature their BI ecosystems, they achieve a clearer picture of the key performance indicators signaling the relative health of their operations. Organizations that embark on activities surrounding predictive analytics and data mining go beyond simply presenting the data in a manner that will allow decisions makers to have a complete context around the information. These organizations generate models based on known information and then apply other organizational data against these models to reveal unknown information.

  20. Standardization of Solar Mirror Reflectance Measurements - Round Robin Test: Preprint

    SciTech Connect (OSTI)

    Meyen, S.; Lupfert, E.; Fernandez-Garcia, A.; Kennedy, C.

    2010-10-01T23:59:59.000Z

    Within the SolarPaces Task III standardization activities, DLR, CIEMAT, and NREL have concentrated on optimizing the procedure to measure the reflectance of solar mirrors. From this work, the laboratories have developed a clear definition of the method and requirements needed of commercial instruments for reliable reflectance results. A round robin test was performed between the three laboratories with samples that represent all of the commercial solar mirrors currently available for concentrating solar power (CSP) applications. The results show surprisingly large differences in hemispherical reflectance (sh) of 0.007 and specular reflectance (ss) of 0.004 between the laboratories. These differences indicate the importance of minimum instrument requirements and standardized procedures. Based on these results, the optimal procedure will be formulated and validated with a new round robin test in which a better accuracy is expected. Improved instruments and reference standards are needed to reach the necessary accuracy for cost and efficiency calculations.

  1. BES Science Network Requirements

    SciTech Connect (OSTI)

    Dart, Eli; Tierney, Brian; Dart, Eli; Biocca, A.; Carlson, R.; Chen, J.; Cotter, S.; Dattoria, V.; Davenport, J.; Gaenko, A.; Kent, P.; Lamm, M.; Miller, S.; Mundy, C.; Ndousse, T.; Pederson, M.; Perazzo, A.; Popescu, R.; Rouson, D.; Sekine, Y.; Sumpter, B.; Wang, C.-Z.; Whitelam, S.; Zurawski, J.

    2011-02-01T23:59:59.000Z

    The Energy Sciences Network (ESnet) is the primary provider of network connectivityfor the US Department of Energy Office of Science (SC), the single largest supporter of basic research in the physical sciences in the United States. In support of the Office ofScience programs, ESnet regularly updates and refreshes its understanding of the networking requirements of the instruments, facilities, scientists, and science programs that it serves. This focus has helped ESnet to be a highly successful enabler of scientific discovery for over 20 years.

  2. NERSC Requirements Workshop November

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Saleshttp://www.fnal.gov/directorate/nalcal/nalcal02_07_05_files/nalcal.gif Directorate - Events -ExascalemadeArchivalRequirements

  3. Requirements Review Reports

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements Recently ApprovedReliability TechnologyRenewalReportReportsJ.TO9Complex

  4. Documentation Requirements for Sensory Impairments

    E-Print Network [OSTI]

    Documentation Requirements for Sensory Impairments Vision and Hearing Students, faculty, staff documentation requirements: 1. Requirements of the PRACTITIONER: A) Ophthalmologists and optometrists of interest. C) Documentation must be typed, dated and signed by the evaluator and submitted to ODR

  5. Quantified maintainability requirements 

    E-Print Network [OSTI]

    Morris, Ronald Scott

    1968-01-01T23:59:59.000Z

    , the system developer anci supporter. The res- ponsibility of each witi', regard to maintainability and the equipment life cycle is discussed in the iollowing paragraphs. The life cycle of a sys+em consists of six distinct phases; (1, ) +he Concept Phase...EI- IIICOi&I- E"IUCOil- TACOil- TECOii- MECOII- Aviation Cnw?and Electronics Command Ilecnani eel Equi pE?ent Co?G&and ;lissi le Co?Emand Ilun1tions Command Tank-Automotive Co?mand Test-Evaluation Commanci ';!eapons Command AR!Iv I'IATERIEL COIR1...

  6. ENVIRONMENTAL HEALTH SCIENCES Plan Requirements Campus: UMICH RG = Requirement Group

    E-Print Network [OSTI]

    Shyy, Wei

    ENVIRONMENTAL HEALTH SCIENCES Plan Requirements Campus: UMICH RG = Requirement Group Career: GPH RQ = Requirement Program: 01848 LN = Line Plan: 3200MPH RG 5298 ENVIRONMENTAL HEALTH SCIENCES REQUIREMENTS, 643, 653, 675, 677 or 695 LN 0030 - Environmental Health Sciences: EHS 501, 506, 507 or 508 LN 0040

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

    SciTech Connect (OSTI)

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

    1997-06-01T23:59:59.000Z

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

  8. Plan for decommissioning the Tokamak Fusion Test Reactor

    SciTech Connect (OSTI)

    Spampinato, P.T.; Walton, G.R. [Princeton Univ., NJ (United States). Plasma Physics Lab.; Commander, J.C. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

    1993-12-31T23:59:59.000Z

    The Tokamak Fusion Test Reactor (TFTR) Project is in the planning phase of developing a decommissioning project. A Preliminary Decontamination and Decommissioning (D&D) Plan has been developed which provides a framework for the baseline approach, and the cost and schedule estimates. TFTR will become activated and contaminated with tritium after completion of the deuterium-tritium (D-T) experiments. Hence some of the D&D operations will require remote handling. It is expected that all of the waste generated will be low level radioactive waste (LLW). The objective of the D&D Project is to make TFTR Test Cell available for use by a new fusion experiment. This paper discusses the D&D objectives, the facility to be decommissioned, estimates of activation, the technical (baseline) approach, and the assumptions used to develop cost and schedule estimates.

  9. Plan for decommissioning the Tokamak Fusion Test Reactor

    SciTech Connect (OSTI)

    Spampinato, P.T.; Walton, G.R. (Princeton Univ., NJ (United States). Plasma Physics Lab.); Commander, J.C. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

    1993-01-01T23:59:59.000Z

    The Tokamak Fusion Test Reactor (TFTR) Project is in the planning phase of developing a decommissioning project. A Preliminary Decontamination and Decommissioning (D D) Plan has been developed which provides a framework for the baseline approach, and the cost and schedule estimates. TFTR will become activated and contaminated with tritium after completion of the deuterium-tritium (D-T) experiments. Hence some of the D D operations will require remote handling. It is expected that all of the waste generated will be low level radioactive waste (LLW). The objective of the D D Project is to make TFTR Test Cell available for use by a new fusion experiment. This paper discusses the D D objectives, the facility to be decommissioned, estimates of activation, the technical (baseline) approach, and the assumptions used to develop cost and schedule estimates.

  10. Advanced Vehicle Testing Activity (AVTA) ? PHEV Evaluations...

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

    fuel economy per trip (mpg) CD only dist CD CS dist CS only dist 38 FY08 EnergyCS Joint Data Collection * EnergyCS provided onboard data for seven vehicles operating in...

  11. Recommended Underground Test Area Activity Reference Documents

    National Nuclear Security Administration (NNSA)

    Site, Nevada, DOENV--478-Rev. 1, July 1999. (15033) o Addendum, CAIP for CAU98, June, 2001, DOENV-478, Rev.1-ADD (789217) o Corrective Action Investigation Plan for Corrective...

  12. Recommended Underground Test Area Activity Reference Documents

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C1

  13. Standard test method for creep-fatigue testing

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2009-01-01T23:59:59.000Z

    1.1 This test method covers the determination of mechanical properties pertaining to creep-fatigue deformation or crack formation in nominally homogeneous materials, or both by the use of test specimens subjected to uniaxial forces under isothermal conditions. It concerns fatigue testing at strain rates or with cycles involving sufficiently long hold times to be responsible for the cyclic deformation response and cycles to crack formation to be affected by creep (and oxidation). It is intended as a test method for fatigue testing performed in support of such activities as materials research and development, mechanical design, process and quality control, product performance, and failure analysis. The cyclic conditions responsible for creep-fatigue deformation and cracking vary with material and with temperature for a given material. 1.2 The use of this test method is limited to specimens and does not cover testing of full-scale components, structures, or consumer products. 1.3 This test method is primarily ...

  14. LCLS Undulator Test Plan

    SciTech Connect (OSTI)

    Wolf, Zachary

    2010-11-24T23:59:59.000Z

    This note presents the test plan for the LCLS undulators. The undulators will be measured and tuned in the Magnetic Measurement Facility at SLAC. The requirements for tuning are well established and are summarized. A brief discussion of the measurement equipment is presented. This is followed by the detailed test plan in which each step is enumerated. Finally, the measurement results and storage format are presented. The LCLS consists of 33 undulator segments, hereafter referred to as undulators, plus 6 spares and one reference undulator. The undulators must be tuned to meet strict requirements. They must also be fiducialized to allow alignment with other components. This note details the plan for tuning and fiducializing the LCLS undulators. The note begins with the list of tuning and fiducialization requirements. The laboratory in which the work will be performed and the relevant equipment is then briefly described. This is followed by a detailed test plan in which all the steps of tuning and fiducialization are enumerated.

  15. Equipment Operational Requirements

    SciTech Connect (OSTI)

    Greenwalt, B; Henderer, B; Hibbard, W; Mercer, M

    2009-06-11T23:59:59.000Z

    The Iraq Department of Border Enforcement is rich in personnel, but poor in equipment. An effective border control system must include detection, discrimination, decision, tracking and interdiction, capture, identification, and disposition. An equipment solution that addresses only a part of this will not succeed, likewise equipment by itself is not the answer without considering the personnel and how they would employ the equipment. The solution should take advantage of the existing in-place system and address all of the critical functions. The solutions are envisioned as being implemented in a phased manner, where Solution 1 is followed by Solution 2 and eventually by Solution 3. This allows adequate time for training and gaining operational experience for successively more complex equipment. Detailed descriptions of the components follow the solution descriptions. Solution 1 - This solution is based on changes to CONOPs, and does not have a technology component. It consists of observers at the forts and annexes, forward patrols along the swamp edge, in depth patrols approximately 10 kilometers inland from the swamp, and checkpoints on major roads. Solution 2 - This solution adds a ground sensor array to the Solution 1 system. Solution 3 - This solution is based around installing a radar/video camera system on each fort. It employs the CONOPS from Solution 1, but uses minimal ground sensors deployed only in areas with poor radar/video camera coverage (such as canals and streams shielded by vegetation), or by roads covered by radar but outside the range of the radar associated cameras. This document provides broad operational requirements for major equipment components along with sufficient operational details to allow the technical community to identify potential hardware candidates. Continuing analysis will develop quantities required and more detailed tactics, techniques, and procedures.

  16. Operational test report for LERF Basin 242AL-44 integrity test

    SciTech Connect (OSTI)

    Galioto, T.M.

    1994-11-08T23:59:59.000Z

    This operational test report documents the results of LERF operational testing per operational test procedure (OTP) TFPE-WP-0231, ``LERF Basin Integrity Testing.`` The primary purpose of the OTP was to resolve test exceptions generated as a result of TFPE-WP-0184. The TOP was prepared and performed in accordance with WHC-SD-534-OTP-002, ``Operational Test Plan for the 242-A Evaporator Upgrades and the Liquid Effluent Retention Facility.`` WHC-S-086, ``Specification for Operational Testing of the Liquid Effluent Retention Facility, Basin Integrity Testing,`` identified the test requirements and acceptance criteria. The completed, signed-off test procedure is contained in Appendix A. The test log is contained in Appendix B. Section 2.1 describes all the test exceptions written during performance of the Operational Test Procedure. The test revisions generated during the testing are discussed in Section 2.2. The dispositioned test exception forms are contained in Appendix C.

  17. Test Comparability

    E-Print Network [OSTI]

    Keller, Christine; Shulenburger, David E.

    2010-01-01T23:59:59.000Z

    KU ScholarWorks | http://kuscholarworks.ku.edu Test Comparability 2010 by Christine Keller and David Shulenburger This work has been made available by the University of Kansas Libraries’ Office of Scholarly Communication and Copyright. Please... and Shulenburger, David. “Test comparability,” with Christine Keller in the Letters section of Change, September/October 2010, p. 6. Published version: http://www.changemag.org/Archives/Back%20 Issues/September-October%202010/letters-to-editor.html Terms of Use...

  18. Test Automation Ant JUnit Test Automation

    E-Print Network [OSTI]

    Mousavi, Mohammad

    Test Automation Ant JUnit Test Automation Mohammad Mousavi Eindhoven University of Technology, The Netherlands Software Testing 2012 Mousavi: Test Automation #12;Test Automation Ant JUnit Outline Test Automation Ant JUnit Mousavi: Test Automation #12;Test Automation Ant JUnit Why? Challenges of Manual Testing

  19. ENGINEERING PHYSICS BSE Plan Requirements

    E-Print Network [OSTI]

    Shyy, Wei

    ENGINEERING PHYSICS BSE Plan Requirements 1 Campus: UMICH RG = Requirement Group Career: UENG RQ = Requirement Program: LN = Line Plan: 2990BSE RG 6394 ENGINEERING PHYSICS MAJOR REQUIREMENTS Effective FA12/1910 (09/04/2012) RQ 4925 Physics Technical Subjects (C or higher) Effective FA12/1910 (09/04/2012) LN 0010

  20. SemTrace: Semantic Requirements Tracing Using Explicit Requirement Knowledge

    E-Print Network [OSTI]

    their activities. Application Lifecycle Management (ALM) is the coordination of development lifecycle activities knowledge and artifacts. A major challenge in distributed software development is the integration of activities along the development lifecycle. Application Lifecycle Management (ALM) is defined as "the

  1. AVTA: Battery Testing - DC Fast Charging's Effects on PEV Batteries...

    Energy Savers [EERE]

    DC Fast Charging's Effects on PEV Batteries AVTA: Battery Testing - DC Fast Charging's Effects on PEV Batteries The Vehicle Technologies Office's Advanced Vehicle Testing Activity...

  2. Geodetic Survey At Nevada Test And Training Range Area (Sabin...

    Open Energy Info (EERE)

    Nevada Test And Training Range Area (Sabin, Et Al., 2004) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Geodetic Survey At Nevada Test And...

  3. Geothermometry At Nevada Test And Training Range Area (Sabin...

    Open Energy Info (EERE)

    Nevada Test And Training Range Area (Sabin, Et Al., 2004) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Geothermometry At Nevada Test And...

  4. SOA1: Geomaterial Behaviour and Testing

    E-Print Network [OSTI]

    Mayne, Paul W.

    Behaviour & Testing 17th ICSMGE, Alexandria, Egypt #12;10/21/2009 2 SOA1: Geomaterial Behaviour & Testing, Alexandria, Egypt #12;10/21/2009 3 SOA1: Geomaterial Behaviour & Testing Sarah M. Springman · Active (2009) SOA-1 Geomaterial Behaviour & Testing 17th ICSMGE, Alexandria, Egypt #12;10/21/2009 4 SOA1

  5. A mathematical model for countercurrent moving-bed activated carbon adsorption

    E-Print Network [OSTI]

    Anderson, Douglas Harold

    1976-01-01T23:59:59.000Z

    the column. There was insufficient data taken to verify this model. The testing procedure was limited by the approximate uniformity of the influent concentrations in the pilot plant and the effect of the activated carbon concentration and initial solute...A MATHEMATICAL MODEL FOR COUNTERCURRENT MOVING-BED ACTIVATED CARBON ADSORPTION A Thesis by DOUGLAS HAROLD ANDERSON Submitted to the Graduate College of Texas ASM University in partial fulfillment of the requirement for the degree of MASTER...

  6. Nevada Test Site Environmental Report 2009

    SciTech Connect (OSTI)

    Cathy Wills, ed.

    2010-09-13T23:59:59.000Z

    The Nevada Test Site Environmental Report 2009 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ Nevada Test Site Environmental Reports (NTSERs) are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx. This NTSER was prepared to satisfy DOE Order DOE O 231.1A, “Environment, Safety and Health Reporting.” Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NNSA/NSO Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NTSER summarizes data and compliance status for calendar year 2009 at the Nevada Test Site (NTS) and its two support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory (RSL)-Nellis. It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR). Through a Memorandum of Agreement, NNSA/NSO is responsible for the oversight of TTR ER projects, and the Sandia Site Office of NNSA (NNSA/SSO) has oversight of all other TTR activities. NNSA/SSO produces the TTR annual environmental report available at http://www.sandia.gov/news/publications/environmental/index.html.

  7. Optical durability testing of candidate solar mirrors

    SciTech Connect (OSTI)

    Jorgensen, G.; Kennedy, C.; King, D.; Terwilliger, K.

    2000-03-24T23:59:59.000Z

    Durability testing of a variety of candidate solar reflector materials at outdoor test sites and in laboratory accelerated weathering chambers is the main activity within the Advanced Materials task of the Concentrated Solar Power (CSP) Program. Outdoor exposure testing (OET) at up to eight outdoor, worldwide exposure sites has been underway for several years. This includes collaboration under the auspices of the International Energy Agency (IEA) Solar Power and Chemical Energy Systems (SolarPACES) agreement. Outdoor sites are fully instrumented in terms of monitoring meteorological conditions and solar irradiance. Candidate materials are optically characterized prior to being subjected to exposure in real and simulated weathering environments. Optical durability is quantified by periodically re-measuring hemispherical and specular reflectance as a function of exposure time. By closely monitoring the site- and time-dependent environmental stress conditions experienced by the material samples, site-dependent loss of performance may be quantified. In addition, accelerated exposure testing (AET) of these materials in parallel under laboratory-controlled conditions may permit correlating the outdoor results with AET, and subsequently predicting service lifetimes. Test results to date for a large number of candidate solar reflector materials are presented in this report. Acronyms are defined. Based upon OET and AET results to date, conclusions can be drawn about the optical durability of the candidate reflector materials. The optical durability of thin glass, thick glass, and two metallized polymers can be characterized as excellent. The all-polymeric construction, several of the aluminized reflectors, and a metallized polymer can be characterized as having intermediate durability and require further improvement, testing and evaluation, or both.

  8. Flow Test At Blue Mountain Geothermal Area (Fairbank Engineering...

    Open Energy Info (EERE)

    Activity Details Location Blue Mountain Geothermal Area Exploration Technique Flow Test Activity Date 2002 - 2002 Usefulness not useful DOE-funding Unknown Exploration Basis...

  9. Injectivity Test At Long Valley Caldera Geothermal Area (Morin...

    Open Energy Info (EERE)

    navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Injectivity Test At Long Valley Caldera Geothermal Area (Morin, Et Al., 1993) Exploration Activity...

  10. Modeling-Computer Simulations At Nevada Test And Training Range...

    Open Energy Info (EERE)

    ENERGYGeothermal Home Exploration Activity: Modeling-Computer Simulations At Nevada Test And Training Range Area (Sabin, Et Al., 2004) Exploration Activity Details Location...

  11. Aerial Photography At Nevada Test And Training Range Area (Sabin...

    Open Energy Info (EERE)

    GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Aerial Photography At Nevada Test And Training Range Area (Sabin, Et Al., 2004) Exploration Activity Details Location...

  12. Application of Reinforcement Learning to Requirements Engineering: Requirements Tracing

    E-Print Network [OSTI]

    Hayes, Jane E.

    of the Software Development Life Cycle (SDLC) can be appreciated by the customers who request and expect delivery the phases of the SDLC, a number of steps can be taken. Requirements tracing ensures that requirements

  13. Duct Tape Durability Testing

    SciTech Connect (OSTI)

    Sherman, Max H.; Walker, Iain S.

    2004-04-01T23:59:59.000Z

    Duct leakage is a major source of energy loss in residential buildings. Most duct leakage occurs at the connections to registers, plenums, or branches in the duct system. At each of these connections, a method of sealing the duct system is required. Typical sealing methods include tapes or mastics applied around the joints in the system. Field examinations of duct systems have shown that taped seals tend to fail over extended periods of time. The Lawrence Berkeley National Laboratory (LBNL) has been testing sealant durability for several years using accelerated test methods and found that typical duct tape (i.e., cloth-backed tapes with natural rubber adhesives) fails more rapidly than other duct sealants. This report summarizes the results of duct sealant durability testing over two years for four UL 181B-FX listed duct tapes (two cloth tapes, a foil tape and an Oriented Polypropylene (OPP) tape). One of the cloth tapes was specifically developed in collaboration with a tape manufacturer to perform better in our durability testing. The tests involved the aging of common ''core-to-collar joints'' of flexible duct to sheet metal collars. Periodic air leakage tests and visual inspection were used to document changes in sealant performance. After two years of testing, the flex-to-collar connections showed little change in air leakage, but substantial visual degradation from some products. A surprising experimental result was failure of most of the clamps used to mechanically fasten the connections. This indicates that the durability of clamps also need to be addressed ensure longevity of the duct connection. An accelerated test method developed during this study has been used as the basis for an ASTM standard (E2342-03).

  14. Light Duty Utility Arm system pre-operational (cold test) test plan

    SciTech Connect (OSTI)

    Bennett, K.L.

    1995-10-20T23:59:59.000Z

    The Light Duty Utility (LDUA) Cold Test Facility, located in the Hanford 400 Area, will be used to support cold testing (pre- operational tests) of LDUA subsystems. Pre-operational testing is composed of subsystem development testing and rework activities, and integrated system qualification testing. Qualification testing will be conducted once development work is complete and documentation is under configuration control. Operational (hot) testing of the LDUA system will follow the testing covered in this plan and will be covered in a separate test plan

  15. Fluid-Bed Testing of Greatpoint Energy's Direct Oxygen Injection Catalytic Gasification Process for Synthetic Natural Gas and Hydrogen Coproduction Year 6 - Activity 1.14 - Development of a National Center for Hydrogen Technology

    SciTech Connect (OSTI)

    Swanson, Michael; Henderson, Ann

    2012-04-01T23:59:59.000Z

    The GreatPoint Energy (GPE) concept for producing synthetic natural gas and hydrogen from coal involves the catalytic gasification of coal and carbon. GPE’s technology “refines” coal by employing a novel catalyst to “crack” the carbon bonds and transform the coal into cleanburning methane (natural gas) and hydrogen. The GPE mild “catalytic” gasifier design and operating conditions result in reactor components that are less expensive and produce pipeline-grade methane and relatively high purity hydrogen. The system operates extremely efficiently on very low cost carbon sources such as lignites, subbituminous coals, tar sands, petcoke, and petroleum residual oil. In addition, GPE’s catalytic coal gasification process eliminates troublesome ash removal and slagging problems, reduces maintenance requirements, and increases thermal efficiency, significantly reducing the size of the air separation plant (a system that alone accounts for 20% of the capital cost of most gasification systems) in the catalytic gasification process. Energy & Environmental Research Center (EERC) pilot-scale gasification facilities were used to demonstrate how coal and catalyst are fed into a fluid-bed reactor with pressurized steam and a small amount of oxygen to “fluidize” the mixture and ensure constant contact between the catalyst and the carbon particles. In this environment, the catalyst facilitates multiple chemical reactions between the carbon and the steam on the surface of the coal. These reactions generate a mixture of predominantly methane, hydrogen, and carbon dioxide. Product gases from the process are sent to a gas-cleaning system where CO{sub 2} and other contaminants are removed. In a full-scale system, catalyst would be recovered from the bottom of the gasifier and recycled back into the fluid-bed reactor. The by-products (such as sulfur, nitrogen, and CO{sub 2}) would be captured and could be sold to the chemicals and petroleum industries, resulting in near-zero hazardous air or water pollution. This technology would also be conducive to the efficient coproduction of methane and hydrogen while also generating a relatively pure CO{sub 2} stream suitable for enhanced oil recovery (EOR) or sequestration. Specific results of bench-scale testing in the 4- to 38-lb/hr range in the EERC pilot system demonstrated high methane yields approaching 15 mol%, with high hydrogen yields approaching 50%. This was compared to an existing catalytic gasification model developed by GPE for its process. Long-term operation was demonstrated on both Powder River Basin subbituminous coal and on petcoke feedstocks utilizing oxygen injection without creating significant bed agglomeration. Carbon conversion was greater than 80% while operating at temperatures less than 1400°F, even with the shorter-than-desired reactor height. Initial designs for the GPE gasification concept called for a height that could not be accommodated by the EERC pilot facility. More gas-phase residence time should allow the syngas to be converted even more to methane. Another goal of producing significant quantities of highly concentrated catalyzed char for catalyst recovery and material handling studies was also successful. A Pd–Cu membrane was also successfully tested and demonstrated to produce 2.54 lb/day of hydrogen permeate, exceeding the desired hydrogen permeate production rate of 2.0 lb/day while being tested on actual coal-derived syngas that had been cleaned with advanced warm-gas cleanup systems. The membranes did not appear to suffer any performance degradation after exposure to the cleaned, warm syngas over a nominal 100-hour test.

  16. Lawrence Berkeley National Laboratory Arboricultural Operations Safety Requirements LBNL Arboricultural Operation Safety Requirements

    E-Print Network [OSTI]

    Eisen, Michael

    Lawrence Berkeley National Laboratory Arboricultural Operations Safety Requirements 1 of 3 LBNL reviewed with LBNL Facilities Electric Shop (6023)? * IF THE ANSWER TO 3E WAS NO, STOP THIS WORK ACTIVITY AND CONTACT FACILITIES ELECTRIC SHOP a. Name of LBNL individual consulted? #12;LBNL Arboricultural Operations

  17. Verifying Test Hypotheses -HOL/TestGen Verifying Test Hypotheses -HOL/TestGen

    E-Print Network [OSTI]

    Verifying Test Hypotheses - HOL/TestGen Verifying Test Hypotheses - HOL/TestGen An Experiment in Test and Proof Thomas Malcher January 20, 2014 1 / 20 #12;Verifying Test Hypotheses - HOL/TestGen HOL/TestGen Outline Introduction Test Hypotheses HOL/TestGen - Demo Verifying Test Hypotheses Conclusion 2 / 20 #12

  18. Webinar: Hydrogen Storage Materials Requirements

    Broader source: Energy.gov [DOE]

    Video recording and text version of the webinar titled, Hydrogen Storage Materials Requirements, originally presented on June 25, 2013.

  19. Nonproliferation Test and Evaluation Complex - NPTEC

    ScienceCinema (OSTI)

    None

    2015-01-09T23:59:59.000Z

    The Nonproliferation Test and Evaluation Complex, or NPTEC, is the world's largest facility for open air testing of hazardous toxic materials and biological simulants. NPTEC is used for testing, experimentation, and training for technologies that require the release of toxic chemicals or biological simulants into the environment.

  20. Nonproliferation Test and Evaluation Complex - NPTEC

    SciTech Connect (OSTI)

    None

    2014-11-10T23:59:59.000Z

    The Nonproliferation Test and Evaluation Complex, or NPTEC, is the world's largest facility for open air testing of hazardous toxic materials and biological simulants. NPTEC is used for testing, experimentation, and training for technologies that require the release of toxic chemicals or biological simulants into the environment.

  1. GEOCHEMICAL TESTING AND MODEL DEVELOPMENT - RESIDUAL TANK WASTE TEST PLAN

    SciTech Connect (OSTI)

    CANTRELL KJ; CONNELLY MP

    2010-03-09T23:59:59.000Z

    This Test Plan describes the testing and chemical analyses release rate studies on tank residual samples collected following the retrieval of waste from the tank. This work will provide the data required to develop a contaminant release model for the tank residuals from both sludge and salt cake single-shell tanks. The data are intended for use in the long-term performance assessment and conceptual model development.

  2. activity energy requirements: Topics by E-print Network

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

    by our parametrization lies beyond the 3 sigma contour for constraints from all the data sets. Sheng Wang; Lam Hui; Morgan May; Zoltan Haiman 2007-10-16 108 Developing "MOU...

  3. activation requires lipid: Topics by E-print Network

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

    Microalgae have presented themselves as a strong candidate to replace diminishing oil reserves as a source of lipids for biofuels. Here we describe successful modifications...

  4. active process requiring: Topics by E-print Network

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

    allowing contractile ring disassembly and completion of cytokinesis. Verena Jantsch-plunger; Pierre Gnczy; Alper Romano; Heinke Schnabel; Danielle Hamill; Ralf Schnabel;...

  5. Simulating Lunar Habitats and Activities to Derive System Requirements

    E-Print Network [OSTI]

    Kortenkamp, David

    crops), water recovery, air revitalization, food processing, solid waste recycling and energy production Johnson Space Center/Metrica Inc., Houston, Texas, 77058, USA Scott Bell NASA Johnson Space Center/SKT Inc., Houston, Texas, 77058, USA Luis Rodriguez NASA Johnson Space Center/USRA, Houston, Texas, 77058, USA

  6. Defect classes - an overdue paradigm for CMOS IC testing

    SciTech Connect (OSTI)

    Hawkins, C.F. [Univ. of New Mexico, Albuquerque, NM (United States); Soden, J.M.; Righter, A.W. [Sandia National Labs., Albuquerque, NM (United States); Ferguson, F.J. [Univ. of California, Santa Cruz, CA (United States)

    1994-09-01T23:59:59.000Z

    The IC test industry has struggled for more than 30 years to establish a test approach that would guarantee a low defect level to the customer. We propose a comprehensive strategy for testing CMOS ICs that uses defect classes based on measured defect electrical properties. Defect classes differ from traditional fault models. Our defect class approach requires that the test strategy match the defect electrical properties, while fault models require that IC defects match the fault definition. We use data from Sandia Labs failure analysis and test facilities and from public literature. We describe test pattern requirements for each defect class and propose a test paradigm.

  7. Microgrid Testing

    SciTech Connect (OSTI)

    Shirazi, M.; Kroposki, B.

    2012-01-01T23:59:59.000Z

    With the publication of IEEE 1574.4 Guide for Design, Operation, and Integration of Distributed Resource Island Systems with Electric Power Systems, there is an increasing amount of attention on not only the design and operations of microgrids, but also on the proper operation and testing of these systems. This standard provides alternative approaches and good practices for the design, operation, and integration of microgrids. This includes the ability to separate from and reconnect to part of the utility grid while providing power to the islanded power system. This presentation addresses the industry need to develop standardized testing and evaluation procedures for microgrids in order to assure quality operation in the grid connected and islanded modes of operation.

  8. Advanced Control Design and Field Testing for Wind Turbines at the National Renewable Energy Laboratory: Preprint

    SciTech Connect (OSTI)

    Hand, M. M.; Johnson, K. E.; Fingersh, L. J.; Wright, A. D.

    2004-05-01T23:59:59.000Z

    Utility-scale wind turbines require active control systems to operate at variable rotational speeds. As turbines become larger and more flexible, advanced control algorithms become necessary to meet multiple objectives such as speed regulation, blade load mitigation, and mode stabilization. At the same time, they must maximize energy capture. The National Renewable Energy Laboratory has developed control design and testing capabilities to meet these growing challenges.

  9. Development of a propulsion system and component test facility for advanced radioisotope powered Mars Hopper platforms

    SciTech Connect (OSTI)

    Robert C. O'Brien; Nathan D. Jerred; Steven D. Howe

    2011-02-01T23:59:59.000Z

    Verification and validation of design and modeling activities for radioisotope powered Mars Hopper platforms undertaken at the Center for Space Nuclear Research is essential for proof of concept. Previous research at the center has driven the selection of advanced material combinations; some of which require specialized handling capabilities. The development of a closed and contained test facility to forward this research is discussed within this paper.

  10. Underground Test Area Quality Assurance Project Plan Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Irene Farnham

    2011-05-01T23:59:59.000Z

    This Quality Assurance Project Plan (QAPP) provides the overall quality assurance (QA) program requirements and general quality practices to be applied to the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Underground Test Area (UGTA) Sub-Project (hereafter the Sub-Project) activities. The requirements in this QAPP are consistent with DOE Order 414.1C, Quality Assurance (DOE, 2005); U.S. Environmental Protection Agency (EPA) Guidance for Quality Assurance Project Plans for Modeling (EPA, 2002); and EPA Guidance on the Development, Evaluation, and Application of Environmental Models (EPA, 2009). The QAPP Revision 0 supersedes DOE--341, Underground Test Area Quality Assurance Project Plan, Nevada Test Site, Nevada, Revision 4.

  11. Software Quality Assurance Subcommittee : Guidelines for Requirements...

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

    Software Quality Assurance Subcommittee : Guidelines for Requirements Management Software Quality Assurance Subcommittee : Guidelines for Requirements Management Requirements...

  12. AVTA: 2014 Chevrolet Cruze Diesel Vehicle Testing Reports

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. ...

  13. AVTA: 2012 Nissan Leaf All-Electric Vehicle Testing Reports

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. ...

  14. AVTA: 2013 Ford Fusion Energi PHEV Testing Results

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. ...

  15. AVTA: 2013 Ford C-Max Energi PHEV Testing Results

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road....

  16. AVTA: 2013 Ford Focus All-Electric Vehicle Testing Reports

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. ...

  17. Review of In-situ Fabrication Methods of Piezoelectric Wafer Active Sensor for Sensing and Actuation Applications

    E-Print Network [OSTI]

    Giurgiutiu, Victor

    1 Review of In-situ Fabrication Methods of Piezoelectric Wafer Active Sensor for Sensing-echo, and electromechanical impedance methods. Traditionally, structural integrity tests required attachment of sensors and magnitude of the surfaces measured (such as aircraft, bridges, structural supports, etc.). In addition

  18. Test plan : reducing soft costs of rooftop solar installations attributed to structural considerations.

    SciTech Connect (OSTI)

    Dwyer, Stephen F.

    2013-05-01T23:59:59.000Z

    This test plan is a document that provides a systematic approach to the planned testing of rooftop structures to determine their actual load carrying capacity. This document identifies typical tests to be performed, the responsible parties for testing, the general feature of the tests, the testing approach, test deliverables, testing schedule, monitoring requirements, and environmental and safety compliance.

  19. Nevada Test Site Radiation Protection Program - Revision 1

    SciTech Connect (OSTI)

    Radiological Control Managers' Council

    2008-06-01T23:59:59.000Z

    Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection,' establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada Test Site (NTS), related (on-site or off-site) U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration off-site projects. This NTS RPP promulgates the radiation protection standards, limits, and program requirements for occupational exposure to ionizing radiation resulting from NNSA/NSO activities at the NTS and other operational areas as stated in 10 CFR 835.1(a). NNSA/NSO activities (including design, construction, operation, and decommissioning) within the scope of this RPP may result in occupational exposures to radiation or radioactive material. Therefore, a system of control is implemented through specific references to the site-specific NV/YMP RCM. This system of control is intended to ensure that the following criteria are met: (1) occupational exposures are maintained as low as reasonably achievable (ALARA), (2) DOE's limiting values are not exceeded, (3) employees are aware of and are prepared to cope with emergency conditions, and (4) employees are not inadvertently exposed to radiation or radioactive material.

  20. Nissan Hypermini Urban Electric Vehicle Testing

    SciTech Connect (OSTI)

    James Francfort; Robert Brayer

    2006-01-01T23:59:59.000Z

    The U.S. Department of Energy’s (DOE’s) Advanced Vehicle Testing Activity (AVTA), which is part of DOE’s FreedomCAR and Vehicle Technologies Program, in partnership with the California cities of Vacaville and Palm Springs, collected mileage and maintenance and repairs data for a fleet of eleven Nissan Hypermini urban electric vehicles (UEVs). The eleven Hyperminis were deployed for various periods between January 2001 and June 2005. During the combined total of 439 months of use, the eleven Hyperminis were driven a total of 41,220 miles by staff from both cities. This equates to an average use of about 22 miles per week per vehicle. There were some early problems with the vehicles, including a charging problem and a need to upgrade the electrical system. In addition, six vehicles required drive system repairs. However, the repairs were all made under warranty. The Hyperminis were generally well-liked and provided drivers with the ability to travel any of the local roads. Full charging of the Hypermini’s lithiumion battery pack required up to 4 hours, with about 8–10 miles of range available for each hour of battery charging. With its right-side steering wheel, some accommodation of the drivers’ customary driving methods was required to adapt for different blind spots and vehicle manipulation. For that reason, the drivers received orientation and training before using the vehicle. The Hypermini is instrumented in kilometers rather than in miles, which required an adjustment for the drivers to calculate speed and range. As the drivers gained familiarity with the vehicles, there was increased acceptance and a preference for using it over traditional city vehicles. In all cases, the Hyperminis attracted a great amount of attention and interest from the general public.

  1. Fusion Energy Sciences Network Requirements

    E-Print Network [OSTI]

    Dart, Eli

    2014-01-01T23:59:59.000Z

    Division, and the Office of Fusion Energy Sciences. This isFusion Energy Sciences NetworkRequirements Office of Fusion Energy Sciences Energy

  2. RADIOACTIVE MATERIAL PACKAGING TORQUE REQUIREMENTS COMPLIANCE

    SciTech Connect (OSTI)

    Watkins, R.; Leduc, D.

    2011-03-24T23:59:59.000Z

    Shipping containers used to transport radioactive material (RAM) in commerce employ a variety of closure mechanisms. Often, these closure mechanisms require a specific amount of torque be applied to a bolt, nut or other threaded fastener. It is important that the required preload is achieved so that the package testing and analysis is not invalidated for the purpose of protecting the public. Torque compliance is a means of ensuring closure preload, is a major factor in accomplishing the package functions of confinement/containment, sub-criticality, and shielding. This paper will address the importance of applying proper torque to package closures, discuss torque value nomenclature, and present one methodology to ensure torque compliance is achieved.

  3. AVTA: 2010 Mercedes Benz HEV Testing Results

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. These results provide benchmark data that researchers can use to develop technology models and guide future research and development. The following reports describe results of testing done on a 2010 Mercedes Benz hybrid-electric vehicle. The baseline performance testing provides a point of comparison for the other test results. Taken together, these reports give an overall view of how this vehicle functions under extensive testing. This research was conducted by Idaho National Laboratory.

  4. AVTA: 2010 Quantum Escape PHEV Testing Results

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. These results provide benchmark data that researchers can use to develop technology models and guide future research and development. The following reports describe results of testing done on a 2010 Quantum Escape PHEV, an experimental model not currently for sale. The baseline performance testing provides a point of comparison for the other test results. Taken together, these reports give an overall view of how this vehicle functions under extensive testing. This research was conducted by Idaho National Laboratory.

  5. AVTA: 2011 Honda CRZ HEV Testing Results

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. These results provide benchmark data that researchers can use to develop technology models and guide future research and development. The following reports describe results of testing done on a 2011 Honda CRZ hybrid electric vehicle. The baseline performance testing provides a point of comparison for the other test results. Taken together, these reports give an overall view of how this vehicle functions under extensive testing. This research was conducted by Idaho National Laboratory.

  6. AVTA: 2011 Chevrolet Volt Testing Results

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. These results provide benchmark data that researchers can use to develop technology models and guide future research and development. The following reports describe results of testing done on a Chevrolet Volt 2011. The baseline performance testing provides a point of comparison for the other test results. Taken together, these reports give an overall view of how this vehicle functions under extensive testing. This research was conducted by Idaho National Laboratory.

  7. Prototype to Test WHY prototype to test

    E-Print Network [OSTI]

    Prinz, Friedrich B.

    Prototype to Test METHOD WHY prototype to test HOW to prototype to test Prototyping to test or design space. The fundamental way you test your prototypes is by letting users experience them and react to them. In creating prototypes to test with users you have the opportunity to examine your solution

  8. Animal Health Diagnostic Center Test and Fee Schedule Test Name Test Fee Discipline Test Days Lag** Samples Container Coolant Comments

    E-Print Network [OSTI]

    Keinan, Alon

    container; 2) slide mailer 1) Refrigerate. Ship in insulated container with ice pack. 2) Not required *May container 1-3) Refrigerate. Ship in insulated container with ice pack For more information, see Appendix in insulated container with ice pack. For more information, see Canine Adrenal & Pituitary Function Tests

  9. Calendar Year 2004 annual site environmental report : Tonopah Test Range, Nevada & Kauai Test Facility, Hawaii.

    SciTech Connect (OSTI)

    Montoya, Amber L.; Wagner, Katrina; Goering, Teresa Lynn; Koss, Susan I.; Salinas, Stephanie A.

    2005-09-01T23:59:59.000Z

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, manages TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2004. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2005) and DOE Order 231.1A, Environment, Safety, and Health Reporting (DOE 2004b).

  10. Requirements

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's PossibleRadiation Protection Technical s o Freiberge s 3 % A PB 2 7 7 2 x>16Forms of1, 2

  11. Soil Remediation Test

    SciTech Connect (OSTI)

    Manlapig, D. M.; Williamsws

    2002-04-01T23:59:59.000Z

    Soils contaminated with petroleum by-products can now be effectively remediated using a variety of technologies. Among these are in-situ bioremediation, land farming, and landfill/replacing of soil. The range of efficiencies and cost effectiveness of these technologies has been well documented. Exsorbet Plus is showing promise as an in-situ bioremediation agent. It is made of naturally grown Spaghnum Peat Moss which has been activated for encapsulation and blended with nitrogen-rich fertilizer. In its initial field test in Caracas, Venezuela, it was able to remediate crude oil-contaminated soil in 90 days at less than half of the cost of competing technologies. Waste Solutions, Corp and the US Department of Energy signed a Cooperative Research and Development Agreement to test Exsorbet Plus at the Rocky Mountain Oilfield Testing Center near Casper, Wyoming. As part of the test, soil contaminated with crude oil was treated with Exsorbet Plus to aid the in-situ bioremediation process. Quantitative total petroleum hydrocarbon (TPH) measurements were acquired comparing the performance of Exsorbet Plus with an adjacent plot undergoing unaided in-situ bioremediation.

  12. Hydrogen Storage Testing and Analysis R&D | Department of Energy

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

    DOE R&D Activities Hydrogen Storage Testing and Analysis R&D Hydrogen Storage Testing and Analysis R&D DOE's hydrogen storage R&D activities include testing, analysis, and...

  13. Thesis and Dissertation Required Elements

    E-Print Network [OSTI]

    Texas at Arlington, University of

    /dissertation documents have a uniform appearance and are suitable for archiving. The requirements follow the guidelines to the following guidelines are acceptable. · All margins must be at least 1.25" and may not be more than 1/dissertation should be double-spaced. #12;Thesis and Dissertation Required Elements 2012 version Paragraph Indentation

  14. Calibration Requirements and Procedures for

    E-Print Network [OSTI]

    Tuceryan, Mihran

    Calibration Requirements and Procedures for Augmented Reality Mihran Tuceryan Douglas S. Greer Ross Graphics, Sept 1995) Calibration Requirements and Procedures for Augmented Reality Mihran Tuceryan Douglas of calibration procedures are necessary so that the location and parameters of each of the system components

  15. MINIMUM SECURITY REQUIREMENTS FOR FEDERAL

    E-Print Network [OSTI]

    March 2006 MINIMUM SECURITY REQUIREMENTS FOR FEDERAL INFORMATION AND INFORMATION SYSTEMS: FEDERAL INFORMATION PROCESSING STANDARD (FIPS) 200 APPROVED BY THE SECRETARY OF COMMERCE MINIMUM SECURITY REQUIREMENTS BY THE SECRETARY OF COMMERCE Shirley Radack, EditorShirley Radack, Editor Computer Security Division

  16. Humidity requirements in WSCF Laboratories

    SciTech Connect (OSTI)

    Evans, R.A.

    1994-10-01T23:59:59.000Z

    The purpose of this paper is to develop and document a position on Relative Humidity (RH) requirements in the WSCF Laboratories. A current survey of equipment vendors for Organic, Inorganic and Radiochemical laboratories indicate that 25% - 80% relative humidity may meet the environmental requirements for safe operation and protection of all the laboratory equipment.

  17. Reduced-Enrichment Research and Test Reactor Program: Environmental assessment

    SciTech Connect (OSTI)

    Not Available

    1980-05-01T23:59:59.000Z

    The principal program objective and principal part of the proposed action is to improve the proliferation resistance of nuclear fuels used in research and test reactors by providing the technical means (through technical development, design, and testing) for reducing the uranium enrichment requirements of these fuels to substantially less than the 90 to 93% enrichment currently used. Operator acceptance of the reduced-enrichment-uranium (REU) fuel alternative will require minimizing of reactor performance reduction, fuel cycle cost increases, the number of new safety and licensing issues raised, and reactor and facility modifications. The other part of the proposed action is to assure the capability for commercial production and supply of REU fuel for use both in the US and abroad. The RERTR Program scope is limited to generic design studies, technical support to reactor operating organizations in preparing for conversions to REU fuels, fuel development, fuel demonstrations, and technical support for commercialization of REU fuels. This environmental assessment addresses the environmental consequences of RERTR Program activities and of specific conversions of typical reactors (the Ford Nuclear Reactor and one or two other to-be-designated demonstrations) to REU-fuel cycles, including domestic and international shipments of enriched uranium pertinent to the conduct of RERTR Program activities.

  18. 3. MATERIAL CERTIFICATIONS REQUIRED. 100% DYE PENETRANT INSPECTION REQUIRED.

    E-Print Network [OSTI]

    McDonald, Kirk

    WELDS SHOULD BE MINIMIZED. NO CODE STAMP REQUIRED. IN ACCORDANCE WITH ASME SECTION IX. 1. WELDING and applicable 1. ALL DIMENSIONS ARE IN INCHES 2. INTERPRET DIMENSIONS AND TOLERANCES PER ASME Y14.5M 3. MACHINED

  19. Automatic Continuous Testing to Speed Software Development

    E-Print Network [OSTI]

    Liskov, Barbara

    the time and energy required to keep code well-tested and prevent regression errors from persisting and technical design of the Eclipse plug-in, which is now publicly released as a beta. Thesis Supervisor

  20. Automatic Continuous Testing to Speed Software Development

    E-Print Network [OSTI]

    Liskov, Barbara

    the time and energy required to keep code well­tested and prevent regression errors from persisting and technical design of the Eclipse plug­in, which is now publicly released as a beta. Thesis Supervisor

  1. Secondary Waste Cast Stone Waste Form Qualification Testing Plan

    SciTech Connect (OSTI)

    Westsik, Joseph H.; Serne, R. Jeffrey

    2012-09-26T23:59:59.000Z

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

  2. Energy Systems High Pressure Test Laboratory (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2011-10-01T23:59:59.000Z

    This fact sheet describes the purpose, lab specifications, applications scenarios, and information on how to partner with NREL's Energy Systems High Pressure Test Laboratory at the Energy Systems Integration Facility. The purpose of the Energy Systems High Pressure Test Laboratory at NREL's Energy Systems Integration Facility (ESIF) is to provide space where high pressure hydrogen components can be safely tested. High pressure hydrogen storage is an integral part of energy storage technology for use in fuel cell and in other distributed energy scenarios designed to effectively utilize the variability inherent with renewable energy sources. The high pressure storage laboratory is co-located with energy storage activities such as ultra-capacitors, super conducting magnetic flywheel and mechanical energy storage systems laboratories for an integrated approach to system development and demonstration. Hazards associated with hydrogen storage at pressures up to 10,000 psi include oxygen displacement, combustion, explosion, and pressurization of room air due to fast release and physical hazards associated with burst failure modes. A critical understanding of component failure modes is essential in developing reliable, robust designs that will minimize failure risk beyond the end of service life. Development of test protocol for accelerated life testing to accurately scale to real world operating conditions is essential for developing regulations, codes and standards required for safe operation. NREL works closely with industry partners in providing support of advanced hydrogen technologies. Innovative approaches to product design will accelerate commercialization into new markets. NREL works with all phases of the product design life cycle from early prototype development to final certification testing. High pressure tests are performed on hydrogen components, primarily for the validation of developing new codes and standards for high pressure hydrogen applications. The following types of tests can be performed: Performance, Component and system level efficiency, Strength of materials and hydrogen compatibility, Safety demonstration, Model validation, and Life cycle reliability.

  3. Climate Science for a Sustainable Energy Future Test Bed and Data Infrastructure Final Report

    SciTech Connect (OSTI)

    Williams, Dean N. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Foster, I. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Van Dam, Kerstin Kleese [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Shipman, G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2014-05-04T23:59:59.000Z

    The collaborative Climate Science for a Sustainable Energy Future (CSSEF) project started in July 2011 with the goal of accelerating the development of climate model components (i.e., atmosphere, ocean and sea ice, and land surface) and enhancing their predictive capabilities while incorporating uncertainty quantification (UQ). This effort required accessing and converting observational data sets into specialized model testing and verification data sets and building a model development test bed, where model components and sub-models can be rapidly evaluated. CSSEF’s prototype test bed demonstrated, how an integrated testbed could eliminate tedious activities associated with model development and evaluation, by providing the capability to constantly compare model output—where scientists store, acquire, reformat, regrid, and analyze data sets one-by-one—to observational measurements in a controlled test bed.

  4. MECHANICAL TEST LAB CAPABILITIES

    E-Print Network [OSTI]

    MECHANICAL TEST LAB CAPABILITIES · Static and cyclic testing (ASTM and non-standard) · Impact drop testing · Slow-cycle fatigue testing · High temperature testing to 2500°F · ASTM/ Boeing/ SACMA standard testing · Ability to design and fabricate non-standard test fixtures and perform non-standard tests

  5. Testing of ethylene propylene seals for the GA-4/GA-9 casks

    SciTech Connect (OSTI)

    Boonstra, R.H.

    1993-08-01T23:59:59.000Z

    The primary O-ring seal of the GA-4 and GA-9 casks was tested for leakage with a full-scale mockup of the cask lid and flange. Tests were performed at temperatures of ambient, {minus}41{degrees}, 121{degrees}, and 193{degrees}C. Shim plates between the lid and flange simulated gaps caused by thermal distortion. The testing used a helium mass spectrometer leak detector (MSLD). Results showed that the primary seal was leaktight for all test conditions. Helium permeation through the seal began in 13--23 minutes for the ambient tests and in 1--2 minutes for the tests at elevated temperatures. After each test several hours of the pumping were typically required to reduce the MSLD background reading to an acceptable level for the next test, indicating that the seal had become saturated with helium. To verify that the test results showed permeation and not real leakage, several response checks were conducted in which a calibrated leak source was inserted in the detector line near the seal. When the leak source was activated the detector responded within seconds.

  6. Orion Flight Test Exploration Flight Test-1

    E-Print Network [OSTI]

    Waliser, Duane E.

    Orion Flight Test Exploration Flight Test-1 PRESS KIT/December 2014 www.nasa.gov NP-2014-11-020-JSC National Aeronautics and Space Administration #12;#12;Orion Flight Test December 2014 Contents Section Page ........................................................................................... 28 i #12;Orion Flight Test ii December 2014 #12;Orion Flight Test December 2014 Flight Overview

  7. Test Preparation Options Free Test Prep Websites

    E-Print Network [OSTI]

    Stowell, Michael

    Test Preparation Options Free Test Prep Websites ACT: http: http://www.collegeboard.com/student/testing/sat/prep_one/test.html http://www.number2.com://testprep.princetonreview.com/CourseSearch/Search.aspx?itemCode=17&productType=F&rid=1&zip=803 02 Test Prep Classes Front Range Community College: Classes

  8. Test and Test Equipment Joshua Lottich

    E-Print Network [OSTI]

    Patel, Chintan

    Test and Test Equipment Joshua Lottich CMPE 640 11/23/05 #12;Testing Verifies that manufactured chip meets design specifications. Cannot test for every potential defect. Modeling defects as faults allows for passing and failing of chips. Ideal test would capture all defects and pass only chips

  9. HANFORD CONTAINERIZED CAST STONE FACILITY TASK 1 PROCESS TESTING & DEVELOPMENT FINAL TEST REPORT

    SciTech Connect (OSTI)

    LOCKREM, L L

    2005-07-13T23:59:59.000Z

    Laboratory testing and technical evaluation activities on Containerized Cast Stone (CCS) were conducted under the Scope of Work (SOW) contained in CH2M HILL Hanford Group, Inc. (CHG) Contract No. 18548 (CHG 2003a). This report presents the results of testing and demonstration activities discussed in SOW Section 3.1, Task I--''Process Development Testing'', and described in greater detail in the ''Containerized Grout--Phase I Testing and Demonstration Plan'' (CHG, 2003b). CHG (2003b) divided the CCS testing and evaluation activities into six categories, as follows: (1) A short set of tests with simulant to select a preferred dry reagent formulation (DRF), determine allowable liquid addition levels, and confirm the Part 2 test matrix. (2) Waste form performance testing on cast stone made from the preferred DRF and a backup DRF, as selected in Part I, and using low activity waste (LAW) simulant. (3) Waste form performance testing on cast stone made from the preferred DRF using radioactive LAW. (4) Waste form validation testing on a selected nominal cast stone formulation using the preferred DRF and LAW simulant. (5) Engineering evaluations of explosive/toxic gas evolution, including hydrogen, from the cast stone product. (6) Technetium ''getter'' testing with cast stone made with LAW simulant and with radioactive LAW. In addition, nitrate leaching observations were drawn from nitrate leachability data obtained in the course of the Parts 2 and 3 waste form performance testing. The nitrate leachability index results are presented along with other data from the applicable activity categories.

  10. Functions and requirements for 105-KE Basin sludge retrieval and packaging

    SciTech Connect (OSTI)

    Feigenbutz, L.V.

    1994-12-16T23:59:59.000Z

    Sludge, and the clouding due to sludge, interferes with basin operation and maintenance activities. This document defines the overall functions and requirements for sludge retrieval and packaging activities to be performed in the 105-KE Basin.

  11. Closure Report for Corrective Action Unit 104: Area 7 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    none,

    2013-06-27T23:59:59.000Z

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 104, Area 7 Yucca Flat Atmospheric Test Sites, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 104 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management. CAU 104 consists of the following 15 Corrective Action Sites (CASs), located in Area 7 of the Nevada National Security Site: · CAS 07-23-03, Atmospheric Test Site T-7C · CAS 07-23-04, Atmospheric Test Site T7-1 · CAS 07-23-05, Atmospheric Test Site · CAS 07-23-06, Atmospheric Test Site T7-5a · CAS 07-23-07, Atmospheric Test Site - Dog (T-S) · CAS 07-23-08, Atmospheric Test Site - Baker (T-S) · CAS 07-23-09, Atmospheric Test Site - Charlie (T-S) · CAS 07-23-10, Atmospheric Test Site - Dixie · CAS 07-23-11, Atmospheric Test Site - Dixie · CAS 07-23-12, Atmospheric Test Site - Charlie (Bus) · CAS 07-23-13, Atmospheric Test Site - Baker (Buster) · CAS 07-23-14, Atmospheric Test Site - Ruth · CAS 07-23-15, Atmospheric Test Site T7-4 · CAS 07-23-16, Atmospheric Test Site B7-b · CAS 07-23-17, Atmospheric Test Site - Climax Closure activities began in October 2012 and were completed in April 2013. Activities were conducted according to the Corrective Action Decision Document/Corrective Action Plan for CAU 104. The corrective actions included No Further Action and Clean Closure. Closure activities generated sanitary waste, mixed waste, and recyclable material. Some wastes exceeded land disposal limits and required treatment prior to disposal. Other wastes met land disposal restrictions and were disposed in appropriate onsite landfills. The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) requests the following: · A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NFO for closure of CAU 104 · The transfer of CAU 104 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO

  12. Meeting Federal Energy Security Requirements

    Broader source: Energy.gov [DOE]

    Presentation—given at at the Fall 2012 Federal Utility Partnership Working Group (FUPWG) meeting—discusses the opportunity to increase the scope of federal-utility partnerships for meeting energy security requirements.

  13. Fusion technology status and requirements

    SciTech Connect (OSTI)

    Thomassen, K.I.

    1982-01-26T23:59:59.000Z

    This paper summarizes the status of fusion technology and discusses the requirements to be met in order to build a demonstration fusion plant. Strategies and programmatic considerations in pursuing engineering feasibility are also outlined.

  14. POSTGRADUATE PROGRAMMES Procedures and Requirements

    E-Print Network [OSTI]

    Jagannatham, Aditya K.

    Engineering, Materials Science, Mechanical Engineering, Nuclear Engineering and Technology and Photonics Statistics), Mechanical Engineering, Nuclear Engineering and Technology, Photonics Science and Engineering(1) POSTGRADUATE PROGRAMMES Procedures and Requirements INDIAN INSTITUTE OF TECHNOLOGY KANPUR

  15. HTS wire requirements for SMES

    SciTech Connect (OSTI)

    Schoenung, S.; Schafer, W.J.

    1994-07-29T23:59:59.000Z

    This presentation/paper gives an overview of the Sandia National Lab`s sponsorship of W.J. Schafer Associates, Inc. to examine the following topics: the refrigeration savings possible by using high temperature superconductors (HTS) in Superconducting Magnetic Energy Storage (SMES), the impact of duty cycle on refrigeration requirements, and outline the required HTS wire performance. Included are specifications for SMES applications, advantages, cost components, assumed conductor performance parameters, and the effects of duty cycle and conductor twist pitch.

  16. acoustic impedance tests: Topics by E-print Network

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

    DETAILS Engineering Websites Summary: no electrical connection, and requires a lift bucket for access, a new approach was needed to enable AE testing Figure 2: Weatherproof...

  17. CRUSH TESTING OF 9977 GENERAL PURPOSE FISSILE PACKAGINGS

    SciTech Connect (OSTI)

    Smith, A.

    2010-07-28T23:59:59.000Z

    The 9977 General Purpose Fissile Package (GPFP) was designed in response to the adoption of the crush test requirement in the US regulations for packages for radioactive materials (10 CFR 71). This presentation on crush testing of the 9977 GPFP Reviews origins of Crush Test Requirements and implementation of crush test requirements in 10 CFR 71. SANDIA testing performed to support the rule making is reviewed. The differences in practice, on the part of the US Department of Energy from those required by the NRC for commercial purposes, are explained. The design features incorporated into the 9977 GPFP to enable it to withstand the crush test and the crush tests performed on the 9977 are described. Lessons learned from crush testing of GPFP packagings are given.

  18. Low temperature irradiation tests on

    E-Print Network [OSTI]

    McDonald, Kirk

    Sample cool down by He gas loop 10K ­ 20K Fast neutron flux Measured by Ni activation in 2010 1.4xK #12;reactor Cryogenics #12;Al-Cu-Mg He gas temperature near sample 12K Resistance changesLow temperature irradiation tests on stabilizer materials using reactor neutrons at KUR Makoto

  19. Part B - Requirements & Funding Information PART B - Requirements...

    Office of Environmental Management (EM)

    of Part A. For example, Part A could be located in the master file for IA number xxx at contracting office xxx. Activities undertaken pursuant to this document are subject...

  20. Hydrogen Storage Materials Requirements (Text Version) | Department...

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

    Requirements (Text Version) Hydrogen Storage Materials Requirements (Text Version) Below is the text version of the webinar titled "Hydrogen Storage Materials Requirements,"...

  1. W-087 Acceptance test procedure. Revision 1

    SciTech Connect (OSTI)

    Joshi, A.W.

    1997-06-10T23:59:59.000Z

    This Acceptance Test Procedure/Operational Test Procedure (ATP/OTP) has been prepared to demonstrate that the Electrical/Instrumentation and Mechanical systems function as required by project criteria and to verify proper operation of the integrated system including the interlocks.

  2. Light Duty Utility Arm Software Test Plan

    SciTech Connect (OSTI)

    Kiebel, G.R.

    1995-12-18T23:59:59.000Z

    This plan describes how validation testing of the software will be implemented for the integrated control and data acquisition system of the Light Duty Utility Arm System (LDUA). The purpose of LDUA software validation testing is to demonstrate and document that the LDUA software meets its software requirements specification.

  3. Nevada Test Site Waste Acceptance Criteria (NTSWAC)

    SciTech Connect (OSTI)

    NNSA /NSO Waste Management Project

    2008-06-01T23:59:59.000Z

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

  4. Calibration curves for some standard Gap Tests

    SciTech Connect (OSTI)

    Bowman, A.L.; Sommer, S.C.

    1989-01-01T23:59:59.000Z

    The relative shock sensitivities of explosive compositions are commonly assessed using a family of experiments that can be described by the generic term ''Gap Test.'' Gap tests include a donor charge, a test sample, and a spacer, or gap, between two explosives charges. The donor charge, gap material, and test dimensions are held constant within each different version of the gap test. The thickness of the gap is then varied to find the value at which 50% of the test samples will detonate. The gap tests measure the ease with a high-order detonation can be established in the test explosive, or the ''detonability,'' of the explosive. Test results are best reported in terms of the gap thickness at the 50% point. It is also useful to define the shock pressure transmitted into the test sample at the detonation threshold. This requires calibrating the gap test in terms of shock pressure in the gap as a function of the gap thickness. It also requires a knowledge of the shock Hugoniot of the sample explosive. We used the 2DE reactive hydrodynamic code with Forest Fire burn rates for the donor explosives to calculate calibration curves for several gap tests. The model calculations give pressure and particle velocity on the centerline of the experimental set-up and provide information about the curvature and pulse width of the shock wave. 10 refs., 1 fig.

  5. Design, fabrication and testing of a bearing test rig and preliminary studies on oil mist lubrication

    E-Print Network [OSTI]

    Shamim, Abdus

    1990-01-01T23:59:59.000Z

    DESIGN, FABRICATION AND TESTING OF A BEARING TEST RIG AND PRELIMINARY STUDIES ON OIL MIST LUBRICATION A Thesis by ABDUS SHAMIM Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements... for the degree of MASTER OF SCIENCE August 1990 Major Subject: Mechanical Engineering DESIGN, FABRICATION AND TESTING OF A BEARING TEST RIG AND PRELIMINARY STUDIES ON OIL MIST LUBRICATION A Thesis by ABDUS SHAMIM Approved as to style and content by: C...

  6. Hydrates detection by cone penetration testing: cone penetration tests through ice layers

    E-Print Network [OSTI]

    Jeanjean, Philippe Henri

    1991-01-01T23:59:59.000Z

    HYDRATES DETECTION BY CONE PENETRATION TESTING: PART I: CONE PENETRATION TESTS THROUGH ICE LAYERS A Thesis by PHILIPPE HENRI JEANJEAN Submitted to the Office of Graduate Studies of Texas ABcM University in partial fulfillment... of the requirement for the degree of MASTER OF SCIENCE May 1991 Major Subject: Civil Engineering HYDRATES DETECTION BY CONE PENETRATION TESTING: PART I: CONE PENETRATION TESTS THROUGH ICE LAYERS A Thesis by PHILIPPE HENRI JEANJEAN Approved as to style...

  7. Automated Black-Box Testing with Abstract VDM Oracles

    E-Print Network [OSTI]

    as test oracles for concrete software. The automation of the resulting testing frame-work is based of a target system. For that reason, a mapping between abstract and concrete test data is requiredAutomated Black-Box Testing with Abstract VDM Oracles Bernhard K. Aichernig Technical University

  8. Samples of Drug Testing Language Memorandum for Human Resources File

    E-Print Network [OSTI]

    Almor, Amit

    Samples of Drug Testing Language Memorandum for Human Resources File DATE: TO: Employee FROM: Supervisor RE: Drug Testing As you know, the position that you have been selected for requires that you pass a pre-employment drug and alcohol test. In addition to the pre-employment test, you will also be subject

  9. Cold Vacuum Drying (CVD) Facility Technical Safety Requirements

    SciTech Connect (OSTI)

    KRAHN, D.E.

    2000-08-08T23:59:59.000Z

    The Technical Safety Requirements (TSRs) for the Cold Vacuum Drying Facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt of multi-canister overpacks (MCOs) containing spent nuclear fuel. removal of free water from the MCOs using the cold vacuum drying process, and inerting and testing of the MCOs before transport to the Canister Storage Building. Controls required for public safety, significant defense in depth, significant worker safety, and for maintaining radiological and toxicological consequences below risk evaluation guidelines are included.

  10. Dynamic Response Testing in an Electrically Heated Reactor Test Facility

    SciTech Connect (OSTI)

    Bragg-Sitton, Shannon M. [NASA Marshall Space Flight Center, Nuclear and Advanced Propulsion Branch, ER-11, MSFC, AL 35812 (United States); Morton, T. J. [Department of Chemical and Nuclear Engineering, University of New Mexico, Albuquerque, NM 87131 (United States)

    2006-01-20T23:59:59.000Z

    Non-nuclear testing can be a valuable tool in the development of a space nuclear power or propulsion system. In a non-nuclear test bed, electric heaters are used to simulate the heat from nuclear fuel. Standard testing allows one to fully assess thermal, heat transfer, and stress related attributes of a given system, but fails to demonstrate the dynamic response that would be present in an integrated, fueled reactor system. The integration of thermal hydraulic hardware tests with simulated neutronic response provides a bridge between electrically heated testing and fueled nuclear testing. By implementing a neutronic response model to simulate the dynamic response that would be expected in a fueled reactor system, one can better understand system integration issues, characterize integrated system response times and response characteristics, and assess potential design improvements at a relatively small fiscal investment. Initial system dynamic response testing was demonstrated on the integrated SAFE-100a heat pipe (HP) cooled, electrically heated reactor and heat exchanger hardware, utilizing a one-group solution to the point kinetics equations to simulate the expected neutronic response of the system. Reactivity feedback calculations were then based on a bulk reactivity feedback coefficient and measured average core temperature. This paper presents preliminary results from similar dynamic testing of a direct drive gas cooled reactor system (DDG), demonstrating the applicability of the testing methodology to any reactor type and demonstrating the variation in system response characteristics in different reactor concepts. Although the HP and DDG designs both utilize a fast spectrum reactor, the method of cooling the reactor differs significantly, leading to a variable system response that can be demonstrated and assessed in a non-nuclear test facility. Planned system upgrades to allow implementation of higher fidelity dynamic testing are also discussed. Proposed DDG testing will utilize a higher fidelity point kinetics model to control core power transients, and reactivity feedback will be based on localized feedback coefficients and several independent temperature measurements taken within the core block. This paper presents preliminary test results and discusses the methodology that will be implemented in follow-on DDG testing and the additional instrumentation required to implement high fidelity dynamic testing.

  11. Pilot-scale treatability test plan for the 200-UP-1 groundwater Operable Unit

    SciTech Connect (OSTI)

    Wittreich, C.D.

    1994-05-01T23:59:59.000Z

    This document presents the treatability test plan for pilot-scale pump and treat testing at the 200-UP-1 Operable Unit. This treatability test plan has been prepared in response to an agreement between the US Department of Energy, the US Environmental Protection Agency, and the Washington State Department of Ecology, as documented in Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1989a) Change Control Form M-13-93-03 (Ecology et al. 1994). The agreement also requires that, following completion of the activities described in this test plan, a 200-UP-1 Operable Unit interim remedial measure (IRM) proposed plan be developed for use in preparing an interim action record of decision (ROD). The IRM Proposed Plan will be supported by the results of the testing described in this treatability test plan, as well as by other 200-UP-1 Operable Unit activities (e.g., limited field investigation, development of a qualitative risk assessment). Once issued, the interim action ROD will specify the interim action for groundwater contamination at the 200-UP-1 Operable Unit. The approach discussed in this treatability test plan is to conduct a pilot-scale pump and treat test for the contaminant plume associated with the 200-UP-1 Operable Unit. Primary contaminants of concern are uranium and technetium-99; the secondary contaminant of concern is nitrate. The pilot-scale treatability testing presented in this test plan has as its primary purpose to assess the performance of aboveground treatment systems with respect to the ability to remove the primary contaminants in groundwater withdrawn from the contaminant plume.

  12. Past Test One

    E-Print Network [OSTI]

    MA 366: Introduction to Di?'erential Equations. Fall 2001, Test One. Instructor: Yip o This test booklet has FIVE QUESTIONS, totaling 50 points for the whole test.

  13. Advanced Vehicle Testing & Evaluation

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

    Vehicle Accelerated Reliability Test Battery Electric Vehicle Fast Charge Test Battery Energy Storage Performance Test For DC Fast Charge Demand Reduction...

  14. Status and specifications of a Project X front-end accelerator test facility at Fermilab

    SciTech Connect (OSTI)

    Steimel, J.; Webber, R.; Madrak, R.; Wildman, D.; Pasquinelli, R.; Evans-Peoples, E.; /Fermilab

    2011-03-01T23:59:59.000Z

    This paper describes the construction and operational status of an accelerator test facility for Project X. The purpose of this facility is for Project X component development activities that benefit from beam tests and any development activities that require 325 MHz or 650 MHz RF power. It presently includes an H- beam line, a 325 MHz superconducting cavity test facility, a 325 MHz (pulsed) RF power source, and a 650 MHz (CW) RF power source. The paper also discusses some specific Project X components that will be tested in the facility. Fermilab's future involves new facilities to advance the intensity frontier. In the early 2000's, the vision was a pulsed, superconducting, 8 GeV linac capable of injecting directly into the Fermilab Main Injector. Prototyping the front-end of such a machine started in 2005 under a program named the High Intensity Neutrino Source (HINS). While the HINS test facility was being constructed, the concept of a new, more versatile accelerator for the intensity frontier, now called Project X, was forming. This accelerator comprises a 3 GeV CW superconducting linac with an associated experimental program, followed by a pulsed 8 GeV superconducting linac to feed the Main Injector synchrotron. The CW Project X design is now the model for Fermilab's future intensity frontier program. Although CW operation is incompatible with the original HINS front-end design, the installation remains useful for development and testing many Project X components.

  15. Testing of Large-Scale ICV Glasses with Hanford LAW Simulant

    SciTech Connect (OSTI)

    Hrma, Pavel R.; Kim, Dong-Sang; Vienna, John D.; Matyas, Josef; Smith, Donald E.; Schweiger, Michael J.; Yeager, John D.

    2005-03-01T23:59:59.000Z

    Preliminary glass compositions for immobilizing Hanford low-activity waste (LAW) by the in-container vitrification (ICV) process were initially fabricated at crucible- and engineering-scale, including simulants and actual (radioactive) LAW. Glasses were characterized for vapor hydration test (VHT) and product consistency test (PCT) responses and crystallinity (both quenched and slow-cooled samples). Selected glasses were tested for toxicity characteristic leach procedure (TCLP) responses, viscosity, and electrical conductivity. This testing showed that glasses with LAW loading of 20 mass% can be made readily and meet all product constraints by a far margin. Glasses with over 22 mass% Na2O can be made to meet all other product quality and process constraints. Large-scale testing was performed at the AMEC, Geomelt Division facility in Richland. Three tests were conducted using simulated LAW with increasing loadings of 12, 17, and 20 mass% Na2O. Glass samples were taken from the test products in a manner to represent the full expected range of product performance. These samples were characterized for composition, density, crystalline and non-crystalline phase assemblage, and durability using the VHT, PCT, and TCLP tests. The results, presented in this report, show that the AMEC ICV product with meets all waste form requirements with a large margin. These results provide strong evidence that the Hanford LAW can be successfully vitrified by the ICV technology and can meet all the constraints related to product quality. The economic feasibility of the ICV technology can be further enhanced by subsequent optimization.

  16. Tank Farms Technical Safety Requirements

    SciTech Connect (OSTI)

    DANNA, M.A.

    2003-10-24T23:59:59.000Z

    The TSRs define the acceptable conditions, safe boundaries, bases thereof, and controls to ensure safe operation during authorized activities, for facilities within the scope of the Tank Farms Documented Safety Analysis (DSA), in parallel with the DSA.

  17. Disposal requirements for PCB waste

    SciTech Connect (OSTI)

    NONE

    1994-12-01T23:59:59.000Z

    Polychlorinated biphenyls (PCBs) are a class of organic chemicals that had become widely used in industrial applications due to their practical physical and chemical properties. Historical uses of PCBs include dielectric fluids (used in utility transformers, capacitors, etc.), hydraulic fluids, and other applications requiring stable, fire-retardant materials. Due to findings that PCBs may cause adverse health effects and due to their persistence and accumulation in the environment, the Toxic Substances Control Act (TSCA), enacted on october 11, 1976, banned the manufacture of PCBs after 1978 [Section 6(e)]. The first PCB regulations, promulgated at 40 CFR Part 761, were finalized on February 17, 1978. These PCB regulations include requirements specifying disposal methods and marking (labeling) procedures, and controlling PCB use. To assist the Department of Energy (DOE) in its efforts to comply with the TSCA statute and implementing regulations, the Office of Environmental Guidance has prepared the document ``Guidance on the Management of Polychlorinated Biphenyls (PCBs).`` That document explains the requirements specified in the statute and regulations for managing PCBs including PCB use, storage, transport, and disposal. PCB materials that are no longer in use and have been declared a waste must be disposed of according to the requirements found at 40 CFR 761.60. These requirements establish disposal options for a multitude of PCB materials including soil and debris, liquid PCBs, sludges and slurries, containers, transformers, capacitors, hydraulic machines, and other electrical equipment. This Information Brief supplements the PCB guidance document by responding to common questions concerning disposal requirements for PCBs. It is one of a series of Information Briefs pertinent to PCB management issues.

  18. IFE chamber technology testing program in NIF and chamber development test plan

    SciTech Connect (OSTI)

    Abdou, M.A. [Univ. of California, Los Angeles, CA (United States)

    1995-12-31T23:59:59.000Z

    Issues concerning chamber technology testing program in NIF involving: criteria for evaluation/prioritization of experiments, engineering scaling requirements for test article design and material selection and R and D plan prior to NIF testing were addressed in this paper. In order to maximize the benefits of testing program in NIF, the testing in NIF should provide the experimental data relevant to DEMO design choice or to DEMO design predictive capability by utilizing engineering scaling test article designs. Test plans were developed for 2 promising chamber design concepts. Early testing in non-fusion/non-ignition prior to testing in ignition facility serves a critical role in chamber R and D test plans in order to reduce the risks and costs of the more complex experiments in NIF.

  19. W-026, acceptance test report manipulator system

    SciTech Connect (OSTI)

    Watson, T.L.

    1997-04-15T23:59:59.000Z

    The purpose of the WRAP Manipulator System Acceptance Test Plan (ATP) is to verify that the 4 glovebox sets of WRAP manipulator components, including rail/carriage, slave arm, master controller and auxiliary equipment, meets the requirements of the functional segments of 14590 specification. The demonstration of performance elements of the ATP are performed as a part of the Assembly specifications. Manipulator integration is integrated in the performance testing of the gloveboxes. Each requirement of the Assembly specification will be carried out in conjunction with glovebox performance tests.

  20. Johnson Noise Thermometry System Requirements

    SciTech Connect (OSTI)

    Britton Jr, Charles L [ORNL; Roberts, Michael [ORNL; Ezell, N Dianne Bull [ORNL; Qualls, A L [ORNL; Holcomb, David Eugene [ORNL

    2013-01-01T23:59:59.000Z

    This document is intended to capture the requirements for the architecture of the developmental electronics for the ORNL-lead drift-free Johnson Noise Thermometry (JNT) project conducted under the Instrumentation, Controls, and Human-Machine Interface (ICHMI) research pathway of the U.S. Department of Energy (DOE) Advanced Small Modular Reactor (SMR) Research and Development (R&D) program. The requirements include not only the performance of the system but also the allowable measurement environment of the probe and the allowable physical environment of the associated electronics. A more extensive project background including the project rationale is available in the initial project report [1].

  1. Project X functional requirements specification

    SciTech Connect (OSTI)

    Holmes, S.D.; Henderson, S.D.; Kephart, R.; Kerby, J.; Kourbanis, I.; Lebedev, V.; Mishra, S.; Nagaitsev, S.; Solyak, N.; Tschirhart, R.; /Fermilab

    2012-05-01T23:59:59.000Z

    Project X is a multi-megawatt proton facility being developed to support a world-leading program in Intensity Frontier physics at Fermilab. The facility is designed to support programs in elementary particle and nuclear physics, with possible applications to nuclear energy research. A Functional Requirements Specification has been developed in order to establish performance criteria for the Project X complex in support of these multiple missions, and to assure that the facility is designed with sufficient upgrade capability to provide U.S. leadership for many decades to come. This paper will briefly review the previously described Functional Requirements, and then discuss their recent evolution.

  2. Advanced Vehicle Testing - Beginning-of-Test Battery Testing...

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

    2.5 V Thermal Mgmt.: Passive, Vacuum-Sealed Unit Pack Weight: 294 kg BATTERY LABORATORY TEST RESULTS SUMMARY Vehicle Mileage and Testing Date Vehicle Odometer: 6,696 mi Date of...

  3. Romanian experience on packaging testing

    SciTech Connect (OSTI)

    Vieru, G. [IAEA Technical Expert, Head, Reliability and Testing Lab., Institute for Nuclear Research (Romania)

    2007-07-01T23:59:59.000Z

    With more than twenty years ago, the Institute for Nuclear Research Pitesti (INR), through its Reliability and Testing Laboratory, was licensed by the Romanian Nuclear Regulatory Body- CNCAN and to carry out qualification tests [1] for packages intended to be used for the transport and storage of radioactive materials. Radioactive materials, generated by Romanian nuclear facilities [2] are packaged in accordance with national [3] and the IAEA's Regulations [1,6] for a safe transport to the disposal center. Subjecting these packages to the normal and simulating test conditions accomplish the evaluation and certification in order to prove the package technical performances. The paper describes the qualification tests for type A and B packages used for transport and storage of radioactive materials, during a period of 20 years of experience. Testing is used to substantiate assumption in analytical models and to demonstrate package structural response. The Romanian test facilities [1,3,6] are used to simulate the required qualification tests and have been developed at INR Pitesti, the main supplier of type A packages used for transport and storage of low radioactive wastes in Romania. The testing programme will continue to be a strong option to support future package development, to perform a broad range of verification and certification tests on radioactive material packages or component sections, such as packages used for transport of radioactive sources to be used for industrial or medical purposes [2,8]. The paper describes and contain illustrations showing some of the various tests packages which have been performed during certain periods and how they relate to normal conditions and minor mishaps during transport. Quality assurance and quality controls measures taken in order to meet technical specification provided by the design there are also presented and commented. (authors)

  4. SOFTWARE QUALITY & SYSTEMS ENGINEERING PROGRAM: Requirements...

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

    Requirements Management Checklist SOFTWARE QUALITY & SYSTEMS ENGINEERING PROGRAM: Requirements Management Checklist The following checklist is intended to provide system owners,...

  5. World nuclear capacity and fuel cycle requirements, November 1993

    SciTech Connect (OSTI)

    Not Available

    1993-11-30T23:59:59.000Z

    This analysis report presents the current status and projections of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. Long-term projections of US nuclear capacity, generation, fuel cycle requirements, and spent fuel discharges for three different scenarios through 2030 are provided in support of the Department of Energy`s activities pertaining to the Nuclear Waste Policy Act of 1982 (as amended in 1987). The projections of uranium requirements also support the Energy Information Administration`s annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment.

  6. Development, tests, and data acquisition of the integrated system of internal sensors for RFX

    SciTech Connect (OSTI)

    Serianni, G.; Bolzonella, T.; Cavazzana, R.; Marchiori, G.; Pomaro, N.; Lotto, L.; Monari, M.; Taliercio, C. [Consorzio RFX, Associazione Euratom-ENEA sulla Fusione, Corso Stati Uniti 4, I-35127 Padova (Italy)

    2004-10-01T23:59:59.000Z

    The RFX reversed field pinch (RFP) has undergone major modifications of the load assembly and is now equipped with a large number of active external coils for magnetohydrodynamics mode control. The study of the effects on the plasma of both the new passive structure and the active coils is then of great importance, as well as the investigation of turbulence due to its influence on plasma transport. An integrated system of magnetic, electrostatic and calorimetric sensors has been realized, fulfilling very challenging requirements in terms of spatial and temporal resolution, which are characteristic features of RFP plasmas. A description of the whole diagnostic system is given, including the original solutions adopted to cope with the limited space available and the thermal and electrical requirements, particularly for the calorimetrical probes. The tests performed on the whole system during the installation are presented. Signal conditioning and data acquisition are described.

  7. Bull Test ID 1118 2013 Florida Bull Test

    E-Print Network [OSTI]

    Jawitz, James W.

    Bull Test ID 1118 2013 Florida Bull Test #12;Bull Test ID 1119 2013 Florida Bull Test #12;Bull Test ID 1120 2013 Florida Bull Test #12;Bull Test ID 1121 2013 Florida Bull Test #12;Bull Test ID 1122 2013 Florida Bull Test #12;Bull Test ID 1123 2013 Florida Bull Test #12;Bull Test ID 1124 2013 Florida

  8. Bull Test ID 1181 2013 Florida Bull Test

    E-Print Network [OSTI]

    Jawitz, James W.

    Bull Test ID 1181 2013 Florida Bull Test #12;Bull Test ID 1182 2013 Florida Bull Test #12;Bull Test ID 1183 2013 Florida Bull Test #12;Bull Test ID 1184 2013 Florida Bull Test #12;Bull Test ID 1185 2013 Florida Bull Test #12;Bull Test ID 1186 2013 Florida Bull Test #12;Bull Test ID 1187 2013 Florida

  9. Bull Test ID 1098 2013 Florida Bull Test

    E-Print Network [OSTI]

    Jawitz, James W.

    Bull Test ID 1098 2013 Florida Bull Test #12;Bull Test ID 1099 2013 Florida Bull Test #12;Bull Test ID 1100 2013 Florida Bull Test #12;Bull Test ID 1101 2013 Florida Bull Test #12;Bull Test ID 1102 2013 Florida Bull Test #12;Bull Test ID 1103 2013 Florida Bull Test #12;Bull Test ID 1104 2013 Florida

  10. Bull Test ID 1160 2013 Florida Bull Test

    E-Print Network [OSTI]

    Jawitz, James W.

    Bull Test ID 1160 2013 Florida Bull Test #12;Bull Test ID 1161 2013 Florida Bull Test #12;Bull Test ID 1162 2013 Florida Bull Test #12;Bull Test ID 1163 2013 Florida Bull Test #12;Bull Test ID 1164 2013 Florida Bull Test #12;Bull Test ID 1165 2013 Florida Bull Test #12;Bull Test ID 1166 2013 Florida

  11. Bull Test ID 1077 2013 Florida Bull Test

    E-Print Network [OSTI]

    Jawitz, James W.

    14th Annual Florida Bull Test #12;Bull Test ID 1077 2013 Florida Bull Test #12;Bull Test ID 1078 2013 Florida Bull Test #12;Bull Test ID 1079 2013 Florida Bull Test #12;Bull Test ID 1080 2013 Florida Bull Test #12;Bull Test ID 1081 2013 Florida Bull Test #12;Bull Test ID 1082 2013 Florida Bull Test #12

  12. Bull Test ID 1140 2013 Florida Bull Test

    E-Print Network [OSTI]

    Jawitz, James W.

    Bull Test ID 1140 2013 Florida Bull Test #12;Bull Test ID 1141 2013 Florida Bull Test #12;Bull Test ID 1142 2013 Florida Bull Test #12;Bull Test ID 1143 2013 Florida Bull Test #12;Bull Test ID 1144 2013 Florida Bull Test #12;Bull Test ID 1145 2013 Florida Bull Test #12;Bull Test ID 1146 2013 Florida

  13. Underground Test Area Fiscal Year 2013 Annual Quality Assurance Report Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Krenzien, Susan; Marutzky, Sam

    2014-01-01T23:59:59.000Z

    This report is required by the Underground Test Area (UGTA) Quality Assurance Plan (QAP) and identifies the UGTA quality assurance (QA) activities for fiscal year (FY) 2013. All UGTA organizations—U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO); Desert Research Institute (DRI); Lawrence Livermore National Laboratory (LLNL); Los Alamos National Laboratory (LANL); Navarro-Intera, LLC (N-I); National Security Technologies, LLC (NSTec); and the U.S. Geological Survey (USGS)—conducted QA activities in FY 2013. The activities included conducting assessments, identifying findings and completing corrective actions, evaluating laboratory performance, and publishing documents. In addition, integrated UGTA required reading and corrective action tracking was instituted.

  14. Massachusetts Large Blade Test Facility Final Report

    SciTech Connect (OSTI)

    Rahul Yarala; Rob Priore

    2011-09-02T23:59:59.000Z

    Project Objective: The Massachusetts Clean Energy Center (CEC) will design, construct, and ultimately have responsibility for the operation of the Large Wind Turbine Blade Test Facility, which is an advanced blade testing facility capable of testing wind turbine blades up to at least 90 meters in length on three test stands. Background: Wind turbine blade testing is required to meet international design standards, and is a critical factor in maintaining high levels of reliability and mitigating the technical and financial risk of deploying massproduced wind turbine models. Testing is also needed to identify specific blade design issues that may contribute to reduced wind turbine reliability and performance. Testing is also required to optimize aerodynamics, structural performance, encourage new technologies and materials development making wind even more competitive. The objective of this project is to accelerate the design and construction of a large wind blade testing facility capable of testing blades with minimum queue times at a reasonable cost. This testing facility will encourage and provide the opportunity for the U.S wind industry to conduct more rigorous testing of blades to improve wind turbine reliability.

  15. Cone Penetrometer N Factor Determination Testing Results

    SciTech Connect (OSTI)

    Follett, Jordan R.

    2014-03-05T23:59:59.000Z

    This document contains the results of testing activities to determine the empirical 'N Factor' for the cone penetrometer in kaolin clay simulant. The N Factor is used to releate resistance measurements taken with the cone penetrometer to shear strength.

  16. DEGREE REQUIREMENTS BIOLOGICAL ENGINEERING TECHNOLOGY

    E-Print Network [OSTI]

    Walter, M.Todd

    DEGREE REQUIREMENTS BIOLOGICAL ENGINEERING TECHNOLOGY ENVIRONMENTAL ENGINEERING TECHNOLOGY The curriculum in the technology programs must satisfy the College of Agriculture and Life Sciences (CALS for the technology programs are listed by subject matter in three major categories: (A) Basic Subjects, (B) Advanced

  17. APPLICATION REQUIREMENTS: Admission Applica on

    E-Print Network [OSTI]

    Rainforth, Emma C.

    basis. An interview may be required. MS Educa onal Technology Program: A state issued teaching cer: State issued teaching cer ficate. Three years of professional experience as a teacher:_____________ ­ __________ ­ ________________ Sex: Male Female Street Address Town or City County State Zip Code Home Telephone

  18. SRS control system upgrade requirements

    SciTech Connect (OSTI)

    Hill, L.F.

    1998-08-04T23:59:59.000Z

    This document defines requirements for an upgrade of the Sodium Removal System (SRS) control system. The upgrade is being performed to solve a number of maintainability and operability issues. The upgraded system will provide the same functions, controls and interlocks as the present system, and in addition provide enhanced functionality in areas discussed in this document.

  19. Computer Science Graduation Requirements Checklist

    E-Print Network [OSTI]

    Zadok, Erez

    Computer Science Graduation Requirements Checklist ­ Fall 2008 Computer Science Courses Course Gr. Sem. Comments CSE 114 Computer Science I [prerequisite: CSE 110] CSE 214 Computer Science II CSE 215 Foundations of Computer Science CSE 219 Computer Science III CSE 220 Computer Organization CSE 300 Writing

  20. Computer Science Graduation Requirements Checklist

    E-Print Network [OSTI]

    Zadok, Erez

    Computer Science Graduation Requirements Checklist ­ Fall 2009 Computer Science Courses Course Gr. Sem. Comments CSE 114 Computer Science I [prerequisite: CSE 110] CSE 214 Computer Science II CSE 215 Foundations of Computer Science CSE 219 Computer Science III CSE 220 Computer Organization CSE 300 Writing

  1. AMS vs. NWS: Educational Requirements

    E-Print Network [OSTI]

    · Reconstruction of past climates · Climate models · Causes of past and future climate change #12;Capstone methods · Oral, written, and multimedia communication ­ Ability to create and deliver scientific ­ Ability to effectively communicate with technical and lay audiences using scientific evidence #12;Required

  2. ALLOCATION OF REACTIVE SUPPORT REQUIREMENTS

    E-Print Network [OSTI]

    Gross, George

    the voltage setting point s kV of each bus Qk and the voltage profile for the buses c j Q . Recall that Q for these transactions so that all bus voltages meet the specified voltage profile requirements. Consequently load is locally met at the bus. In other words, we assume that at each load bus the power factor is 1

  3. Documentation Requirements for Learning Disabilities

    E-Print Network [OSTI]

    Documentation Requirements for Learning Disabilities Students, faculty, staff, and campus guests wishing to request accommodations due to learning disabilities should refer to the following documentation of interest. C) Documentation must be typed, dated, signed by the evaluator and submitted to ODR

  4. LCLS Heavy Met Outgassing Tests

    SciTech Connect (OSTI)

    Kishiyama, K. I.

    2010-12-01T23:59:59.000Z

    A Heavy Met that is 95% tungsten, 3% nickel and 2% iron and sintered to 100% density and is Ultra High Vacuum (UHV) compatible is proposed for use as the X-ray slit in the Front End Enclosure and the Fixed Mask for the Linac Coherent Light Source (LCLS). The Heavy Met was tested in the LLNL Vacuum Sciences and Engineering Lab (VSEL) to determine its outgassing rate and its overall compatibility with the vacuum requirements for LCLS.

  5. 10 CFR 850 Implementation of Requirements

    SciTech Connect (OSTI)

    Lee, S

    2012-01-05T23:59:59.000Z

    10 CFR 850 defines a contractor as any entity, including affiliated entities, such as a parent corporation, under contract with DOE, including a subcontractor at any tier, with responsibility for performing work at a DOE site in furtherance of a DOE mission. The Chronic Beryllium Disease Prevention Program (CBDPP) applies to beryllium-related activities that are performed at the Lawrence Livermore National Laboratory (LLNL). The CBDPP or Beryllium Safety Program is integrated into the LLNL Worker Safety and Health Program and, thus, implementation documents and responsibilities are integrated in various documents and organizational structures. Program development and management of the CBDPP is delegated to the Environment, Safety and Health (ES&H) Directorate, Worker Safety and Health Functional Area. As per 10 CFR 850, Lawrence Livermore National Security, LLC (LLNS) periodically submits a CBDPP to the National Nuclear Security Administration/Livermore Site Office (NNSA/LSO). The requirements of this plan are communicated to LLNS workers through ES&H Manual Document 14.4, 'Working Safely with Beryllium.' 10 CFR 850 is implemented by the LLNL CBDPP, which integrates the safety and health standards required by the regulation, components of the LLNL Integrated Safety Management System (ISMS), and incorporates other components of the LLNL ES&H Program. As described in the regulation, and to fully comply with the regulation, specific portions of existing programs and additional requirements are identified in the CBDPP. The CBDPP is implemented by documents that interface with the workers, principally through ES&H Manual Document 14.4. This document contains information on how the management practices prescribed by the LLNL ISMS are implemented, how beryllium hazards that are associated with LLNL work activities are controlled, and who is responsible for implementing the controls. Adherence to the requirements and processes described in the ES&H Manual ensures that ES&H practices across LLNL are developed in a consistent manner. Other implementing documents, such as the ES&H Manual, are integral in effectively implementing 10 CFR 850.

  6. Comparison of standard acute toxicity tests with rapid-screening toxicity tests

    SciTech Connect (OSTI)

    Toussaint, M.W.; Shedd, T.R.; VanDerSchal, W.H.; Leather, G.R.

    1995-10-01T23:59:59.000Z

    This study compared the relative sensitivity of five inexpensive, rapid toxicity tests to the sensitivity of five standard aquatic acute toxicity tests through literature review and testing. The rapid toxicity tests utilized organisms that require little culturing or handling prior to testing: a freshwater rotifer (Branchionus ccalyciflorus); brine shrimp (Artemia salina); lettuce (Lactuca sativa); and two microbial tests (Photo bacterium phosphoreum - Microtox test, and a mixture of bacterial species - the polytox test). Standard acute toxicity test species included water fleas (Daphnia magna and Ceriadaphnta dubia), green algae (Setenastrum capricarnutum), fathead minnows (Pimephalespromelas), and mysid shrimp (Mysidopsis bahia). Sensitivity comparisons between rapid and standard acute toxicity tests were based on LC5O/EC50 data from 11 test chemicals. Individually, the lettuce and rotifer tests ranked most similar in sensitivity to the standard tests, while Microtox fell just outside the range of sensitivities represented by the group of standard acute toxicity tests. The brine shrimp and Polytox tests were one or more orders of magnitude different from the standard acute toxicity tests for most compounds. The lettuce, rotifer, and Microtox tests could be used as a battery for preliminary toxicity screening of chemicals. Further evaluation of complex real-world environmental samples is recommended.

  7. A comparison of standard acute toxicity tests with rapid-screening toxicity tests

    SciTech Connect (OSTI)

    Toussaint, M.W. [Geo-Centers, Inc., Fort Washington, MD (United States); Shedd, T.R. [Army Biomedical Research and Development Lab., Frederick, MD (United States); Schalie, W.H. van der [Environmental Protection Agency, Washington, DC (United States); Leather, G.R. [Hood Coll., Frederick, MD (United States). Dept. of Biology

    1995-05-01T23:59:59.000Z

    This study compared the relative sensitivity of five inexpensive, rapid toxicity tests to the sensitivity of five standard aquatic acute toxicity tests through literature review and testing. The rapid toxicity tests utilized organisms that require little culturing or handling prior to testing: a freshwater rotifer (Branchionus calyciflorus); brine shrimp (Artemia salina); lettuce (Lactuca sativa); and two microbial tests (Photobacterium phosphoreum--Microtox{reg_sign} test, and a mixture of bacterial species--the Polytox{reg_sign} test). Standard acute toxicity test species included water fleas (Daphnia magna and Ceriodaphnia dubia), green algae (Selenastrum capricornutum), fathead minnows (Pimephales promelas), and mysid shrimp (Mysidopsis bahia). Sensitivity comparisons between rapid and standard acute toxicity tests were based on LC50/EC50 data from 11 test chemicals. Individually, the lettuce and rotifer tests ranked most similar in sensitivity to the standard tests, while Microtox fell just outside the range of sensitivities represented by the group of standard acute toxicity tests. The brine shrimp and Polytox tests were one or more orders of magnitude different from the standard acute toxicity tests for most compounds. The lettuce, rotifer, and Microtox tests could be used as a battery for preliminary toxicity screening of chemicals. Further evaluation of complex real-world environmental samples is recommended.

  8. Concolic Testing Koushik Sen

    E-Print Network [OSTI]

    Sen, Koushik

    Concolic testing automates test input generation by com­ bining the concrete and symbolic (concolic) execution of the code under test. Traditional test input generation tech­ niques use either (1) concrete test inputs from these constraints. In contrast, concolic testing tightly couples both concrete

  9. Concolic Testing Koushik Sen

    E-Print Network [OSTI]

    Sen, Koushik

    Concolic testing automates test input generation by com- bining the concrete and symbolic (concolic) execution of the code under test. Traditional test input generation tech- niques use either (1) concrete test inputs from these constraints. In contrast, concolic testing tightly couples both concrete

  10. Organic Separation Test Results

    SciTech Connect (OSTI)

    Russell, Renee L.; Rinehart, Donald E.; Peterson, Reid A.

    2014-09-22T23:59:59.000Z

    Separable organics have been defined as “those organic compounds of very limited solubility in the bulk waste and that can form a separate liquid phase or layer” (Smalley and Nguyen 2013), and result from three main solvent extraction processes: U Plant Uranium Recovery Process, B Plant Waste Fractionation Process, and Plutonium Uranium Extraction (PUREX) Process. The primary organic solvents associated with tank solids are TBP, D2EHPA, and NPH. There is concern that, while this organic material is bound to the sludge particles as it is stored in the tanks, waste feed delivery activities, specifically transfer pump and mixer pump operations, could cause the organics to form a separated layer in the tank farms feed tank. Therefore, Washington River Protection Solutions (WRPS) is experimentally evaluating the potential of organic solvents separating from the tank solids (sludge) during waste feed delivery activities, specifically the waste mixing and transfer processes. Given the Hanford Tank Waste Treatment and Immobilization Plant (WTP) waste acceptance criteria per the Waste Feed Acceptance Criteria document (24590-WTP-RPT-MGT-11-014) that there is to be “no visible layer” of separable organics in the waste feed, this would result in the batch being unacceptable to transfer to WTP. This study is of particular importance to WRPS because of these WTP requirements.

  11. Antarctic Mapping Project ACTIVE RADAR CALIBRATOR

    E-Print Network [OSTI]

    Howat, Ian M.

    RADARSAT Antarctic Mapping Project ACTIVE RADAR CALIBRATOR INSTALLATION DOCUMENT October, 1999 ENVIRONMENTAL RESEARCH INSTITUTE OF MICHIGAN CENTER FOR EARTH SCIENCES ALASKA SAR FACILITY BYRD POLAR RESEARCH...................................................................................................................................................3 Active Radar Calibrator Testing

  12. CLOSEOUT REPORT FOR HYBRID SULFUR PRESSURIZED BUTTON CELL TEST FACILITY

    SciTech Connect (OSTI)

    Steeper, T.

    2010-09-15T23:59:59.000Z

    This document is the Close-Out Report for design and partial fabrication of the Pressurized Button Cell Test Facility at Savannah River National Laboratory (SRNL). This facility was planned to help develop the sulfur dioxide depolarized electrolyzer (SDE) that is a key component of the Hybrid Sulfur Cycle for generating hydrogen. The purpose of this report is to provide as much information as possible in case the decision is made to resume research. This report satisfies DOE Milestone M3GSR10VH030107.0. The HyS Cycle is a hybrid thermochemical cycle that may be used in conjunction with advanced nuclear reactors or centralized solar receivers to produce hydrogen by watersplitting. The HyS Cycle utilizes the high temperature (>800 C) thermal decomposition of sulfuric acid to produce oxygen and regenerate sulfur dioxide. The unique aspect of HyS is the generation of hydrogen in a water electrolyzer that is operated under conditions where dissolved sulfur dioxide depolarizes the anodic reaction, resulting in substantial voltage reduction. Low cell voltage is essential for both high thermodynamic efficiency and low hydrogen cost. Sulfur dioxide is oxidized at the anode, producing sulfuric acid that is sent to the high temperature acid decomposition portion of the cycle. Sulfur dioxide from the decomposer is cycled back to electrolyzers. The electrolyzer cell uses the membrane electrode assembly (MEA) concept. Anode and cathode are formed by spraying a catalyst, typically platinized carbon, on both sides of a Proton Exchange Membrane (PEM). SRNL has been testing SDEs for several years including an atmospheric pressure Button Cell electrolyzer (2 cm{sup 2} active area) and an elevated temperature/pressure Single Cell electrolyzer (54.8 cm{sup 2} active area). SRNL tested 37 MEAs in the Single Cell electrolyzer facility from June 2005 until June 2009, when funding was discontinued. An important result of the final months of testing was the development of a method that prevents the formation of a sulfur layer previously observed in MEAs used in the Hybrid Sulfur Cycle electrolyzer. This result is very important because the sulfur layer increased cell voltage and eventually destroyed the MEA that is the heart of the cell. Steimke and Steeper [2005, 2006, 2007, 2008] reported on testing in the Single Cell Electrolyzer test facility in several periodic reports. Steimke et. al [2010] issued a final facility close-out report summarizing all the testing in the Single Cell Electrolyzer test facility. During early tests, significant deterioration of the membrane occurred in 10 hours or less; the latest tests ran for at least 200 hours with no sign of deterioration. Ironically, the success with the Single Cell electrolyzer meant that it became dedicated to long runs and not available for quick membrane evaluations. Early in this research period, the ambient pressure Button Cell Electrolyzer test facility was constructed to quickly evaluate membrane materials. Its small size allowed testing of newly developed membranes that typically were not available in sizes large enough to test in the Single Cell electrolyzer. The most promising membranes were tested in the Single Cell Electrolyzer as soon as sufficient large membranes could be obtained. However, since the concentration of SO{sub 2} gas in sulfuric acid decreases rapidly with increasing temperature, the ambient pressure Button Cell was no longer able to achieve the operating conditions needed to evaluate the newer improved high temperature membranes. Significantly higher pressure operation was required to force SO{sub 2} into the sulfuric acid to obtain meaningful concentrations at increased temperatures. A high pressure (200 psig), high temperature (120 C) Button Cell was designed and partially fabricated just before funding was discontinued in June 2009. SRNL completed the majority of the design of the test facility, including preparation of a process and instrument drawing (P&ID) and preliminary designs for the major components. SRNL intended to complete the designs and procu

  13. Radioactive material package seal tests

    SciTech Connect (OSTI)

    Madsen, M.M.; Humphreys, D.L.; Edwards, K.R.

    1990-01-01T23:59:59.000Z

    General design or test performance requirements for radioactive materials (RAM) packages are specified in Title 10 of the US Code of Federal Regulations Part 71 (US Nuclear Regulatory Commission, 1983). The requirements for Type B packages provide a broad range of environments under which the system must contain the RAM without posing a threat to health or property. Seals that provide the containment system interface between the packaging body and the closure must function in both high- and low-temperature environments under dynamic and static conditions. A seal technology program, jointly funded by the US Department of Energy Office of Environmental Restoration and Waste Management (EM) and the Office of Civilian Radioactive Waste Management (OCRWM), was initiated at Sandia National Laboratories. Experiments were performed in this program to characterize the behavior of several static seal materials at low temperatures. Helium leak tests on face seals were used to compare the materials. Materials tested include butyl, neoprene, ethylene propylene, fluorosilicone, silicone, Eypel, Kalrez, Teflon, fluorocarbon, and Teflon/silicone composites. Because most elastomer O-ring applications are for hydraulic systems, manufacturer low-temperature ratings are based on methods that simulate this use. The seal materials tested in this program with a fixture similar to a RAM cask closure, with the exception of silicone S613-60, are not leak tight (1.0 {times} 10{sup {minus}7} std cm{sup 3}/s) at manufacturer low-temperature ratings. 8 refs., 3 figs., 1 tab.

  14. Central serotonin neurons are required for arousal to CO2

    E-Print Network [OSTI]

    Central serotonin neurons are required for arousal to CO2 Gordon F. Buchanana,b,1 and George B neurons are stimulated by CO2, and sero- tonin activates thalamocortical networks, we hypothesized any arousal response to inhalation of 10% CO2 (with 21% O2 in balance N2) but had normal arousal

  15. Hanford Tanks Initiative requirements and document management process guide

    SciTech Connect (OSTI)

    Schaus, P.S.

    1998-05-22T23:59:59.000Z

    This revision of the guide provides updated references to project management level Program Management and Assessment Configuration Management activities, and provides working level directions for submitting requirements and project documentation related to the Hanford Tanks Initiative (HTI) project. This includes documents and information created by HTI, as well as non-HTI generated materials submitted to the project.

  16. PFBC HGCU Test Facility

    SciTech Connect (OSTI)

    Not Available

    1993-01-01T23:59:59.000Z

    This is the thirteenth Technical Progress Report submitted to the Department of Energy (DOE) in connection with the cooperative agreement between the DOE and Ohio Power Company for the Tidd PFBC Hot Gas Clean Up Test Facility. This report covers the period of work completed during the Fourth Quarter of CY 1992. The following are highlights of the activities that occurred during this report period: Initial operation of the Advanced Particle Filter (APF) occurred during this quarter. The following table summarizes the operating dates and times. HGCU ash lockhopper valve plugged with ash. Primary cyclone ash pluggage. Problems with the coal water paste. Unit restarted warm 13 hours later. HGCU expansion joint No. 7 leak in internal ply of bellows. Problems encountered during these initial tests included hot spots on the APP, backup cyclone and instrumentation spools, two breakdowns of the backpulse air compressor, pluggage of the APF hopper and ash removal system, failure (breakage) of 21 filter candles, leakage of the inner ply of one (1) expansion joint bellows, and numerous other smaller problems. These operating problems are discussed in detail in a subsequent section of this report. Following shutdown and equipment inspection in December, design modifications were initiated to correct the problems noted above. The system is scheduled to resume operation in March, 1993.

  17. 2011 Hyundai Sonata Hybrid - vin 3539 Advanced Vehicle Testing...

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

    Pack Capacity: 5.3 Ah Cooling: ActiveCabin Air Pack Weight: 96 lb BATTERY LABORATORY TEST RESULTS SUMMARY Vehicle Mileage and Testing Date Vehicle Odometer: 5,730 mi Date of...

  18. 2013 Chevrolet Volt - VIN 3929 - Advanced Vehicle Testing - Beginning...

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

    Voltage 3 : 3.00 V Thermal Management: Active - Liquid cooled BATTERY LABORATORY TEST RESULTS SUMMARY Vehicle Mileage and Testing Date Vehicle Odometer: 4,007 mi Date of...

  19. Requirements | Photosynthetic Antenna Research Center

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

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

  20. Iodine Sorbent Performance in FY 2012 Deep Bed Tests

    SciTech Connect (OSTI)

    Nick Soelberg; Tony Watson

    2012-08-01T23:59:59.000Z

    Nuclear fission results in the production of fission products and activation products, some of which tend to be volatile during used fuel reprocessing and evolve in gaseous species into the reprocessing facility off-gas systems. Analyses have shown that I-129, due to its radioactivity, high potential mobility in the environment, and high longevity (half life of 15.7 million years), can require control efficiencies of up to 1,000x or higher to meet regulatory emission limits. Iodine capture is an important aspect of the Separations and Waste Forms Campaign Off-gas Sigma Team (Jubin 2011, Pantano 2011). Deep-bed iodine sorption tests for both silver-functionalized Aerogel and silver zeolite sorbents were performed during Fiscal Year 2012. These tests showed that: • Decontamination factors were achieved that exceed reasonably conservative estimates for DFs needed for used fuel reprocessing facilities in the U.S. to meet regulatory requirements for I-129 capture. • Silver utilizations approached or exceeded 100% for high inlet gas iodine concentrations, but test durations were not long enough to approach 100% silver utilization for lower iodine concentrations. • The depth of the mass transfer zone was determined for both low iodine concentrations (under 10 ppmv) and for higher iodine concentrations (between 10-50 ppmv); the depth increases over time as iodine is sorbed. • These sorbents capture iodine by chemisorption, where the sorbed iodine reacts with the silver to form very non-volatile AgI. Any sorbed iodine that is physisorbed but not chemically reacted with silver to form AgI might not be tightly held by the sorbent. The portion of sorbed iodine that tends to desorb because it is not chemisorbed (reacted to form AgI) is small, under 1%, for the AgZ tests, and even smaller, under 0.01%, for the silver-functionalized Aerogel.

  1. Ion Exchange Testing with SRF Resin FY 2012

    SciTech Connect (OSTI)

    Russell, Renee L.; Rinehart, Donald E.; Peterson, Reid A.

    2014-07-02T23:59:59.000Z

    Ion exchange using spherical resorcinol-formaldehyde (SRF) resin has been selected by the U.S. Department of Energy’s Office of River Protection (DOE-ORP) for use in the Pretreatment Facility (PTF) of the Hanford Tank Waste Treatment and Immobilization Plant (WTP) and for potential application in at-tank deployment. Numerous studies have shown SRF resin to be effective for removing 137Cs from a wide variety of actual and simulated tank waste supernatants (Adamson et al. 2006; Blanchard et al. 2008; Burgeson et al. 2004; Duignan and Nash 2009; Fiskum et al. 2006a; Fiskum et al. 2006b; Fiskum et al. 2006c; Fiskum et al. 2007; Hassan and Adu-Wusu 2003; King et al. 2004; Nash et al. 2006). Prior work at the Pacific Northwest National Laboratory (PNNL) has focused primarily on the loading behavior for 4 to 6 M Na solutions at 25 to 45°C. Recent proposed changes to the WTP ion exchange process baseline indicate that loading may include a broader range of sodium molarities (0.1 to 8 M) and higher temperatures (50°C) to alleviate post-filtration precipitation issues. This report discusses ion exchange loading kinetics testing activities performed in accordance with Test Plan TP-WTPSP-002, Rev. 3.01, which was prepared and approved in response to the Test Specification 24590-PTF-TSP-RT-09-002, Rev. 0 (Lehrman 2010) and Test Exception 24590-PTF-TEF-RT-11-00003, Rev. 0 (Meehan 2011). This testing focused on column tests evaluating the impact of elevated temperature on resin degradation over an extended period of time and batch contacts evaluating the impact on Cs loading over a broad range of sodium concentrations (0.1 to 5 M). These changes may be required to alleviate post-filtration precipitation issues and broaden the data range of SRF resin loading under the conditions expected with the new equipment and process changes.

  2. Accelerated Stress Testing, Qualification Testing, HAST, Field...

    Office of Environmental Management (EM)

    stress tests beyond the qualification test levels, which are necessary to predict PV module wear-out. The commercial success of PVs is ultimately based on the long-term...

  3. Long-term testing

    SciTech Connect (OSTI)

    Ferber, M.; Graves, G.A. Jr.

    1994-12-31T23:59:59.000Z

    Land-based gas turbines are significantly different from automotive gas turbines in that they are designed to operate for 50,000 h or greater (compared to 5,000--10,000 h). The primary goal of this research is to determine the long-term survivability of ceramic materials for industrial gas turbine applications. Research activities in this program focus on the evaluation of the static tensile creep and stress rupture (SR) behavior of three commercially available structural ceramics which have been identified by the gas turbine manufacturers as leading candidates for use in industrial gas turbines. For each material investigated, a minimum of three temperatures and four stresses will be used to establish the stress and temperature sensitivities of the creep and SR behavior. Because existing data for many candidate structural ceramics are limited to testing times less than 2,000 h, this program will focus on extending these data to times on the order of 10,000 h, which represents the lower limit of operating time anticipated for ceramic blades and vanes in gas turbine engines. A secondary goal of the program will be to investigate the possibility of enhancing life prediction estimates by combining interrupted tensile SR tests and tensile dynamic fatigue tests in which tensile strength is measured as a function of stressing rate. The third goal of this program will be to investigate the effects of water vapor upon the SR behavior of the three structural ceramics chosen for the static tensile studies by measuring the flexural strength as a function of stressing rate at three temperatures.

  4. AMI FW UPGRADEABILITY TEST PROCEDURE AND SECURITY ASSESSMENT

    SciTech Connect (OSTI)

    Snyder, Isabelle B [ORNL] [ORNL

    2014-01-01T23:59:59.000Z

    The National Institute of Standards and Technology (NIST) is producing NISTIR 7823 to define test requirements for Smart Meter upgradability. The term Smart Meter refers specifically to advanced electric meters being deployed to enhance management of electricity distribution for residential and industrial consumers. The underlying functional and security requirements for Smart Meter upgradability are specified in NEMA standard SG-AMI 1-2009. The purpose of NISTIR 7823 is to describe conformance test requirements that may be used voluntarily by testers and/or test laboratories to determine whether Smart Meters and Upgrade Management Systems conform to the requirements of NEMA SG-AMI 1-2009.

  5. Regulatory requirements affecting disposal of asbestos-containing waste

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    Many U.S. Department of Energy (DOE) facilities are undergoing decontamination and decommissioning (D&D) activities. The performance of these activities may generate asbestos-containing waste because asbestos was formerly used in many building materials, including floor tile, sealants, plastics, cement pipe, cement sheets, insulating boards, and insulating cements. The regulatory requirements governing the disposal of these wastes depend on: (1) the percentage of asbestos in the waste and whether the waste is friable (easily crumbled or pulverized); (2) other physical and chemical characteristics of the waste; and (3) the State in which the waste is generated. This Information Brief provides an overview of the environment regulatory requirements affecting disposal of asbestos-containing waste. It does not address regulatory requirements applicable to worker protection promulgated under the Occupational Safety and Health Act (OSHAct), the Mining Safety and Health Act (MSHA), or the Toxic Substances Control Act (TSCA).

  6. Pressure Change Measurement Leak Testing Errors

    SciTech Connect (OSTI)

    Pryor, Jeff M [ORNL] [ORNL; Walker, William C [ORNL] [ORNL

    2014-01-01T23:59:59.000Z

    A pressure change test is a common leak testing method used in construction and Non-Destructive Examination (NDE). The test is known as being a fast, simple, and easy to apply evaluation method. While this method may be fairly quick to conduct and require simple instrumentation, the engineering behind this type of test is more complex than is apparent on the surface. This paper intends to discuss some of the more common errors made during the application of a pressure change test and give the test engineer insight into how to correctly compensate for these factors. The principals discussed here apply to ideal gases such as air or other monoatomic or diatomic gasses; however these same principals can be applied to polyatomic gasses or liquid flow rate with altered formula specific to those types of tests using the same methodology.

  7. Dual-Axis Resonance Testing of Wind Turbine Blades

    Energy Innovation Portal (Marketing Summaries) [EERE]

    2014-07-28T23:59:59.000Z

    Wind turbine blades must undergo strength and fatigue testing in order to be rated and marketed appropriately. Presently, wind turbine blades are fatigue-tested in the flapwise direction and in the edgewise direction independently. This testing involves placing the blades through 1 to 10 million or more load or fatigue cycles, which may take 3 to 12 months or more to complete for each tested direction. There is a need for blade testing techniques that are less expensive to use and require...

  8. TMACS test procedure TP001: Alarm management. Revision 6

    SciTech Connect (OSTI)

    Scanlan, P.K.

    1994-09-01T23:59:59.000Z

    The TMACS Software Project Test Procedures translate the project`s acceptance criteria into test steps. Software releases are certified when the affected Test Procedures are successfully performed and the customers authorize installation of these changes. This Test Procedure addresses the Alarm Management requirements of the TMACS. The features to be tested are: real-time alarming on high and low level and discrete alarms, equipment alarms, dead-band filtering, alarm display color coding, alarm acknowledgement, and alarm logging.

  9. Controller Field Tests on the NREL CART2 Turbine

    SciTech Connect (OSTI)

    Bossanyi, E.; Wright, A.; Fleming, P.

    2010-12-01T23:59:59.000Z

    This document presents the results of the field tests carried out on the CART2 turbine at NREL to validate individual pitch control and active tower damping.

  10. Flow Test At Valles Caldera - Sulphur Springs Geothermal Area...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Valles Caldera - Sulphur Springs Geothermal Area (Musgrave, Et Al., 1989)...

  11. Title Preactivity Survey Report for Five Tonopah Test Range Explosive...

    National Nuclear Security Administration (NNSA)

    Preactivity Survey Report for Five Tonopah Test Range Explosive Ordnance Disposal Sites Pre-activity survey report to clear areas to be cleaned up. No sensitive species were...

  12. Geographic Information System At Nevada Test And Training Range...

    Open Energy Info (EERE)

    Nevada Test And Training Range Area (Sabin, Et Al., 2004) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Geographic Information System At Nevada...

  13. Injectivity Test At Long Valley Caldera Geothermal Area (Farrar...

    Open Energy Info (EERE)

    Details Location Long Valley Caldera Geothermal Area Exploration Technique Injectivity Test Activity Date 1999 - 1999 Usefulness not useful DOE-funding Unknown Notes A second...

  14. NOx control subsystem test plan: LEBS Phase II

    SciTech Connect (OSTI)

    NONE

    1995-03-16T23:59:59.000Z

    It is planned that NO{sub x} control subsystem testing in support of Phase II of the Low-Emissions Boiler Systems (LEBS) Project occur in ABB Power Plant Laboratories` (PPL) pilot scale Boiler Simulation Facility (BSF). This work will be performed to provide necessary design and operational information for inclusion of an optimized NO, control subsystem in the Proof-of-Concept Test Facility (POCTF) and Commercial Generating Unit (CGU) designs. The BSF is a 50 to 90x10{sup 6} BTU/hr (15 to 26 MWt) coal, oil or natural gas fired tangential furnace designed to replicate the residence time/temperature history of a utility scale tangentially fired boiler. All major aspects of a typical utility boiler are duplicated in the BSF including the lower furnace, the ash hopper, multiple burner elevations, the arch section, superheater/reheater panels, and the convective heat transfer surfaces. The furnace walls and heat transfer surfaces are cooled by a surrounding water jacket. Steam generated is vented off at atmospheric pressure so that a constant sink temperature of 100{degrees}C (212{degrees}C) is maintained. The lower furnace water walls are selectively refractory lined to maintain an appropriate furnace gas temperature history. Refractory is required because the sink temperature (100{degrees}C) is cooler than that of a typical, utility boiler, and the surface-to-volume ratio of the BSF is greater than that of a utility boiler due to scale effects. For the subject testing, the BSF will be configured as a coal fired boiler. Design and planning activities associated with the construction of the NO{sub x} control subsystem test unit will continue through June, 1995. Additionally, the schedule for specification of certain low NO{sub x} firing system components was set to allow for precursor, internal and LEBS development activities to occur and subsequently provide necessary design parameters.

  15. Deep Bed Iodine Sorbent Testing FY 2011 Report

    SciTech Connect (OSTI)

    Nick Soelberg; Tony Watson

    2011-08-01T23:59:59.000Z

    Nuclear fission results in the production of fission products (FPs) and activation products that increasingly interfere with the fission process as their concentrations increase. Some of these fission and activation products tend to evolve in gaseous species during used nuclear fuel reprocessing. Analyses have shown that I129, due to its radioactivity, high potential mobility in the environment, and high longevity (half life of 15.7 million years), can require control efficiencies of up to 1,000x or higher to meet regulatory emission limits. Deep-bed iodine sorption testing has been done to evaluate the performance of solid sorbents for capturing iodine in off-gas streams from nuclear fuel reprocessing plants. The objectives of the FY 2011 deep bed iodine sorbent testing are: (1) Evaluate sorbents for iodine capture under various conditions of gas compositions and operating temperature (determine sorption efficiencies, capacities, and mass transfer zone depths); and (2) Generate data for dynamic iodine sorption modeling. Three tests performed this fiscal year on silver zeolite light phase (AgZ-LP) sorbent are reported here. Additional tests are still in progress and can be reported in a revision of this report or a future report. Testing was somewhat delayed and limited this year due to initial activities to address some questions of prior testing, and due to a period of maintenance for the on-line GC. Each test consisted of (a) flowing a synthetic blend of gases designed to be similar to an aqueous dissolver off-gas stream over the sorbent contained in three separate bed segments in series, (b) measuring each bed inlet and outlet gas concentrations of iodine and methyl iodide (the two surrogates of iodine gas species considered most representative of iodine species expected in dissolver off-gas), (c) operating for a long enough time to achieve breakthrough of the iodine species from at least one (preferably the first two) bed segments, and (d) post-test purging with pure N2 to drive loosely or physisorbed iodine species off of the sorbent. Post-test calculations determine the control efficiencies for each bed, iodine loadings on the sorbent, and mass transfer zone depths. Portions of the iodine-laden sorbent from the first bed of two of the tests have been shipped to SNL for waste form studies. Over the past three years, we have explored a full range of inlet iodine and methyl iodide concentrations ranging from {approx}100 ppb to {approx}100 ppm levels, and shown adequate control efficiencies within a bed depth as shallow as 2 inches for lower concentrations and 4 inches for higher concentrations, for the AgZ-type sorbents. We are now performing a limited number of tests in the NC-77 sorbent from SNL. Then we plan to continue to (a) fill in data gaps needed for isotherms and dynamic sorbent modeling, and (b) test the performance of additional sorbents under development.

  16. Final Report - LAW Envelope A and B Glass Formulations Testing in Increase Waste Loading. VSL-06R6900-1

    SciTech Connect (OSTI)

    Kruger, Albert A.; Joseph, I.; Muller, I. S.; Gong, W.; Gan, H.; Pegg, I. L.; Matlack, K. S.

    2013-12-03T23:59:59.000Z

    This report describes the results of testing specified by the Test Plan VSL-06R6900-1 Rev 0. The work was performed in compliance with quality assurance requirements specified in the Test Plan. Results required by the Test Plan are reported. The test results and this report have been reviewed for correctness, technical adequacy, completeness, and accuracy.

  17. Final Report - LAW Envelope C Glass Formulation Testing to Increase Waste Loading, VSL-05R5900-1

    SciTech Connect (OSTI)

    Kruger, Albert A.; Pegg, I. L.; Matlack, K. S.; Joseph, I.; Muller, I. S.; Gong, W.

    2013-12-03T23:59:59.000Z

    This report describes the results of testing specified by Test Plan VSL-05R5900-1 Rev.0. The work was performed in compliance with the quality assurance requirements specified in the Test Plan. Results required by the Test Plan are reported. The test results and this report have been reviewed for correctness, technical adequacy, completeness, and accuracy.

  18. 2007 Nissan Altima-7982 Hybrid Electric Vehicle Battery Test Results

    SciTech Connect (OSTI)

    Tyler Grey; Chester Motloch; James Francfort

    2010-01-01T23:59:59.000Z

    The U.S. Department of Energy's Advanced Vehicle Testing Activity conducts several different types of tests on hybrid electric vehicles, including testing hybrid electric vehicles batteries when both the vehicles and batteries are new, and at the conclusion of 160,000 miles of accelerated testing. This report documents the battery testing performed and battery testing results for the 2007 Nissan Altima hybrid electric vehicle (Vin Number 1N4CL21E27C177982). Testing was performed by the Electric Transportation Engineering Corporation. The Advanced Vehicle Testing Activity is part of the U.S. Department of Energy's Vehicle Technologies Program. The Idaho National Laboratory and the Electric Transportation Engineering Corporation conduct Advanced Vehicle Testing Activity for the U.S. Department of Energy.

  19. 2006 Toyota Highlander-5681 Hybrid Electric Vehicle Battery Test Results

    SciTech Connect (OSTI)

    Tyler Gray; Chester Motloch; James Francfort

    2010-01-01T23:59:59.000Z

    The U.S. Department of Energy's Advanced Vehicle Testing Activity conducts several different types of tests on hybrid electric vehicles, including testing hybrid electric vehicles batteries when both the vehicles and batteries are new, and at the conclusion of 160,000 miles of accelerated testing. This report documents the battery testing performed and battery testing results for the 2007 Toyota Highlander hybrid electric vehicle (Vin Number JTEDW21A860005681). Testing was performed by the Electric Transportation Engineering Corporation. The Advanced Vehicle Testing Activity is part of the U.S. Department of Energy's Vehicle Technologies Program. The Idaho National Laboratory and the Electric Transportation Engineering Corporation conduct Advanced Vehicle Testing Activity for the U.S. Department of Energy.

  20. 2006 Toyota Highlander-6395 Hyrid Electric Vehicle Battery Test Results

    SciTech Connect (OSTI)

    Tyler Gray; Chester Motloch; James Francfort

    2010-01-01T23:59:59.000Z

    The U.S. Department of Energy's Advanced Vehicle Testing Activity conducts several different types of tests on hybrid electric vehicles, including testing hybrid electric vehicles batteries when both the vehicles and batteries are new, and at the conclusion of 160,000 miles of accelerated testing. This report documents the battery testing performed and battery testing results for the 2007 Toyota Highlander hybrid electric vehicle (Vin Number JTEDW21A160006395). Testing was performed by the Electric Transportation Engineering Corporation. The Advanced Vehicle Testing Activity is part of the U.S. Department of Energy's Vehicle Technologies Program. The Idaho National Laboratory and the Electric Transportation Engineering Corporation conduct Advanced Vehicle Testing Activity for the U.S. Department of Energy.

  1. 2007 Toyota Camry-7129 Hybrid Electric Vehicle Battery Test Results

    SciTech Connect (OSTI)

    Tyler Gray; Chester Motloch; James Francfort

    2010-01-01T23:59:59.000Z

    The U.S. Department of Energy's Advanced Vehicle Testing Activity conducts several different types of tests on hybrid electric vehicles, including testing hybrid electric vehicles batteries when both the vehicles and batteries are new, and at the conclusion of 160,000 miles of accelerated testing. This report documents the battery testing performed and battery testing results for the 2007 Toyota Camry hybrid electric vehicle (Vin Number JTNBB46K773007129). Testing was performed by the Electric Transportation Engineering Corporation. The Advanced Vehicle Testing Activity is part of the U.S. Department of Energy's Vehicle Technologies Program. The Idaho National Laboratory and the Electric Transportation Engineering Corporation conduct Advanced Vehicle Testing Activity for the U.S. Department of Energy.

  2. 2011 Hyundai Sonata 3539 - Hybrid Electric Vehicle Battery Test Results

    SciTech Connect (OSTI)

    Matthew Shirk; Tyler Gray; Jeffrey Wishart

    2014-09-01T23:59:59.000Z

    The U.S. Department of Energy’s Advanced Vehicle Testing Activity Program consists of vehicle, battery, and infrastructure testing on advanced technology related to transportation. The activity includes tests on hybrid electric vehicles, including testing hybrid electric vehicle batteries when both the vehicles and batteries are new and at the conclusion of 160,000 miles of on-road fleet testing. This report documents battery testing performed for the 2011 Hyundai Sonata Hybrid (VIN KMHEC4A47BA003539). Battery testing was performed by Intertek Testing Services NA. The Idaho National Laboratory and Intertek collaborate on the Advanced Vehicle Testing Activity for the Vehicle Technologies Program of the U.S. Department of Energy.

  3. Formulation of a candidate glass for use as an acceptance test standard material

    SciTech Connect (OSTI)

    Ebert, W.L.; Strachan, D.M.; Wolf, S.F.

    1998-04-01T23:59:59.000Z

    In this report, the authors discuss the formulation of a glass that will be used in a laboratory testing program designed to measure the precision of test methods identified in the privatization contracts for the immobilization of Hanford low-activity wastes. Tests will be conducted with that glass to measure the reproducibility of tests and analyses that must be performed by glass producers as a part of the product acceptance procedure. Test results will be used to determine if the contractually required tests and analyses are adequate for evaluating the acceptability of likely immobilized low-activity waste (ILAW) products. They will also be used to evaluate if the glass designed for use in these tests can be used as an analytical standard test material for verifying results reported by vendors for tests withg ILAW products. The results of those tests and analyses will be presented in a separate report. The purpose of this report is to document the strategy used to formulate the glass to be used in the testing program. The low-activity waste reference glass LRM that will be used in the testing program was formulated to be compositionally similar to ILAW products to be made with wastes from Hanford. Since the ILAW product compositions have not been disclosed by the vendors participating in the Hanford privatization project, the composition of LRM was formulated based on simulated Hanford waste stream and amounts of added glass forming chemicals typical for vitrified waste forms. The major components are 54 mass % SiO{sub 2}, 20 mass % Na{sub 2}O, 10 mass % Al{sub 2}O{sub 3}, 8 mass % B{sub 2}O{sub 3}, and 1.5 mass % K{sub 2}O. Small amounts of other chemicals not present in Hanford wastes were also included in the glass, since they may be included as chemical additives in ILAW products. This was done so that the use of LRM as a composition standard could be evaluated. Radionuclides were not included in LRM because a nonradioactive material was desired.

  4. Assessment of Quality Assurance Measures for Radioactive Material Transport Packages not Requiring Competent Authority Design Approval - 13282

    SciTech Connect (OSTI)

    Komann, Steffen; Groeke, Carsten; Droste, Bernhard [BAM Federal Institute for Materials Research and Testing, Unter den Eichen 44-46, 12203 Berlin (Germany)] [BAM Federal Institute for Materials Research and Testing, Unter den Eichen 44-46, 12203 Berlin (Germany)

    2013-07-01T23:59:59.000Z

    The majority of transports of radioactive materials are carried out in packages which don't need a package design approval by a competent authority. Low-active radioactive materials are transported in such packages e.g. in the medical and pharmaceutical industry and in the nuclear industry as well. Decommissioning of NPP's leads to a strong demand for packages to transport low and middle active radioactive waste. According to IAEA regulations the 'non-competent authority approved package types' are the Excepted Packages and the Industrial Packages of Type IP-1, IP-2 and IP-3 and packages of Type A. For these types of packages an assessment by the competent authority is required for the quality assurance measures for the design, manufacture, testing, documentation, use, maintenance and inspection (IAEA SSR 6, Chap. 306). In general a compliance audit of the manufacturer of the packaging is required during this assessment procedure. Their regulatory level in the IAEA regulations is not comparable with the 'regulatory density' for packages requiring competent authority package design approval. Practices in different countries lead to different approaches within the assessment of the quality assurance measures in the management system as well as in the quality assurance program of a special package design. To use the package or packaging in a safe manner and in compliance with the regulations a management system for each phase of the life of the package or packaging is necessary. The relevant IAEA-SSR6 chap. 801 requires documentary verification by the consignor concerning package compliance with the requirements. (authors)

  5. IDENTIFICATION OF DOE'S POST-CLOSURE MONITORING NEEDS AND REQUIREMENTS

    SciTech Connect (OSTI)

    M.A. Ebadian, Ph.D.

    1999-01-01T23:59:59.000Z

    The 2006 plan sets an ambitious agenda for the U.S. Department of Energy (DOE), Office of Environmental Management (EM) and the remediation of sites contaminated by decades of nuclear weapons production activities. The plan's primary objective is to reduce overall clean up costs by first eliminating the environmental problems that are most expensive to control and safely maintain. In the context of the 2006 Plan, closure refers to the completion of area or facility specific cleanup projects. The cleanup levels are determined by the planned future use of the site or facility. Use restrictions are still undecided for most sites but are highly probable to exclude residential or agricultural activities. Most of the land will be remediated to ''industrial use'' levels with access restrictions and some areas will be closed-off through containment. Portions of the site will be reserved for waste disposal, either as a waste repository or the in-situ immobilization of contaminated soil and groundwater, and land use will be restricted to waste disposal only. The land used for waste disposal will require monitoring and maintenance activities after closure. Most of the land used for industrial use may also require such postclosure activities. The required postclosure monitoring and maintenance activities will be imposed by regulators and stakeholders. Regulators will not approve closure plans without clearly defined monitoring methods using approved technologies. Therefore, among all other more costly and labor-intensive closure-related activities, inadequate planning for monitoring and lack of appropriate monitoring technologies can prevent closure. The purpose of this project is to determine, document, and track the current and evolving postclosure monitoring requirements at DOE-EM sites. This information will aid CMST-CP in guiding its postclosure technology development and deployment efforts.

  6. Seismic Performance Requirements for WETF

    SciTech Connect (OSTI)

    Hans Jordan

    2001-01-01T23:59:59.000Z

    This report develops recommendations for requirements on the Weapons Engineering Tritium Facility (WETF) performance during seismic events. These recommendations are based on fragility estimates of WETF structures, systems, and components that were developed by LANL experts during facility walkdowns. They follow DOE guidance as set forth in standards DOE-STD-1021-93, ''Natural Phenomena Hazards Performance Categorization Guidelines for Structures, Systems, and Components'' and DOE-STD-1020-94, ''Natural Phenomena Hazards Design and Evaluation Criteria for Department of Energy Facilities''. Major recommendations are that WETF institute a stringent combustible loading control program and that additional seismic bracing and anchoring be provided for gloveboxes and heavy equipment.

  7. Stellar Astrophysics Requirements NERSC Forecast

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over Our Instagram Secretary900Steep Slope Calculator Estimates Cooling andRequirements

  8. Physics Degree Requirements 2008 -2010 Bulletin

    E-Print Network [OSTI]

    Dyer, Bill

    Physics Degree Requirements 2008 -2010 Bulletin Professional Option Student: __________________________ Advisor: ____________________________ Updated 2/8/08 Physics Required Cr Gr Taken PHYS 137 1 ___ ______ PHYS 461 4 ___ ______ PHYS 490 3 ___ ______ Subtotal 47 (C- or better required) Physics Electives (8 cr

  9. HEP/NP Requirements Review 2013

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

    FES Requirements Review 2014 BES Requirements Review 2014 Requirements Review Reports Case Studies Contact Us Technical Assistance: 1 800-33-ESnet (Inside US) 1 800-333-7638...

  10. DOE-STD-1104 Requirements Crosswalk

    Office of Environmental Management (EM)

    09 to DOE-STD-1104-2014 Requirements Matrix - 1 - No. Section Page Number DOE-STD-1104-2009 Requirement DOE-STD-1104-2014 Requirements Comment Gen DOE-STD-1104-2009 was broadly...

  11. A Requirements Analyst's Apprentice: A Proposal

    E-Print Network [OSTI]

    Reubenstein, Howard

    The Requirements Analyst's APprentice (RAAP) partially automates the modeling process involved in creating a software requirement. It uses knowledge of the specific domain and general experience regarding software requirements ...

  12. Advanced Test Reactor Testing Experience: Past, Present and Future

    SciTech Connect (OSTI)

    Frances M. Marshall

    2005-04-01T23:59:59.000Z

    The Advanced Test Reactor (ATR), at the Idaho National Laboratory (INL), is one of the world’s premier test reactors for providing the capability for studying the effects of intense neutron and gamma radiation on reactor materials and fuels. The physical configuration of the ATR, a 4-leaf clover shape, allows the reactor to be operated at different power levels in the corner “lobes” to allow for different testing conditions for multiple simultaneous experiments. The combination of high flux (maximum thermal neutron fluxes of 1E15 neutrons per square centimeter per second and maximum fast [E>1.0 MeV] neutron fluxes of 5E14 neutrons per square centimeter per second) and large test volumes (up to 48" long and 5.0" diameter) provide unique testing opportunities. The current experiments in the ATR are for a variety of test sponsors -- US government, foreign governments, private researchers, and commercial companies needing neutron irradiation services. There are three basic types of test configurations in the ATR. The simplest configuration is the sealed static capsule, wherein the target material is placed in a capsule, or plate form, and the capsule is in direct contact with the primary coolant. The next level of complexity of an experiment is an instrumented lead experiment, which allows for active monitoring and control of experiment conditions during the irradiation. The highest level of complexity of experiment is the pressurized water loop experiment, in which the test sample can be subjected to the exact environment of a pressurized water reactor. For future research, some ATR modifications and enhancements are currently planned. This paper provides more details on some of the ATR capabilities, key design features, experiments, and future plans.

  13. Beryllium Use in the Advanced Test Reactor

    SciTech Connect (OSTI)

    Glen R. Longhurst

    2007-12-01T23:59:59.000Z

    The Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) began operation in 1967. It makes use of a unique serpentine fuel core design and a beryllium reflector. Reactor control is achieved with rotating beryllium cylinders to which have been fastened plates of hafnium. Over time, the beryllium develops rather high helium content because of nuclear transmutations and begins to swell. The beryllium must be replaced at nominally 10-year intervals. Determination of when the replacement is made is by visual observation using a periscope to examine the beryllium surface for cracking and swelling. Disposition of the irradiated beryllium was once accomplished in the INL’s Radioactive Waste Management Complex, but that is no longer possible. Among contributing reasons are high levels of specific radioactive contaminants including transuranics. The INL is presently considering disposition pathways for this irradiated beryllium, but presently is storing it in the canal adjacent to the reactor. Numerous issues are associated with this situation including (1) Is there a need for ultra-low uranium material? (2) Is there a need to recover tritium from irradiated beryllium either because this is a strategic material resource or in preparation for disposal? (3) Is there a need to remove activation and fission products from irradiated beryllium? (4) Will there be enough material available to meet requirements for research reactors (fission and fusion)? In this paper will be discussed the present status of considerations on these issues.

  14. RMOTC - Testing - Geothermal

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

    Geothermal Testing Notice: As of July 1st, 2014, Testing at RMOTC has officially completed. We would like to thank all of our testing partners and everyone who helped make the...

  15. Test Herrera Report Template

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

    development are described in detail in the following section. The model was run in six test sites: Test Site 1 is along the Cowlitz River (Segment 3); Test Site 2 includes the...

  16. ZiaTest

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

    ZiaTest ZiaTest Description This test executes a new proposed standard benchmark method for MPI startup that is intended to provide a realistic assessment of both launch and wireup...

  17. Directed random testing

    E-Print Network [OSTI]

    Pacheco, Carlos, Ph.D. Massachusetts Institute of Technology

    2009-01-01T23:59:59.000Z

    Random testing can quickly generate many tests, is easy to implement, scales to large software applications, and reveals software errors. But it tends to generate many tests that are illegal or that exercise the same parts ...

  18. Studying the Communications Requirements of Electric Utilities...

    Office of Environmental Management (EM)

    Studying the Communications Requirements of Electric Utilities to Inform Federal Smart Grid Policies- Public Meeting Studying the Communications Requirements of Electric Utilities...

  19. Microsoft Word - Requirements_list.docx

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

    SELECTED LIST OF REQUIREMENTS DESCRIPTION REQUIREMENT APPLICABILITY 1. Federal Motor Carrier Registration 49 CFR 390.19; 390.21 Motor carriers that conduct commercial motor vehicle...

  20. Required Training for Users | Advanced Photon Source

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

    Required Training for Users All APS users, including APS staff, resident users, general users, etc., must complete the required "core" courses listed below before participating in...

  1. Bioinformatics and Genomics Degree Requirements Booklet

    E-Print Network [OSTI]

    dePamphilis, Claude

    Bioinformatics and Genomics Degree Requirements Booklet Fall 2010 #12;Contents Course Requirements Bioinformatics and Genomics Curriculum -------------------------------------------------------8 General #12;Bioinformatics and Genomics Option (BG

  2. Hazardous Waste Minimum Distance Requirements (Connecticut)

    Broader source: Energy.gov [DOE]

    These regulations set minimum distance requirements between certain types of facilities that generate, process, store, and dispose of hazardous waste and other land uses. The regulations require an...

  3. Cold vacuum drying facility design requirements

    SciTech Connect (OSTI)

    IRWIN, J.J.

    1999-07-01T23:59:59.000Z

    This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified.

  4. Calendar year 2007 annual site environmental report for Tonopah Test range, Nevada and Kauai Test Facility, Hawaii,

    SciTech Connect (OSTI)

    Agogino, Karen [Department of Energy, Albuquerque, NM (US), NNSA; Sanchez, Rebecca [Sandia Corp., Albuquerque, NM (US)

    2008-09-30T23:59:59.000Z

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation (Sandia), a wholly owned subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE)/National Nuclear Security Administration (NNSA), through the Sandia Site Offi ce (SSO), in Albuquerque, NM, administers the contract and oversees contractor operations at TTR and KTF. Sandia manages and conducts operations at TTR in support of the DOE/NNSA’s Weapons Ordnance Program and has operated the site since 1957. Washington Group International subcontracts to Sandia in administering most of the environmental programs at TTR. Sandia operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2007. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia is responsible only for those environmental program activities related to its operations. The DOE/NNSA/Nevada Site Offi ce (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2007a) and DOE Manual 231.1-1A, Environment, Safety, and Health Reporting Manual (DOE 2007).

  5. Calendar year 2002 annual site environmental report for Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii.

    SciTech Connect (OSTI)

    Wagner, Katrina; Sanchez, Rebecca V.; Mayeux, Lucie; Koss, Susan I.; Salinas, Stephanie A.

    2003-09-01T23:59:59.000Z

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, oversees TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2002. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 5400.1, General Environmental Protection Program (DOE 1990) and DOE Order 231.1, Environment, Safety, and Health Reporting (DOE 1996).

  6. Enhancement of La0.6Sr0.4Co0.2Fe0.8O3-? Durability and Surface Electro-catalytic Activity by La0.85Sr0.15MnO3-? Investigated using a New Test Electrode Platform

    SciTech Connect (OSTI)

    Lynch, Matthew; Yang, Lei; Qin, Wentao; Choi, Jongjin; Liu, Mingfei; Blinn, Kevin; Liu, Meilin

    2011-01-01T23:59:59.000Z

    A carefully designed test cell platform with a new electrode structure is utilized to determine the intrinsic surface catalytic properties of an electrode. With this design, the electrocatalytic activity and stability of an La{sub 0.6}Sr{sub 0.4}Co{sub 0.2}Fe{sub 0.8}O{sub 3??} (LSCF) cathode is enhanced by a dense thin La{sub 0.85}Sr{sub 0.15}MnO{sub 3±?} (LSM) coating, suggesting that an efficient electrode architecture has been demonstrated that can make effective use of desirable properties of two different materials: fast ionic and electronic transport in the backbone (LSCF) and facile surface kinetics on the thin-film coating (LSM). Theoretical analyses suggest that the enhanced electrocatalytic activity of LSM-coated LSCF is attributed possibly to surface activation under cathodic polarization due to the promotion of oxygen adsorption and/or dissociation by the surface layer and the dramatically increased oxygen vacancy population in the surface film. Further, the observed time-dependent activation over a few hundreds of hours and durability are likely associated with the formation of a favorable hybrid surface phase intermediate between LSM and LSCF. This efficient electrode architecture was successfully applied to the state-of-the-art LSCF-based cathodes by a simple solution infiltration process, achieving reduced interfacial resistance and improved stability under fuel cell operating conditions.

  7. 1998 Annual Site Environmental Report Tonopah Test Range, Nevada

    SciTech Connect (OSTI)

    Duncan, D.K.; Fink, C.H.; Sanchez, R.V.

    1999-09-01T23:59:59.000Z

    Sandia National Laboratories (SNL) operates the Tonopah Test Range (TTR) for the Department of Energy (DOE) Weapons Ordnance Program. This annual report (calendar year 1998) summarizes the compliance status to environmental regulations applicable at the site including those statutes that govern air and water quality, waste management cleanup of contaminated areas, control of toxic substances, and adherence to requirements as related to the National Environmental Policy Act (NEPA). In compliance with DOE orders, SNL also conducts environmental surveillance for radiological and nonradiological contaminants. SNL's responsibility for environmental surveillance at TTR extends only to those areas where SNL activities are carried out. Annual radiological and nonradiological routine releases and unplanned releases (occurrences) are also summarized. This report has been prepared in accordance with DOE Order 5400.1, General Environmental Protection Program (DOE 1990a).

  8. PRESSURE ACTIVATED SEALANT TECHNOLOGY

    SciTech Connect (OSTI)

    Michael A. Romano

    2004-04-01T23:59:59.000Z

    The objective of this project is to develop new, efficient, cost effective methods of internally sealing natural gas pipeline leaks through the application of differential pressure activated sealants. In researching the current state of the art for gas pipeline sealing technologies we concluded that if the project was successful, it appeared that pressure activated sealant technology would provide a cost effective alternative to existing pipeline repair technology. From our analysis of current field data for a 13 year period from 1985 to 1997 we were able to identify 205 leaks that were candidates for pressure activated sealant technology, affirming that pressure activated sealant technology is a viable option to traditional external leak repairs. The data collected included types of defects, areas of defects, pipe sizes and materials, incident and operating pressures, ability of pipeline to be pigged and corrosion states. This data, and subsequent analysis, was utilized as a basis for constructing applicable sealant test modeling.

  9. AVTA: 2010 Ford Fusion HEV Testing Results

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. These results provide benchmark data that researchers can use to develop technology models and guide future research and development. The following reports describe results of testing done on a 2010 Ford Fusion hybrid-electric vehicle. Baseline data, which provides a point of comparison for the other test results, was collected at two different research laboratories. Baseline and other data collected at Idaho National Laboratory is in the attached documents. Baseline and battery testing data collected at Argonne National Laboratory is available in summary and CSV form on the Argonne Downloadable Dynometer Database site (http://www.transportation.anl.gov/D3/2010_fusion_hybrid.html). Taken together, these reports give an overall view of how this vehicle functions under extensive testing.

  10. AVTA: 2011 Hyundai Sonata HEV Testing Results

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. These results provide benchmark data that researchers can use to develop technology models and guide future research and development. The following reports describe results of testing done on a 2011 Hyundai Sonata hybrid electric vehicle. Baseline data, which provides a point of comparison for the other test results, was collected at two different research laboratories. Baseline and other data collected at Idaho National Laboratory is in the attached documents. Baseline and battery testing data collected at Argonne National Laboratory is available in summary and CSV form on the Argonne Downloadable Dynometer Database site (http://www.anl.gov/energy-systems/group/downloadable-dynamometer-databas...). Taken together, these reports give an overall view of how this vehicle functions under extensive testing.

  11. LANSCE | Materials Test Station

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

    Research Facility Training Office Contact Administrative nav background Materials Test Station dotline Testing New Reactor Fuels that Reduce Radioactive Waste Mission Used...

  12. High Temperature Calcination - MACT Upgrade Equipment Pilot Plant Test

    SciTech Connect (OSTI)

    Richard D. Boardman; B. H. O'Brien; N. R. Soelberg; S. O. Bates; R. A. Wood; C. St. Michel

    2004-02-01T23:59:59.000Z

    About one million gallons of acidic, hazardous, and radioactive sodium-bearing waste are stored in stainless steel tanks at the Idaho Nuclear Technology and Engineering Center (INTEC), which is a major operating facility of the Idaho National Engineering and Environmental Laboratory. Calcination at high-temperature conditions (600 C, with alumina nitrate and calcium nitrate chemical addition to the feed) is one of four options currently being considered by the Department of Energy for treatment of the remaining tank wastes. If calcination is selected for future processing of the sodium-bearing waste, it will be necessary to install new off-gas control equipment in the New Waste Calcining Facility (NWCF) to comply with the Maximum Achievable Control Technology (MACT) standards for hazardous waste combustors and incinerators. This will require, as a minimum, installing a carbon bed to reduce mercury emissions from their current level of up to 7,500 to <45 {micro}g/dscm, and a staged combustor to reduce unburned kerosene fuel in the off-gas discharge to <100 ppm CO and <10 ppm hydrocarbons. The staged combustor will also reduce NOx concentrations of about 35,000 ppm by 90-95%. A pilot-plant calcination test was completed in a newly constructed 15-cm diameter calciner vessel. The pilot-plant facility was equipped with a prototype MACT off-gas control system, including a highly efficient cyclone separator and off-gas quench/venturi scrubber for particulate removal, a staged combustor for unburned hydrocarbon and NOx destruction, and a packed activated carbon bed for mercury removal and residual chloride capture. Pilot-plant testing was performed during a 50-hour system operability test January 14-16, followed by a 100-hour high-temperature calcination pilot-plant calcination run January 19-23. Two flowsheet blends were tested: a 50-hour test with an aluminum-to-alkali metal molar ratio (AAR) of 2.25, and a 50-hour test with an AAR of 1.75. Results of the testing indicate that sodium-bearing waste can be successfully calcined at 600 C with an AAR of 1.75. Unburned hydrocarbons are reduced to less than 10 ppm (7% O2, dry basis), with >90% reduction of NOx emissions. Mercury removal by the carbon bed reached 99.99%, surpassing the control efficiency needed to meet MACT emissions standards. No deleterious impacts on the carbon bed were observed during the tests. The test results imply that upgrading the NWCF calciner with a more efficient cyclone separator and the proposed MACT equipment can process the remaining tanks wastes in 3 years or less, and comply with the MACT standards.

  13. Vendor System Vulnerability Testing Test Plan

    SciTech Connect (OSTI)

    James R. Davidson

    2005-01-01T23:59:59.000Z

    The Idaho National Laboratory (INL) prepared this generic test plan to provide clients (vendors, end users, program sponsors, etc.) with a sense of the scope and depth of vulnerability testing performed at the INL’s Supervisory Control and Data Acquisition (SCADA) Test Bed and to serve as an example of such a plan. Although this test plan specifically addresses vulnerability testing of systems applied to the energy sector (electric/power transmission and distribution and oil and gas systems), it is generic enough to be applied to control systems used in other critical infrastructures such as the transportation sector, water/waste water sector, or hazardous chemical production facilities. The SCADA Test Bed is established at the INL as a testing environment to evaluate the security vulnerabilities of SCADA systems, energy management systems (EMS), and distributed control systems. It now supports multiple programs sponsored by the U.S. Department of Energy, the U.S. Department of Homeland Security, other government agencies, and private sector clients. This particular test plan applies to testing conducted on a SCADA/EMS provided by a vendor. Before performing detailed vulnerability testing of a SCADA/EMS, an as delivered baseline examination of the system is conducted, to establish a starting point for all-subsequent testing. The series of baseline tests document factory delivered defaults, system configuration, and potential configuration changes to aid in the development of a security plan for in depth vulnerability testing. The baseline test document is provided to the System Provider,a who evaluates the baseline report and provides recommendations to the system configuration to enhance the security profile of the baseline system. Vulnerability testing is then conducted at the SCADA Test Bed, which provides an in-depth security analysis of the Vendor’s system.b a. The term System Provider replaces the name of the company/organization providing the system being evaluated. This can be the system manufacturer, a system user, or a third party organization such as a government agency. b. The term Vendor (or Vendor’s) System replaces the name of the specific SCADA/EMS being tested.

  14. National Ignition Facility system design requirements Laser System SDR002

    SciTech Connect (OSTI)

    Larson, D.W.; Bowers, J.M.; Bliss, E.S.; Karpenko, V.P.; English, E.

    1996-08-20T23:59:59.000Z

    This System Design Requirement document establishes the performance, design, development, and test requirements for the NIP Laser System. The Laser System generates and delivers high-power optical pulses to the target chamber, and is composed of all optical puke creating and transport elements from Puke Generation through Final Optics as well as the special equipment that supports, energizes and controls them. The Laser System consists of the following WBS elements: 1.3 Laser System 1.4 Beam Transport System 1.6 Optical Components 1.7 Laser Control 1.8.7 Final Optics.

  15. A Test Calculus Framework applied to network security policies

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    A Test Calculus Framework applied to network security policies Yli`es Falcone1 , Jean'H`eres, France Abstract. We propose a syntax-driven test generation technique to au- tomaticaly derive abstract test cases from a set of requirements expressed in a linear temporal logic. Assuming that an elementary

  16. State Waste Discharge Permit Application: Electric resistance tomography testing

    SciTech Connect (OSTI)

    Not Available

    1994-04-01T23:59:59.000Z

    This permit application documentation is for a State Waste Discharge Permit issued in accordance with requirements of Washington Administrative Code 173-216. The activity being permitted is a technology test using electrical resistance tomography. The electrical resistance tomography technology was developed at Lawrence Livermore National Laboratory and has been used at other waste sites to track underground contamination plumes. The electrical resistance tomography technology measures soil electrical resistance between two electrodes. If a fluid contaminated with electrolytes is introduced into the soil, the soil resistance is expected to drop. By using an array of measurement electrodes in several boreholes, the areal extent of contamination can be estimated. At the Hanford Site, the purpose of the testing is to determine if the electrical resistance tomography technology can be used in the vicinity of large underground metal tanks without the metal tank interfering with the test. It is anticipated that the electrical resistance tomography technology will provide a method for accurately detecting leaks from the bottom of underground tanks, such as the Hanford Site single-shell tanks.

  17. Cosmological Tests of Gravity

    E-Print Network [OSTI]

    Koyama, Kazuya

    2015-01-01T23:59:59.000Z

    Einstein's theory of General Relativity (GR) is tested accurately within the local universe i.e., the Solar System, but this leaves open the possibility that it is not a good description at the largest scales in the Universe. The standard model of cosmology assumes GR as the theory to describe gravity on all scales. In 1998, astronomers made the surprising discovery that the expansion of the Universe is accelerating, not slowing down. This late-time acceleration of the Universe has become the most challenging problem in theoretical physics. Within the framework of GR, the acceleration would originate from an unknown dark energy. Alternatively, it could be that there is no dark energy and GR itself is in error on cosmological scales. The standard model of cosmology is based on a huge extrapolation of our limited knowledge of gravity. This discovery of the late time acceleration of the Universe may require us to revise the theory of gravity and the standard model of cosmology based on GR. We will review recent ...

  18. Documents Required by the Office of Academic Affairs for Clinician Educator Actions, October 2014 Rank Action Duration Required documents (Number of letters shown are minimums)

    E-Print Network [OSTI]

    Puglisi, Joseph

    Documents Required by the Office of Academic Affairs for Clinician Educator Actions, October 2014 Rank Action Duration Required documents (Number of letters shown are minimums) Clinical Instructor% FTE or greater and who have outside clinical activity, http://med.stanford.edu/academicaffairs/documents

  19. Initial field testing definition of subsurface sealing and backfilling tests in unsaturated tuff; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Fernandez, J.A. [Sandia National Labs., Albuquerque, NM (United States); Case, J.B.; Tyburski, J.R. [I. T. Corp., Albuquerque, NM (United States)

    1993-05-01T23:59:59.000Z

    This report contains an initial definition of the field tests proposed for the Yucca Mountain Project repository sealing program. The tests are intended to resolve various performance and emplacement concerns. Examples of concerns to be addressed include achieving selected hydrologic and structural requirements for seals, removing portions of the shaft liner, excavating keyways, emplacing cementitious and earthen seals, reducing the impact of fines on the hydraulic conductivity of fractures, efficient grouting of fracture zones, sealing of exploratory boreholes, and controlling the flow of water by using engineered designs. Ten discrete tests are proposed to address these and other concerns. These tests are divided into two groups: Seal component tests and performance confirmation tests. The seal component tests are thorough small-scale in situ tests, the intermediate-scale borehole seal tests, the fracture grouting tests, the surface backfill tests, and the grouted rock mass tests. The seal system tests are the seepage control tests, the backfill tests, the bulkhead test in the Calico Hills unit, the large-scale shaft seal and shaft fill tests, and the remote borehole sealing tests. The tests are proposed to be performed in six discrete areas, including welded and non-welded environments, primarily located outside the potential repository area. The final selection of sealing tests will depend on the nature of the geologic and hydrologic conditions encountered during the development of the Exploratory Studies Facility and detailed numerical analyses. Tests are likely to be performed both before and after License Application.

  20. Letter Report: LAW Simulant Development for Cast Stone Screening Test

    SciTech Connect (OSTI)

    Russell, Renee L.; Westsik, Joseph H.; Swanberg, David J.; Eibling, Russell E.; Cozzi, Alex; Lindberg, Michael J.; Josephson, Gary B.; Rinehart, Donald E.

    2013-03-27T23:59:59.000Z

    More than 56 million gallons of radioactive and hazardous waste are stored in 177 underground storage tanks at the U.S. Department of Energy’s (DOE’s) Hanford Site in southeastern Washington State. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the wastes and immobilize them in a glass waste form. The WTP includes a pretreatment facility to separate the wastes into a small volume of high-level waste (HLW) containing most of the radioactivity and a larger volume of low-activity waste (LAW) containing most of the nonradioactive chemicals. The HLW will be converted to glass in the HLW vitrification facility for ultimate disposal at an offsite federal repository. At least a portion (~35%) of the LAW will be converted to glass in the LAW vitrification facility and will be disposed of onsite at the Integrated Disposal Facility (IDF). The pretreatment and HLW vitrification facilities will have the capacity to treat and immobilize the wastes destined for each facility. However, a second facility will be needed for the expected volume of additional LAW requiring immobilization. A cementitious waste form known as Cast Stone is being considered to provide the required additional LAW immobilization capacity. The Cast Stone waste form must be acceptable for disposal in the IDF. The Cast Stone waste form and immobilization process must be tested to demonstrate that the final Cast Stone waste form can comply with waste acceptance criteria for the IDF disposal facility and that the immobilization processes can be controlled to consistently provide an acceptable waste form product. Further, the waste form must be tested to provide the technical basis for understanding the long term performance of the waste form in the IDF disposal environment. These waste form performance data are needed to support risk assessment and performance assessment (PA) analyses of the long-term environmental impact of the waste disposal in the IDF. A testing program was developed in fiscal year (FY) 2012 describing in some detail the work needed to develop and qualify Cast Stone as a waste form for the solidification of Hanford LAW (Westsik et al. 2012). Included within Westsik et al. (2012) is a section on the near-term needs to address Tri-Party Agreement Milestone M-062-40ZZ. The objectives of the testing program to be conducted in FY 2013 and FY 2014 are to: • Determine an acceptable formulation for the LAW Cast Stone waste form. • Evaluate sources of dry materials for preparing the LAW Cast Stone. • Demonstrate the robustness of the Cast Stone waste form for a range of LAW compositions. • Demonstrate the robustness of the formulation for variability in the Cast Stone process. • Provide Cast Stone contaminant release data for PA and risk assessment evaluations. The first step in determining an acceptable formulation for the LAW Cast Stone waste form is to conduct screening tests to examine expected ranges in pretreated LAW composition, waste stream concentrations, dry-materials sources, and mix ratios of waste feed to dry blend. A statistically designed test matrix will be used to evaluate the effects of these key parameters on the properties of the Cast Stone as it is initially prepared and after curing. The second phase of testing will focus on selection of a baseline Cast Stone formulation for LAW and demonstrating that Cast Stone can meet expected waste form requirements for disposal in the IDF. It is expected that this testing will use the results of the screening tests to define a smaller suite of tests to refine the composition of the baseline Cast Stone formulation (e.g. waste concentration, water to dry mix ratio, waste loading).

  1. Test Automation with TTCN-3 -State of the Art and a Future Perspective

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Test Automation with TTCN-3 - State of the Art and a Future Perspective Ina Schieferdecker TU.schieferdecker@fokus.fraunhofer.de Abstract. Test automation encompasses all activities to automate various steps in the overall testing process including automation of test management, test generation, or test execution. The standardized

  2. Phase 1 Methyl Iodide Deep-Bed Adsorption Tests

    SciTech Connect (OSTI)

    Nick Soelberg; Tony Watson

    2014-08-01T23:59:59.000Z

    Nuclear fission results in the production of fission products (FPs) and activation products including iodine-129, which could evolve into used fuel reprocessing facility off-gas systems, and could require off-gas control to limit air emissions to levels within acceptable emission limits. Research, demonstrations, and some reprocessing plant experience have indicated that diatomic iodine can be captured with efficiencies high enough to meet regulatory requirements. Research on the capture of organic iodides has also been performed, but to a lesser extent [Jubin 2012b]. Several questions remain open regarding the capture of iodine bound in organic compounds. Deep-bed methyl iodide adsorption testing has progressed according to a multi-laboratory methyl iodide adsorption test plan. This report summarizes the first phase of methyl iodide adsorption work performed according to this test plan using the deep-bed iodine adsorption test system at the Idaho National Laboratory (INL), performed during Fiscal Year (FY) 2013 and early FY-2014. Testing has been performed to address questions posed in the test plan, and followed the testing outline in the test plan. Tests established detection limits, developed procedures for sample analysis with minimal analytical interferences, and confirmed earlier results that show that the methyl iodide reacts when in contact with the AgZ sorbent, and not significantly in the gas flow upstream of the sorbent. The reaction(s) enable separation of the iodine from the organic moiety, so that the iodine can chemisorb onto the sorbent. The organic moiety can form other compounds, some of which are organic compounds that are detected and can be tentatively identified using GC-FID and GCMS. Test results also show that other gas constituents (NOx and/or H2O) can affect the methyl iodide reactions. With NOx and H2O present in the gas stream, the majority of uncaptured iodine exiting iodine-laden sorbent beds is in the form of I2 or HI, species that are soluble in NaOH scrubbing solution for iodine analysis. But when NOx and H2O are not present, then the majority of the uncaptured iodine exiting iodine-laden sorbent is in the form of methyl iodide. Methyl iodide adsorption efficiencies have been high enough so that initial DFs exceed 1,000 to 10,000. The methyl iodide mass transfer zone depths are estimated at 4-8 inches, possibly deeper than mass transfer zone depths estimated for I2 adsorption on AgZ. Additional deep-bed testing and analyses are recommended to (a) expand the data base for methyl iodide adsorption under various conditions specified in the methyl iodide test plan, and (b) provide more data for evaluating organic iodide reactions and reaction byproducts for different potential adsorption conditions.

  3. Logical Structure Extraction from Software Requirements Documents

    E-Print Network [OSTI]

    Czarnecki, Krzysztof

    Documents I. INTRODUCTION Requirements management (RM) tools store and manipu- late software requirementsLogical Structure Extraction from Software Requirements Documents Rehan Rauf, Michal Antkiewicz,mantkiew,kczarnec}@gsd.uwaterloo.ca Abstract--Software requirements documents (SRDs) are often authored in general-purpose rich-text editors

  4. Grantee Checklist for the Inspection & Monitoring Requirement

    Broader source: Energy.gov [DOE]

    This document walks Grantees through the Inspection and Monitoring requirement of the Quality Work Plan.

  5. Improving Unit Operations-Test Station Performance

    E-Print Network [OSTI]

    Filak, J. J. Jr.

    IMPROVING UNIT OPERATIONS - TEST STATION PERFORMANCE JosqIb 1. Filak. Jr, ? Corporate Energy Manager. Park.er?Hannafin COfpontioo- Cleveland. Oh ABSTRACT: This program's basic concept deals with the possibilities for reducing energy efficiency... requirements, control operation test performance functions more successfully, and retain peak load surges from reaching higher utility rate expense levels. 142 ESL-IE-95-04-23 Proceedings from the Seventeenth Industrial Energy Technology Conference...

  6. Modular test facility for HTS insert coils

    SciTech Connect (OSTI)

    Lombardo, V; Bartalesi, A.; Barzi, E.; Lamm, M.; Turrioni, D.; Zlobin, A.V.; /Fermilab

    2009-10-01T23:59:59.000Z

    The final beam cooling stages of a Muon Collider may require DC solenoid magnets with magnetic fields in the range of 40-50 T. In this paper we will present a modular test facility developed for the purpose of investigating very high field levels with available 2G HTS superconducting materials. Performance of available conductors is presented, together with magnetic calculations and evaluation of Lorentz forces distribution on the HTS coils. Finally a test of a double pancake coil is presented.

  7. Dynamometer Testing (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2010-11-01T23:59:59.000Z

    This fact sheet describes the dynamometer and its testing capabilities at the National Wind Technology Center.

  8. Integrated Recycling Test Fuel Fabrication

    SciTech Connect (OSTI)

    R.S. Fielding; K.H. Kim; B. Grover; J. Smith; J. King; K. Wendt; D. Chapman; L. Zirker

    2013-03-01T23:59:59.000Z

    The Integrated Recycling Test is a collaborative irradiation test that will electrochemically recycle used light water reactor fuel into metallic fuel feedstock. The feedstock will be fabricated into a metallic fast reactor type fuel that will be irradiation tested in a drop in capsule test in the Advanced Test Reactor on the Idaho National Laboratory site. This paper will summarize the fuel fabrication activities and design efforts. Casting development will include developing a casting process and system. The closure welding system will be based on the gas tungsten arc burst welding process. The settler/bonder system has been designed to be a simple system which provides heating and controllable impact energy to ensure wetting between the fuel and cladding. The final major pieces of equipment to be designed are the weld and sodium bond inspection system. Both x-radiography and ultrasonic inspection techniques have been examine experimentally and found to be feasible, however the final remote system has not been designed. Conceptual designs for radiography and an ultrasonic system have been made.

  9. Energy requirements for rural development

    SciTech Connect (OSTI)

    Jones, D.W.

    1988-06-01T23:59:59.000Z

    This study on the role of energy in the development of rural areas was originally conducted in the spring and summer of 1985. It was intended to serve as a background paper for the preparation of a program plan for the Office of Energy of the United States Agency for International Development. As such it begins with a brief overview of how rural development fits into national development, then offers a comprehensive framework for thinking about rural development in particular and the energy implications of the various components of rural development. Agriculture naturally comes to mind when rural areas are mentioned, but industry is an important component of rural activity as well. Consequently, both agricultural and nonagricultural energy use is discussed. Modernization of rural areas will change household, as well as production, energy use. However, household energy use is a veritable subject in its own right, with a large literature. Consequently, that topic is discussed in less detail than the production energy topics.

  10. Activation Energies from Transition Path Sampling Simulations

    E-Print Network [OSTI]

    Dellago, Christoph

    unavailable for processes occurring in complex systems. Since in this method activation energies diatomic immersed in a bath of repulsive soft particles. Keywords: Activation energy; Computer simulation on the transition path sampling methodology, our approach to determine activation energies does not require full

  11. AVTA: 2014 Mazda Mazda3 i-ELOOP Vehicle Testing Reports

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road....

  12. AVTA: 2014 Smart Electric Drive Coupe All-Electric Vehicle Testing Reports

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. ...

  13. AVTA: 2012 Mitsubishi i-MiEV All-Electric Vehicle Testing Reports

    Broader source: Energy.gov [DOE]

    The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. ...

  14. CERTS Microgrid Laboratory Test Bed

    SciTech Connect (OSTI)

    Eto, Joe; Lasseter, Robert; Schenkman, Ben; Stevens, John; Klapp, Dave; Volkommer, Harry; Linton, Ed; Hurtado, Hector; Roy, Jean

    2009-06-18T23:59:59.000Z

    The objective of the CERTS Microgrid Test Bed project was to enhance the ease of integrating energy sources into a microgrid. The project accomplished this objective by developing and demonstrating three advanced techniques, collectively referred to as the CERTS Microgrid concept, that significantly reduce the level of custom field engineering needed to operate microgrids consisting of generating sources less than 100kW. The techniques comprising the CERTS Microgrid concept are: 1) a method for effecting automatic and seamless transitions between grid-connected and islanded modes of operation, islanding the microgrid's load from a disturbance, thereby maintaining a higher level of service, without impacting the integrity of the utility's electrical power grid; 2) an approach to electrical protection within a limited source microgrid that does not depend on high fault currents; and 3) a method for microgrid control that achieves voltage and frequency stability under islanded conditions without requiring high-speed communications between sources. These techniques were demonstrated at a full-scale test bed built near Columbus, Ohio and operated by American Electric Power. The testing fully confirmed earlier research that had been conducted initially through analytical simulations, then through laboratory emulations,and finally through factory acceptance testing of individual microgrid components. The islanding and resychronization method met all Institute of Electrical and Electronics Engineers Standard 1547 and power quality requirements. The electrical protection system was able to distinguish between normal and faulted operation. The controls were found to be robust under all conditions, including difficult motor starts and high impedance faults. The results from these tests are expected to lead to additional testing of enhancements to the basic techniques at the test bed to improve the business case for microgrid technologies, as well to field demonstrations involving microgrids that involve one or more of the CERTS Microgrid concepts. Future planned microgrid work involves unattended continuous operation of the microgrid for 30 to 60 days to determine how utility faults impact the operation of the microgrid and to gage the power quality and reliability improvements offered by microgrids.

  15. Solderability test system

    DOE Patents [OSTI]

    Yost, F.; Hosking, F.M.; Jellison, J.L.; Short, B.; Giversen, T.; Reed, J.R.

    1998-10-27T23:59:59.000Z

    A new test method to quantify capillary flow solderability on a printed wiring board surface finish. The test is based on solder flow from a pad onto narrow strips or lines. A test procedure and video image analysis technique were developed for conducting the test and evaluating the data. Feasibility tests revealed that the wetted distance was sensitive to the ratio of pad radius to line width (l/r), solder volume, and flux predry time. 11 figs.

  16. Solderability test system

    DOE Patents [OSTI]

    Yost, Fred (Cedar Crest, NM); Hosking, Floyd M. (Albuquerque, NM); Jellison, James L. (Albuquerque, NM); Short, Bruce (Beverly, MA); Giversen, Terri (Beverly, MA); Reed, Jimmy R. (Austin, TX)

    1998-01-01T23:59:59.000Z

    A new test method to quantify capillary flow solderability on a printed wiring board surface finish. The test is based on solder flow from a pad onto narrow strips or lines. A test procedure and video image analysis technique were developed for conducting the test and evaluating the data. Feasibility tests revealed that the wetted distance was sensitive to the ratio of pad radius to line width (l/r), solder volume, and flux predry time.

  17. Coated Fiber Neutron Detector Test

    SciTech Connect (OSTI)

    Lintereur, Azaree T.; Ely, James H.; Kouzes, Richard T.; Stromswold, David C.

    2009-10-23T23:59:59.000Z

    Radiation portal monitors used for interdiction of illicit materials at borders include highly sensitive neutron detection systems. The main reason for having neutron detection capability is to detect fission neutrons from plutonium. The currently deployed radiation portal monitors (RPMs) from Ludlum and Science Applications International Corporation (SAIC) use neutron detectors based upon 3He-filled gas proportional counters, which are the most common large neutron detector. There is a declining supply of 3He in the world, and thus, methods to reduce the use of this gas in RPMs with minimal changes to the current system designs and sensitivity to cargo-borne neutrons are being investigated. Reported here are the results of tests of the 6Li/ZnS(Ag)-coated non-scintillating plastic fibers option. This testing measured the required performance for neutron detection efficiency and gamma ray rejection capabilities of a system manufactured by Innovative American Technology (IAT).

  18. Field project to obtain pressure core, wireline log, and production test data for evaluation of CO/sub 2/ flooding potential. Texas Pacific Bennett Ranch Unit well No. 310, Wasson (San Andres) Field, Yoakum County, Texas

    SciTech Connect (OSTI)

    Swift, T.E.; Goodrich, J.H.; Kumar, R.M.; McCoy, R.L.; Wilhelm, M.H.; Glascock, M.R.

    1982-01-01T23:59:59.000Z

    The coring, logging and testing of Bennett Ranch Unit well No. 310 was a cooperative effort between Texas Pacific, owner of the well, and Gruy Federal, Inc. The requirements of the contract, which are summarized in Enclosure 1, Appendix A, include drilling and coring activities. The pressure-coring and associated logging and testing programs in selected wells are intended to provide data on in-situ oil saturation, porosity and permeability distribution, and other data needed for resource characterization of fields and reservoirs in which CO/sub 2/ injection might have a high probability of success. This report presents detailed information on the first such project. This project demonstrates the usefulness of integrating pressure core, log and production data to realistically evaluate a reservoir for carbon dioxide flood. The engineering of tests and analysis of such experimental data requires original thinking, but the reliability of the results is higher than data derived from conventional tests.

  19. Check for peroxides every 6 months. opened test 1 test 2 test 3

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Check for peroxides every 6 months. opened test 1 test 2 test 3 date initials Check for peroxides every 6 months. opened test 1 test 2 test 3 date initials Check for peroxides every 6 months. Test strips can be obtained from EH&S, 5-8200 opened test 1 test 2 test 3 date initials Check for peroxides

  20. Automatic Test Factoring for Java

    E-Print Network [OSTI]

    Saff, David

    2005-06-08T23:59:59.000Z

    Test factoring creates fast, focused unit tests from slow system-widetests; each new unit test exercises only a subset of the functionalityexercised by the system test. Augmenting a test suite with factoredunit tests ...