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Sample records for doe test snf

  1. NSNFP Activities in Support of Repository Licensing for Disposal of DOE SNF

    SciTech Connect (OSTI)

    Henry H. Loo; Brett W.. Carlsen; Sheryl L. Morton; Larry L. Taylor; Gregg W. Wachs

    2004-09-01

    The U.S. Department of Energy (DOE) Office of Civilian Radioactive Waste Management is in the process of preparing the Yucca Mountain license application for submission to the Nuclear Regulatory Commission as the nation’s first geologic repository for spent nuclear fuel (SNF) and high-level waste. Because the DOE SNF will be part of the license application, there are various components of the license application that will require information relative to the DOE SNF. The National Spent Nuclear Fuel Program (NSNFP) is the organization that directs the research, development, and testing of treatment, shipment, and disposal technologies for all DOE SNF. This report documents the work activities conducted by the NSNFP and discusses the relationship between these NSNFP technical activities and the license application. A number of the NSNFP activities were performed to provide risk insights and understanding of DOE SNF disposal as well as to prepare for anticipated questions from the regulatory agency.

  2. LESSONS LEARNED FROM CIRFT TESTING ON SNF VIBRATION INTEGRITY STUDY

    SciTech Connect (OSTI)

    Wang, Jy-An John; Wang, Hong; Jiang, Hao; Bevard, Bruce Balkcom; Howard, Rob L; Scaglione, John M

    2015-01-01

    A cyclic integrated reversible-bending fatigue tester (CIRFT) was developed to support U.S. NRC and DOE Used Fuel Disposition Campaign studies on high burn-up (HBU) spent nuclear fuel (SNF) transportation during normal conditions of transport (NCT). Two devices were developed; the first CIRFT was successfully installed and operated in the ORNL hot-cells in September 2013. Since hot cell testing commenced several HBU SNF samples from both Zr-4 and M5 clads were investigated. The second CIRFT device was developed in February 2014, and has been used to test clad/fuel surrogate rods (stainless steel with alumina pellet inserts). The second CIRFT machine has also been used for sensor development and test sensitivity analyses, as well as loading boundary condition parameter studies. The lessons learned from CIRFT testing will be presented in this paper.

  3. Lessons learned from CIRFT testing on SNF vibration integrity study

    SciTech Connect (OSTI)

    Wang, Jy-An John; Wang, Hong; Jiang, Hao; Bevard, Bruce Balkcom; Howard, Rob L.; Scaglione, John M.

    2015-01-01

    A cyclic integrated reversible-bending fatigue tester (CIRFT) was developed to support U.S. NRC and DOE Used Fuel Disposition Campaign studies on high burn-up (HBU) spent nuclear fuel (SNF) transportation during normal conditions of transport (NCT). Two devices were developed; the first CIRFT was successfully installed and operated in the ORNL hot-cells in September 2013. Since hot cell testing commenced several HBU SNF samples from both Zr-4 and M5 clads were investigated. The second CIRFT device was developed in February 2014, and has been used to test clad/fuel surrogate rods (stainless steel with alumina pellet inserts). The second CIRFT machine has also been used for sensor development and test sensitivity analyses, as well as loading boundary condition parameter studies. The lessons learned from CIRFT testing will be presented in this paper.

  4. EXTERNAL CRITICALITY CALCULATION FOR DOE SNF CODISPOSAL WASTE PACKAGES

    SciTech Connect (OSTI)

    H. Radulescu

    2002-10-18

    The purpose of this document is to evaluate the potential for criticality for the fissile material that could accumulate in the near-field (invert) and in the far-field (host rock) beneath the U.S. Department of Energy (DOE) spent nuclear fuel (SNF) codisposal waste packages (WPs) as they degrade in the proposed monitored geologic repository at Yucca Mountain. The scope of this calculation is limited to the following DOE SNF types: Shippingport Pressurized Water Reactor (PWR), Enrico Fermi, Fast Flux Test Facility (FFTF), Fort St. Vrain, Melt and Dilute, Shippingport Light Water Breeder Reactor (LWBR), N-Reactor, and Training, Research, Isotope, General Atomics reactor (TRIGA). The results of this calculation are intended to be used for estimating the probability of criticality in the near-field and in the far-field. There are no limitations on use of the results of this calculation. The calculation is associated with the waste package design and was developed in accordance with the technical work plan, ''Technical Work Plan for: Department of Energy Spent Nuclear Fuel and Plutonium Disposition Work Packages'' (Bechtel SAIC Company, LLC [BSC], 2002a). This calculation is subject to the Quality Assurance Requirements and Description (QARD) per the activity evaluation under work package number P6212310Ml in the technical work plan TWP-MGR-MD-0000 10 REV 01 (BSC 2002a).

  5. White Paper: Multi-purpose canister (MPC) for DOE-owned spent nuclear fuel (SNF)

    SciTech Connect (OSTI)

    Knecht, D.A.

    1994-04-01

    The paper examines the issue, What are the advantages, disadvantages, and other considerations for using the MPC concept as part of the strategy for interim storage and disposal of DOE-owned SNF? The paper is based in part on the results of an evaluation made for the DOE National Spent Fuel Program by the Waste Form Barrier/Canister Team, which is composed of knowledgeable DOE and DOE-contractor personnel. The paper reviews the MPC and DOE SNF status, provides criteria and other considerations applicable to the issue, and presents an evaluation, conclusions, and recommendations. The primary conclusion is that while most of DOE SNF is not currently sufficiently characterized to be sealed into an MPC, the advantages of standardized packages in handling, reduced radiation exposure, and improved human factors should be considered in DOE SNF program planning. While the design of MPCs for DOE SNF are likely premature at this time, the use of canisters should be considered which are consistent with interim storage options and the MPC design envelope.

  6. National spent fuel program preliminary report RCRA characteristics of DOE-owned spent nuclear fuel DOE-SNF-REP-002. Revision 3

    SciTech Connect (OSTI)

    1995-07-01

    This report presents information on the preliminary process knowledge to be used in characterizing all Department of Energy (DOE)-owned Spent Nuclear Fuel (SNF) types that potentially exhibit a Resource Conservation and Recovery Act (RCRA) characteristic. This report also includes the process knowledge, analyses, and rationale used to preliminarily exclude certain SNF types from RCRA regulation under 40 CFR {section}261.4(a)(4), ``Identification and Listing of Hazardous Waste,`` as special nuclear and byproduct material. The evaluations and analyses detailed herein have been undertaken as a proactive approach. In the event that DOE-owned SNF is determined to be a RCRA solid waste, this report provides general direction for each site regarding further characterization efforts. The intent of this report is also to define the path forward to be taken for further evaluation of specific SNF types and a recommended position to be negotiated and established with regional and state regulators throughout the DOE Complex regarding the RCRA-related policy issues.

  7. Commercial SNF Accident Release Fractions

    SciTech Connect (OSTI)

    J. Schulz

    2004-11-05

    container that confines the fuel assemblies could provide an additional barrier for diminishing the total release fraction should the fuel rod cladding breach during an accident. This analysis, however, does not take credit for the additional barrier and establishes only the total release fractions for bare unconfined intact commercial SNF assemblies, which may be conservatively applied to confined intact commercial I SNF assemblies.

  8. Canister storage building compliance assessment SNF project NRC equivalency criteria - HNF-SD-SNF-DB-003

    SciTech Connect (OSTI)

    BLACK, D.M.

    1999-08-11

    This document presents the Project's position on compliance with the SNF Project NRC Equivalency Criteria--HNF-SD-SNF-DE-003, Spent Nuclear Fuel Project Path Forward Additional NRC Requirements. No non-compliances are shown The compliance statements have been reviewed and approved by DOE. Open items are scheduled to be closed prior to project completion.

  9. Long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF)

    Broader source: Energy.gov [DOE]

    GC-52 provides legal advice to DOE regarding the long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF). SNF is nuclear fuel that has been used as fuel in a reactor...

  10. DOE Testing Reveals Samsung Refrigerator Does Not Meet Energy...

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

    Reveals Samsung Refrigerator Does Not Meet Energy Star Requirements DOE Testing Reveals Samsung Refrigerator Does Not Meet Energy Star Requirements March 16, 2010 - 4:28pm Addthis...

  11. Drug Testing for DOE Positions | Department of Energy

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

    Drug Testing for DOE Positions Drug Testing for DOE Positions Drug Testing for DOE Positions Drug Testing Matrix Secretary Bodman's Memorandum Regarding Drug Testing at DOE Fact ...

  12. DOE's Round Robin Test Program FAQ Sheet

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

    Frequently Asked Questions for: DOE's Round Robin Test Program May 2011 i Table of Contents Introduction ........................................................................................................................................ 1 What products will be tested? .......................................................................................................... 1 What is the testing process?

  13. AHAM DOE Verification Test Agreement | Department of Energy

    Energy Savers [EERE]

    DOE Verification Test Agreement AHAM DOE Verification Test Agreement This letter is to inform AHAM that DOE is adopting a new policy regarding DOE ENERGY STAR verification testing ...

  14. DOE-STD-3022-98; DOE Standard DOE HEPA Filter Test Program

    Office of Environmental Management (EM)

    DOE STANDARD DOE HEPA FILTER TEST PROGRAM U.S. Department of Energy FSC 4460 Washington, ... predecessor, entitled "Operating Policy of DOE HEPA Filter Test Programs" (NE F 3-42). ...

  15. Potential dispositioning flowsheets for ICPP SNF and wastes

    SciTech Connect (OSTI)

    Olson, A.L.; Anderson, P.A.; Bendixsen, C.L.

    1995-11-01

    The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Laboratory (INEL), has reprocessed irradiated nuclear fuels for the US Department of Energy (DOE) since 1953. This activity resulted mainly in the recovery of uranium and the management of the resulting wastes. The acidic radioactive high-level liquid waste was routinely stored in stainless steel tanks and then calcined to form a dry granular solid. The calcine is stored in stainless steel bins that are housed in underground concrete vaults. In April 1992, the DOE discontinued the practice of reprocessing irradiated nuclear fuels. This decision has left a legacy of 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste), 3800 cubic meters of calcine waste, and 289 metric tons of heavy metal within unprocessed spent nuclear fuel (SNF) left in inventory at the ICPP. The nation`s radioactive waste policy has been established by the Nuclear Waste Policy Act (NWPA), which requires the final disposal of SNF and radioactive waste in accordance with US Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) standards. In accordance with these regulations and other legal agreements between the State of Idaho and the DOE, the DOE must, among other requirements, (1) complete a final Environmental Impact Statement by April 30, 1995, (2) evaluate and test sodium-bearing waste pre-treatment technologies, (3) select the sodium-bearing and calcine waste pre-treatment technology, if necessary, by June 1, 1995, and (4) select a technology for converting calcined waste into an appropriate disposal form by June 1, 1995.

  16. Evaluation of codisposal viability of MOX (FFTF) DOE-owned fuel: Phase 1 -- Intact mode calculations

    SciTech Connect (OSTI)

    Goluoglu, S.; Davis, J.W.; Montierth, L.M.

    1999-07-01

    The authors provide the intact criticality information that supports the disposal of spent nuclear fuel (SNF) from the US Department of Energy's (DOE's) Fast Flux Test Facility (FFTF) in the potential Monitored Geologic Repository at Yucca Mountain. FFTF is one of more than 250 forms of DOE-owned SNF. Because of the variety of the DOE SNF, the National Spent Nuclear Fuel Program has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. The FFTF fuel is representative of the mixed-oxide fuel (MOX) group.

  17. Damaged Spent Nuclear Fuel at U.S. DOE Facilities Experience and Lessons Learned

    SciTech Connect (OSTI)

    Brett W. Carlsen; Eric Woolstenhulme; Roger McCormack

    2005-11-01

    From a handling perspective, any spent nuclear fuel (SNF) that has lost its original technical and functional design capabilities with regard to handling and confinement can be considered as damaged. Some SNF was damaged as a result of experimental activities and destructive examinations; incidents during packaging, handling, and transportation; or degradation that has occurred during storage. Some SNF was mechanically destroyed to protect proprietary SNF designs. Examples of damage to the SNF include failed cladding, failed fuel meat, sectioned test specimens, partially reprocessed SNFs, over-heated elements, dismantled assemblies, and assemblies with lifting fixtures removed. In spite of the challenges involved with handling and storage of damaged SNF, the SNF has been safely handled and stored for many years at DOE storage facilities. This report summarizes a variety of challenges encountered at DOE facilities during interim storage and handling operations along with strategies and solutions that are planned or were implemented to ameliorate those challenges. A discussion of proposed paths forward for moving damaged and nondamaged SNF from interim storage to final disposition in the geologic repository is also presented.

  18. DOE/EIS-0203-SA-07 DOE/EA-1148-SA-01 DOE/EIS-0250F-S-1-SA-02

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

    ... SNF from fuel performance testing at Babcock and Wilcox Research Center; and special case SNF ... (cubic meters) 8 32year a 50 SNF R&D Library Storage (MTHM) 0.010 120 b (c) a. ...

  19. CONTAINMENT EVALUATION OF BREACHED AL-SNF FOR CASK TRANSPORT

    SciTech Connect (OSTI)

    Vinson, D. W.; Sindelar, R. L.; Iyer, N. C.

    2005-11-07

    Aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors (FRR/DRR) is being shipped to the Savannah River Site. To enter the U.S., the cask with loaded fuel must be certified to comply with the requirements in the Title 10 of the U.S. Code of Federal Regulations, Part 71. The requirements include demonstration of containment of the cask with its contents under normal and accident conditions. Al-SNF is subject to corrosion degradation in water storage, and many of the fuel assemblies are ''failed'' or have through-clad damage. A methodology has been developed with technical bases to show that Al-SNF with cladding breaches can be directly transported in standard casks and maintained within the allowable release rates. The approach to evaluate the limiting allowable leakage rate, L{sub R}, for a cask with breached Al-SNF for comparison to its test leakage rate could be extended to other nuclear material systems. The approach for containment analysis of Al-SNF follows calculations for commercial spent fuel as provided in NUREG/CR-6487 that adopts ANSI N14.5 as a methodology for containment analysis. The material-specific features and characteristics of damaged Al-SNF (fuel materials, fabrication techniques, microstructure, radionuclide inventory, and vapor corrosion rates) that were derived from literature sources and/or developed in laboratory testing are applied to generate the four containment source terms that yield four separate cask cavity activity densities; namely, those from fines; gaseous fission product species; volatile fission product species; and fuel assembly crud. The activity values, A{sub 2}, are developed per the guidance of 10CFR71. The analysis is performed parametrically to evaluate maximum number of breached assemblies and exposed fuel area for a proposed shipment in a cask with a test leakage rate.

  20. Air Transport of Spent Nuclear Fuel (SNF) Assemblies

    SciTech Connect (OSTI)

    Haire, M.J.; Moses, S.D.; Shapovalov, V.I.; Morenko, A.

    2007-07-01

    Sometimes the only feasible means of shipping research reactor spent nuclear fuel (SNF) among countries is via air transport because of location or political conditions. The International Atomic Energy Agency (IAEA) has established a regulatory framework to certify air transport Type C casks. However, no such cask has been designed, built, tested, and certified. In lieu of an air transport cask, research reactor SNF has been transported using a Type B cask under an exemption with special arrangements for administrative and security controls. This work indicates that it may be feasible to transport commercial power reactor SNF assemblies via air, and that the cost is only about three times that of shipping it by railway. Optimization (i.e., reduction) of this cost factor has yet to be done. (authors)

  1. DOE's New Large Blade Test Facility in Massachusetts Completes...

    Office of Environmental Management (EM)

    DOE's New Large Blade Test Facility in Massachusetts Completes First Commercial Blade Tests DOE's New Large Blade Test Facility in Massachusetts Completes First Commercial Blade ...

  2. SNF shipping cask shielding analysis

    SciTech Connect (OSTI)

    Johnson, J.O.; Pace, J.V. III

    1996-01-01

    The Waste Management and Remedial Action Division has planned a modification sequence for storage facility 7827 in the Solid Waste Storage Area (SWSA). The modification cycle is: (1) modify an empty caisson, (2) transfer the spent nuclear fuel (SNF) of an occupied caisson to a hot cell in building 3525 for inspection and possible repackaging, and (3) return the package to the modified caisson in the SWSA. Although the SNF to be moved is in the solid form, it has different levels of activity. Thus, the following 5 shipping casks will be available for the task: the Loop Transport Carrier, the In- Pile Loop LITR HB-2 Carrier, the 6.5-inch HRLEL Carrier, the HFIR Hot Scrap Carrier, and the 10-inch ORR Experiment Removal Shield Cask. This report describes the shielding tasks for the 5 casks: determination of shielding characteristics, any streaming avenues, estimation of thermal limits, and shielding calculational uncertainty for use in the transportation plan.

  3. DOE and Partners Test Enhanced Geothermal Systems Technologies...

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

    and Partners Test Enhanced Geothermal Systems Technologies DOE and Partners Test Enhanced Geothermal Systems Technologies February 20, 2008 - 4:33pm Addthis DOE has embarked on a ...

  4. DOE Publishes Final Rule for Television Test Procedure | Department...

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

    DOE Publishes Final Rule for Plumbing Products Test Procedures DOE Publishes Notice of Proposed Rulemaking Regarding the Compliance Date for the Dehumidifier Test Procedure...

  5. DOE-STD-3026-99; DOE Standard Filter Test Facility Quality Program...

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

    Superseding DOE NE F 3-44 July 1986 DOE STANDARD FILTER TEST FACILITY QUALITY PROGRAM PLAN ... for HEPA filter testing performed at a DOE-accepted HEPA Filter Test Facility (FTF). ...

  6. DOE - NNSA/NFO -- Test Films

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

    Historical Test Films > Film Page NNSA/NFO Language Options U.S. DOE/NNSA - Nevada Field Office Historical Test Film Instructions: Click the Windows Media or MPG Movie link below the thumbnail to view the video Film details are listed on the right under Description Click the Full Text link for additional information about the video Refer to the Viewing Instructions and FAQs

  7. CRITICALITY CALCULATION FOR THE MOST REACTIVE DEGRADED CONFIGURATIONS OF THE FFTF SNF CODISPOSAL WP CONTAINING AN INTACT IDENT-69 CONTAINER

    SciTech Connect (OSTI)

    D.R. Moscalu

    2002-08-28

    The objective of this calculation is to perform additional degraded mode criticality evaluations of the Department of Energy's (DOE) Fast Flux Test Facility (FFTF) Spent Nuclear Fuel (SNF) codisposed in a 5-Defense High-Level Waste (5-DHLW) Waste Package (WP). The scope of this calculation is limited to the most reactive degraded configurations of the codisposal WP with an almost intact Ident-69 container (breached and flooded but otherwise non-degraded) containing intact FFTF SNF pins. The configurations have been identified in a previous analysis (CRWMS M&O 1999a) and the present evaluations include additional relevant information that was left out of the original calculations. The additional information describes the exact distribution of fissile material in each container (DOE 2002a). The effects of the changes that have been included in the baseline design of the codisposal WP (CRWMS M&O 2000) are also investigated. The calculation determines the effective neutron multiplication factor (k{sub eff}) for selected degraded mode internal configurations of the codisposal waste package. These calculations will support the demonstration of the technical viability of the design solution adopted for disposing of MOX (FFTF) spent nuclear fuel in the potential repository. This calculation is subject to the Quality Assurance Requirements and Description (QARD) (DOE 2002b) per the activity evaluation under work package number P6212310M2 in the technical work plan TWP-MGR-MD-000010 REV 01 (BSC 2002).

  8. DOE Withdraws Proposed Rulemaking (Test Procedure) and Proposed...

    Energy Savers [EERE]

    Withdraws Proposed Rulemaking (Test Procedure) and Proposed Coverage Determination (Energy Conservation Standard) for Set-Top Boxes DOE Withdraws Proposed Rulemaking (Test ...

  9. DOE Pens New Agreement with Southern Company to Test Advanced...

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

    Southern Company (Atlanta, Ga.) will test both pre- and post-combustion ... with DOE. The NCCC is equipped to test multiple slipstreams from diverse fuel ...

  10. DOE Publishes Final Rule for Residential Furnace Fan Test Procedure...

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

    Department of Energy (DOE) has published a final rule regarding test procedures for ... EERE-2010-BT-TP-0010. Find product information about current standards and test ...

  11. DOE-Sponsored Field Test Demonstrates Viability of Simultaneous...

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

    Field Test Demonstrates Viability of Simultaneous CO2 Storage and Enhanced Oil Recovery in Carbonate Reservoirs DOE-Sponsored Field Test Demonstrates Viability of Simultaneous CO2 ...

  12. 105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 1 Fuel

    SciTech Connect (OSTI)

    PACKER, M.J.

    1999-11-04

    Metallic uranium Spent Nuclear Fuel (SNF) is currently stored within two water filled pools, 105-KE Basin (KE Basin) and 105-KW Basin (KW Basin), at the United States Department of Energy (U.S. DOE) Hanford Site, in southeastern Washington State. The Spent Nuclear Fuel Project (SNF Project) is responsible to DOE for operation of these fuel storage pools and for the 2100 metric tons of SNF materials that they contain. The SNF Project mission includes safe removal and transportation of all SNF from these storage basins to a new storage facility in the 200 East Area. To accomplish this mission, the SNF Project modifies the existing KE Basin and KW Basin facilities and constructs two new facilities: the 100 K Area Cold Vacuum Drying Facility (CVDF), which drains and dries the SNF; and the 200 East Area Canister Storage Building (CSB), which stores the SNF. The purpose of this document is to describe the design basis feed compositions for materials stored or processed by SNF Project facilities and activities. This document is not intended to replace the Hanford Spent Fuel Inventory Baseline (WHC 1994b), but only to supplement it by providing more detail on the chemical and radiological inventories in the fuel (this volume) and sludge. A variety of feed definitions is required to support evaluation of specific facility and process considerations during the development of these new facilities. Six separate feed types have been identified for development of new storage or processing facilities. The approach for using each feed during design evaluations is to calculate the proposed facility flowsheet assuming each feed. The process flowsheet would then provide a basis for material compositions and quantities which are used in follow-on calculations.

  13. DOE - NNSA/NFO -- Historical Test Films

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

    ... 1950-57 http:www.nv.doe.govlibraryfilmsFilmsLibrary051.jpg 800052 Atomic Guided Missiles 1955 http:www.nv.doe.govlibraryfilmsFilmsLibrary052.jpg 800053 Meeting the ...

  14. SNF AGING SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    L.L. Swanson

    2005-04-06

    The purpose of this system description document (SDD) is to establish requirements that drive the design of the spent nuclear fuel (SNF) aging system and associated bases, which will allow the design effort to proceed. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD follows the design with regard to the description of the system. The description provided in the SDD reflects the current results of the design process. Throughout this SDD, the term aging cask applies to vertical site-specific casks and to horizontal aging modules. The term overpack is a vertical site-specific cask that contains a dual-purpose canister (DPC) or a disposable canister. Functional and operational requirements applicable to this system were obtained from ''Project Functional and Operational Requirements'' (F&OR) (Curry 2004 [DIRS 170557]). Other requirements that support the design process were taken from documents such as ''Project Design Criteria Document'' (PDC) (BSC 2004 [DES 171599]), ''Site Fire Hazards Analyses'' (BSC 2005 [DIRS 172174]), and ''Nuclear Safety Design Bases for License Application'' (BSC 2005 [DIRS 171512]). The documents address requirements in the ''Project Requirements Document'' (PRD) (Canori and Leitner 2003 [DIRS 166275]). This SDD includes several appendices. Appendix A is a Glossary; Appendix B is a list of key system charts, diagrams, drawings, lists and additional supporting information; and Appendix C is a list of

  15. DOE - NNSA/NFO -- Atomic Testing Museum

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

    National Atomic Testing Museum NNSANFO Language Options U.S. DOENNSA - Nevada Field Office NATIONAL ATOMIC TESTING MUSEUM Photograph of Atomic Testing Museum The Nevada Test Site ...

  16. Standardized DOE Spent Nuclear Fuel Canister and Transportation System for Shipping to the National Repository

    SciTech Connect (OSTI)

    Pincock, David Lynn; Morton, Dana Keith; Lengyel, Arpad Leslie

    2001-02-01

    The U.S.Department of Energys (DOE) National Spent Nuclear Fuel Program (NSNFP), located at the Idaho National Engineering and Environmental Laboratory (INEEL), has been chartered with the responsibility for developing spent nuclear fuel (SNF) standardized canisters and a transportation cask system for shipping DOE SNF to the national repository. The mandate for this development is outlined in the Memorandum of Agreement for Acceptance of Department of Energy Spent Nuclear Fuel and High-Level Radioactive Waste that states, EM shall design and fabricate DOE SNF canisters for shipment to RW. (1) It also states, EM shall be responsible for the design, NRC certification, and fabrication of the transportation cask system for DOE SNF canisters or bare DOE SNF in accordance with 10 CFR Part 71. (2) In fulfillment of these requirements, the NSNFP has developed four SNF standardized canister configurations and has conceptually designed a versatile transportation cask system for shipping the canisters to the national repository.1 The standardized canister sizes were derived from the national repository waste package design for co-disposal of SNF with high-level waste (HLW). One SNF canister can be placed in the center of the waste package or one can be placed in one of five radial positions, replacing a HLW canister. The internal cavity of the transportation cask was derived using the same logic, matching the size of the internal cavity of the waste package. The size of the internal cavity for the transportation cask allows the shipment of multiple canister configurations with the application of a removable basket design. The standardized canisters have been designed to be loaded with DOE SNF, placed into interim storage, shipped to the national repository, and placed in a waste package without having to be reopened. Significant testing has been completed that clearly demonstrates that the standardized canisters can safely achieve their intended design goals. The

  17. DOE - Office of Legacy Management -- Geothermal Test Facility - 001

    Office of Legacy Management (LM)

    Geothermal Test Facility - 001 FUSRAP Considered Sites Site: Geothermal Test Facility (001) Remediated; records are managed by DOE LM. More information at http://www.lm.doe.gov/geothermal/Sites.aspx Designated Name: Not Designated under FUSRAP Alternate Name: Geothermal Test Facility, CA, Site Location: Imperial County, California Evaluation Year: Not considered for FUSRAP - in another program Site Operations: Geothermal testing projects Site Disposition: Remediated by DOE Office of

  18. DOE's New Large Blade Test Facility in Massachusetts Completes First

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

    Commercial Blade Tests | Department of Energy DOE's New Large Blade Test Facility in Massachusetts Completes First Commercial Blade Tests DOE's New Large Blade Test Facility in Massachusetts Completes First Commercial Blade Tests December 19, 2011 - 3:15pm Addthis This is an excerpt from the Fourth Quarter 2011 edition of the Wind Program R&D Newsletter. Since opening its doors for business in May, the Wind Technology Testing Center (WTTC), in Boston, Massachusetts, has come up to full

  19. End of Year 2010 SNF & HLW Inventories | Department of Energy

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

    End of Year 2010 SNF & HLW Inventories End of Year 2010 SNF & HLW Inventories Map of the United States of America that shows the location of approximately 64,000 MTHM of Spent ...

  20. ISOTOPIC MODEL FOR COMMERCIAL SNF BURNUP CREDIT

    SciTech Connect (OSTI)

    A.H. Wells

    2004-11-17

    The purpose of this report is to demonstrate a process for selecting bounding depletion parameters, show that they are conservative for pressurized water reactor (PWR) and boiling water reactor (BWR) spent nuclear fuel (SNF), and establish the range of burnup for which the parameters are conservative. The general range of applicability is for commercial light water reactor (LWR) SNF with initial enrichments between 2.0 and 5.0 weight percent {sup 235}U and burnups between 10 and 50 gigawatt-day per metric ton of uranium (GWd/MTU).

  1. Flow Test At Colrado Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Colrado Area (DOE GTP) Exploration Activity Details Location Colado Geothermal Area...

  2. Flow Test At Wister Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Wister Area (DOE GTP) Exploration Activity Details Location Wister Area Exploration...

  3. Flow Test At Alum Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Alum Area (DOE GTP) Exploration Activity Details Location Alum Geothermal Area...

  4. Flow Test At Maui Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Maui Area (DOE GTP) Exploration Activity Details Location Maui Area Exploration...

  5. DOE Issues Final Appliance Test Procedure Rule | Department of Energy

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

    Appliance Test Procedure Rule DOE Issues Final Appliance Test Procedure Rule December 8, 2006 - 9:46am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced a final rule establishing new test procedures and related definitions to determine the energy efficiency of certain residential appliances and commercial equipment. The rulemaking clarifies and codifies the test procedures mandated by the Energy Policy Act (EPAct) of 2005. "These new test procedures are the

  6. Spent Nuclear Fuel (SNF) Project Execution Plan

    SciTech Connect (OSTI)

    LEROY, P.G.

    2000-11-03

    The Spent Nuclear Fuel (SNF) Project supports the Hanford Site Mission to cleanup the Site by providing safe, economic, environmentally sound management of Site spent nuclear fuel in a manner that reduces hazards by staging it to interim onsite storage and deactivates the 100 K Area facilities.

  7. DOE - NETL Gasification Technology Test Sites

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

    technology test sites Once a technology is ready to be tested at pilot or commercial scale, the cost of building a test facility becomes significant -- often beyond the funding...

  8. DOE Publishes Report on Accelerated Life Testing of SSL Luminaires...

    Energy Savers [EERE]

    The U.S. Department of Energy (DOE) has published the findings of a new study utilizing a highly accelerated life-test method (called the "hammer test") intended to produce ...

  9. DOE and Partners Test Enhanced Geothermal Systems Technologies | Department

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

    of Energy and Partners Test Enhanced Geothermal Systems Technologies DOE and Partners Test Enhanced Geothermal Systems Technologies February 20, 2008 - 4:33pm Addthis DOE has embarked on a project with a number of partners to test Enhanced Geothermal Systems (EGS) technologies at a commercial geothermal power facility near Reno, Nevada. EGS technology enhances the permeability of underground strata, typically by injecting water into the strata at high pressure. The concept was initially

  10. DOE Publishes Final Rule for Residential Furnace Fan Test Procedure |

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

    Department of Energy Publishes Final Rule for Residential Furnace Fan Test Procedure DOE Publishes Final Rule for Residential Furnace Fan Test Procedure January 3, 2014 - 12:00am Addthis The Department of Energy (DOE) has published a final rule regarding test procedures for residential furnace fans. 79 FR 500 (January 3, 2014). Find more information on the rulemaking, including milestones, statutory authority, rulemaking documents, and any other related rulemakings. All notices, public

  11. DOE Approves Field Test for Promising Carbon Capture Technology |

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

    Department of Energy Approves Field Test for Promising Carbon Capture Technology DOE Approves Field Test for Promising Carbon Capture Technology November 20, 2012 - 12:00pm Addthis Washington, DC - A promising post combustion membrane technology that can separate and capture 90 percent of the carbon dioxide (CO2) from a pulverized coal plant has been successfully demonstrated and received Department of Energy (DOE) approval to advance to a larger-scale field test. In an $18.75 million

  12. DOE - NNSA/NFO -- Photo Library Atmospheric Testing

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

    Atmospheric NNSA/NFO Language Options U.S. DOE/NNSA - Nevada Field Office Photo Library - Atmospheric Testing A total of 100 atmospheric tests were conducted at the Nevada Test Site. These tests were conducted to provide information on weapons effects, effects of the height of burst on overpressure, and information on nuclear phenomena to improve the design of nuclear weapons. Atmospheric testing ceased for good in 1963, after which nuclear testing moved underground. Instructions: Click the

  13. DOE Launches Public Test Procedure Guidance Website

    Broader source: Energy.gov [DOE]

    The Department of Energy this week launched a new online database offering guidance on the Department’s test procedures for appliances and commercial equipment.  The new database will provide a...

  14. DOE's Round Robin Test Program FAQ Sheet | Department of Energy

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

    DOE's Round Robin Test Program FAQ Sheet DOE's Round Robin Test Program FAQ Sheet This document is the May 2011 version of the Frequently Asked Questions about the US Department of Energy's Round Robin Test Program. roundrobintestprogram_faq_may2011.pdf (177.44 KB) More Documents & Publications 6450-01-P, DOE 10 CFR Parts 430 and 431, Docket No. EERE-2010-BT-CE-0014 RIN 1904-AC23, Draft Submission to Federal Register, Notice of Revisions to Energy Efficiency Enforcement Regulations, Request

  15. DOE Publishes Report on Accelerated Life Testing of SSL Luminaires

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) has published the findings of a new study utilizing a highly accelerated life-test method (called the "hammer test") intended to produce failures in SSL luminaires in a reasonable test period, with the goal

  16. DOE - NNSA/NFO -- Photo Library - Test Preparation

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

    Test Preparation NNSA/NFO Language Options U.S. DOE/NNSA - Nevada Field Office Photo Library - Test Preparation Photos in this category depict preparations for past nuclear tests. The last test at the Nevada National Security Site was conducted in 1992, the year President Bush instituted a moratorium. Since that time, the United States has ceased all nuclear testing. Instructions: Click the photograph THUMBNAIL to view the photograph details Click the Category, Number, or Date table header links

  17. DOE - NNSA/NFO -- Photo Library Underground Testing

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

    Underground Testing NNSA/NFO Language Options U.S. DOE/NNSA - Nevada Field Office Photo Library - Underground Testing Between 1951 and 1992, 828 underground nuclear tests were conducted in specially drilled shafts, horizontal tunnels and craters at the Nevada National Security Site. Most vertical shaft tests assisted in the development of new weapon systems. Horizontal tunnel tests occurred to evaluate the effects (radiation, ground shock) of various weapons on military hardware and systems.

  18. DOE - Office of Legacy Management -- Nevada Test Site - 023

    Office of Legacy Management (LM)

    Nevada Test Site - 023 FUSRAP Considered Sites Site: Nevada Test Site (023) More information at http://energy.gov/em and http://www.nv.energy.gov Designated Name: Not Designated under FUSRAP Alternate Name: Nevada National Security Site; Nevada Test Site and Tonopah Test Range; NNSS Location: Nye County, Nevada Evaluation Year: Not considered for FUSRAP - in another program Site Operations: Nuclear weapons testing Site Disposition: Remediation in progress by DOE Office of Environmental

  19. DOE Energy Star Testing Reveals Inefficient ASKO Dishwasher

    Broader source: Energy.gov [DOE]

    DOE testing in support of the Energy Star program has revealed that an ASKO dishwasher (model D5122XXLB), which the company had claimed was Energy Star compliant, consumes more energy than...

  20. DOE Seeks Comment on Application of Clothes Washer Test Procedure

    Broader source: Energy.gov [DOE]

    Today, the U.S. Department of Energy (DOE) issued a draft interpretative rule clarifying its views on the application of the current residential clothes washer test procedure to machines that offer...

  1. DOE Pens New Agreement with Southern Company to Test Advanced

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

    Carbon-Capture & Gasification Technologies | Department of Energy Pens New Agreement with Southern Company to Test Advanced Carbon-Capture & Gasification Technologies DOE Pens New Agreement with Southern Company to Test Advanced Carbon-Capture & Gasification Technologies June 12, 2014 - 12:30pm Addthis Washington, D.C. - The U.S. Department of Energy (DOE) has signed a new 5-year cooperative agreement with Southern Company to evaluate advanced carbon-capture and gasification

  2. DOE Withdraws Proposed Rulemaking (Test Procedure) and Proposed Coverage

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

    Determination (Energy Conservation Standard) for Set-Top Boxes | Department of Energy Withdraws Proposed Rulemaking (Test Procedure) and Proposed Coverage Determination (Energy Conservation Standard) for Set-Top Boxes DOE Withdraws Proposed Rulemaking (Test Procedure) and Proposed Coverage Determination (Energy Conservation Standard) for Set-Top Boxes December 23, 2013 - 12:00am Addthis The Department of Energy (DOE) has issued pre-publication Federal Register notices withdrawing the notice

  3. DOE Testing Reveals Samsung Refrigerator Does Not Meet Energy Star Requirements

    Broader source: Energy.gov [DOE]

    DOE-initiated testing has revealed that a Samsung refrigerator (model RF26VAB), which the company had claimed was Energy Star compliant, consumed more energy than permitted by the Energy Star...

  4. DOE Hybrid and Electric Vehicle Test Platform

    SciTech Connect (OSTI)

    Gao, Yimin

    2012-03-31

    Based on the contract NT-42790 to the Department of Energy, “Plug-in Hybrid Ethanol Research Platform”, Advanced Vehicle Research Center (AVRC) Virginia has successfully developed the phase I electric drive train research platform which has been named as Laboratory Rapid Application Testbed (LabRAT). In phase II, LabRAT is to be upgraded into plug-in hybrid research platform, which will be capable of testing power systems for electric vehicles, and plug-in hybrid electric vehicles running on conventional as well as alternative fuels. LabRAT is configured as a rolling testbed with plentiful space for installing various component configurations. Component connections are modularized for flexibility and are easily replaced for testing various mechanisms. LabRAT is designed and built as a full functional vehicle chassis with a steering system, brake system and four wheel suspension. The rear drive axle offers maximum flexibility with a quickly changeable gear ratio final drive to accommodate different motor speed requirements. The electric drive system includes an electric motor which is mechanically connected to the rear axle through an integrated speed/torque sensor. Initially, a 100 kW UQM motor and corresponding UQM motor controller is used which can be easily replaced with another motor/controller combination. A lithium iron phosphate (LiFePO4) battery pack is installed, which consists of 108 cells of 100 AH capacity, giving the total energy capacity of 32.5 kWh. Correspondingly, a fully functional battery management system (BMS) is installed to perform battery cell operation monitoring, cell voltage balancing, and reporting battery real time operating parameters to vehicle controller. An advanced vehicle controller ECU is installed for controlling the drive train. The vehicle controller ECU receives traction or braking torque command from driver through accelerator and brake pedal position sensors and battery operating signals from the BMS through CAN BUS

  5. DOE standard: Filter test facility quality program plan

    SciTech Connect (OSTI)

    1999-02-01

    This standard was developed primarily for application in US Department of Energy programs. It contains specific direction for HEPA filter testing performed at a DOE-accepted HEPA Filter Test Facility (FTF). Beneficial comments (recommendations, additions, deletions) and any pertinent data that may improve this document should be sent to the Office of Nuclear Safety Policy and Standards (EH-31), US Department of Energy, Washington, DC 20585, by letter or by using the self-addressed Document Improvement Proposal form (DOE F 1300.3) appearing at the end of this document.

  6. DESIGN ANALYSIS FOR THE NAVAL SNF WASTE PACKAGE

    SciTech Connect (OSTI)

    T.L. Mitchell

    2000-05-31

    The purpose of this analysis is to demonstrate the design of the naval spent nuclear fuel (SNF) waste package (WP) using the Waste Package Department's (WPD) design methodologies and processes described in the ''Waste Package Design Methodology Report'' (CRWMS M&O [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000b). The calculations that support the design of the naval SNF WP will be discussed; however, only a sub-set of such analyses will be presented and shall be limited to those identified in the ''Waste Package Design Sensitivity Report'' (CRWMS M&O 2000c). The objective of this analysis is to describe the naval SNF WP design method and to show that the design of the naval SNF WP complies with the ''Naval Spent Nuclear Fuel Disposal Container System Description Document'' (CRWMS M&O 1999a) and Interface Control Document (ICD) criteria for Site Recommendation. Additional criteria for the design of the naval SNF WP have been outlined in Section 6.2 of the ''Waste Package Design Sensitivity Report'' (CRWMS M&O 2000c). The scope of this analysis is restricted to the design of the naval long WP containing one naval long SNF canister. This WP is representative of the WPs that will contain both naval short SNF and naval long SNF canisters. The following items are included in the scope of this analysis: (1) Providing a general description of the applicable design criteria; (2) Describing the design methodology to be used; (3) Presenting the design of the naval SNF waste package; and (4) Showing compliance with all applicable design criteria. The intended use of this analysis is to support Site Recommendation reports and assist in the development of WPD drawings. Activities described in this analysis were conducted in accordance with the technical product development plan (TPDP) ''Design Analysis for the Naval SNF Waste Package (CRWMS M&O 2000a).

  7. A review of DOE HEPA filter component test activities

    SciTech Connect (OSTI)

    Slawski, J.W.; Bresson, J.F.; Scripsick, R.C.

    1997-08-01

    All HEPA filters purchased for installation in DOE nuclear facilities are required to be tested at a Filter Test Facility (FTF) prior to installation. The number of HEPA filters purchased by DOE has been reduced so much that the Hanford FTF was closed. From Fiscal Year (FY) 1992 to 1994, funding was not provided to the FTF Technical Support Group (TSG) at the Los Alamos National Laboratory. As a consequence, Round Robin Tests (RRTs), performed twice each year by the FTFs to assess constituency of test results among the FTFs, were not performed in FY 1992 and FY 1993. The Annual Reports of FTF test activities were not prepared for FY 1992 - 1995. Technical support provided to the FTFs was minimal. There is talk of closing a second FTF, and ongoing discussions as to whether DOE will continue to fund operation of the FTFs. In FY 1994, DOE Defense Programs commenced funding the TSG. RRT data for FY 1994 and 1995 have been entered into the database; the FY 1994 RRT report has been issued; and the FY 1995 RRT report is in progress. Data from semiannual reports have been retrieved and entered into the database. Standards related to HEPA filter test and procurement activities are now scheduled for issuance by FY 1996. Continuation of these activities depends on whether DOE will continue to support the HEPA filter test program. The history and activities of the FTFs and the TSG at Los Alamos have been reported at previous Air Cleaning Conferences. Data from the FY 1991 Annual Report of FTF activities was presented at the 1992 Air Cleaning Conference. Preparation of the Annual Reports was temporarily suspended in 1992. However, all of the FTF Semiannual report data have been retrieved and entered into the data base. This paper focuses primarily on the results of HEPA filter tests conducted by FTFs during FY 1992 - FY 1995, and the possible effects of the DOE program uncertainties on the quality of HEPA filters for installation at the DOE sites. 15 refs., 13 tabs.

  8. DOE - NNSA/NFO -- Test Film Order Form

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

    Home > Library > Forms > Historical Test Film Order Form U.S. DOE/NNSA - Nevada Field Office Historical Test Film Order Form The Historical Nuclear Weapons Test films which have been declassified can be ordered from the Nuclear Testing Archive for a fee per video, plus shipping and handling. The form is used only to request a film(s). A representative will contact you regarding your order and payment options. Please call 702-794-5117 or 702-794-5106. You can contact us by email to

  9. DOE/NV/11718--1080 Nevada Test Site

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

    1080 Nevada Test Site Environmental Report 2004 National Nuclear Security Administration Strengthening national security through engineering and operational excellence Bechtel Nevada Disclaimer Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors.

  10. Interrelation of technologies for RW preparation and sites for final isolation of the wastes from pyrochemical processing of SNF

    SciTech Connect (OSTI)

    Gupalo, V.S.; Chistyakov, V.N.; Kormilitsyn, M.V.; Kormilitsyna, L.A.

    2013-07-01

    For the justification of engineering solutions and practical testing of the radiochemical component of the perspective nuclear power complex with on-site variant of nuclear fuel cycle (NFC), it is planned to establish a multi-functional research-development complex (MFCRC) for radiochemical processing of spent nuclear fuels (SNF) from fast reactors. MFCRC is being established at the NIIAR site, it comprises technological process lines, where innovation pyro-electrochemical and hydrometallurgical technologies are realized, with an option for closing the inter-chain material flows for testing the combined radiochemically converted materials. The technological flowchart for processing at the MFCRC is subdivided into 3 segments: -) complex of the lead operations for dismantling the fuel elements (FE) and fuel assemblies (FA), -) pyrochemical extraction flowchart for processing SNF, and -) hydrometallurgical flowchart for processing SNF. The engineered solutions for the management and disposition of the radioactive wastes from MFCRC are reviewed.

  11. DOE Field Operations Program EV and HEV Testing

    SciTech Connect (OSTI)

    Francfort, James Edward; Slezak, L. A.

    2001-10-01

    The United States Department of Energy’s (DOE) Field Operations Program tests advanced technology vehicles (ATVs) and disseminates the testing results to provide fleet managers and other potential ATV users with accurate and unbiased information on vehicle performance. The ATVs (including electric, hybrid, and other alternative fuel vehicles) are tested using one or more methods - Baseline Performance Testing (EVAmerica and Pomona Loop), Accelerated Reliability Testing, and Fleet Testing. The Program (http://ev.inel.gov/sop) and its nine industry testing partners have tested over 30 full-size electric vehicle (EV) models and they have accumulated over 4 million miles of EV testing experience since 1994. In conjunction with several original equipment manufacturers, the Program has developed testing procedures for the new classes of hybrid, urban, and neighborhood EVs. The testing of these vehicles started during 2001. The EVS 18 presentation will include (1) EV and hybrid electric vehicle (HEV) test results, (2) operating experience with and performance trends of various EV and HEV models, and (3) experience with operating hydrogen-fueled vehicles. Data presented for EVs will include vehicle efficiency (km/kWh), average distance driven per charge, and range testing results. The HEV data will include operating considerations, fuel use rates, and range testing results.

  12. DOE/NV/11718--514 Nevada Test Site

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

    514 Nevada Test Site / 2000 Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site February 2001 Post Office Box 98521 Las Vegas, NV 89193-8521 Prepared by: Bechtel Nevada 95 U.S. Department of Energy Nevada Operations Office Prepared for: DISCLAIMER Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the

  13. CRAD, NNSA- Startup and Restart of Nuclear Facilities (SNF)

    Broader source: Energy.gov [DOE]

    CRAD for Startup and Restart of Nuclear Facilities (SNF). Criteria Review and Approach Documents (CRADs) that can be used to conduct a well-organized and thorough assessment of elements of safety and health programs.

  14. Probabilistic Performance Assessment: SCC of SNF Interim Storage...

    Office of Scientific and Technical Information (OSTI)

    Probabilistic Performance Assessment: SCC of SNF Interim Storage Canisters C. Bryan1, C. ... Effect of Initial Heat Load Two alternative cases run, with 4 kW and 10 kW heat ...

  15. Options for Burning LWR SNF in LIFE Engine

    SciTech Connect (OSTI)

    Farmer, J

    2008-09-09

    We have pursued two processes in parallel for the burning of LWR SNF in the LIFE engine: (1) solid fuel option and (2) liquid fuel option. Approaches with both are discussed. The assigned Topical Report on liquid fuels is attached.

  16. Evaluation of Internal Criticality of the Plutonium Dispostion MOX SNF Waste Form

    SciTech Connect (OSTI)

    A.A. Alsaed

    1999-09-28

    The purpose of this calculation is to perform a parametric study to determine the effects of fission product leaching, assembly collapse, and iron oxide loss ({Delta}Fe{sub 2}O{sub 3}) on the reactivity of a waste package (WP) containing mixed oxide (MOX) spent nuclear fuel (SNF). Previous calculations (CRWMS M&O 1998a) have shown that the criticality control features of the WP are adequate to prevent criticality of a flooded WP for all the enrichment/burnup pairs expected for the MOX SNF. Therefore, the objective of this calculation is to determine the increase in reactivity that might result from possible degradation of the WP criticality control features. Specifically, this calculation tests the sensitivity of effective neutron multiplication factor (k{sub eff}) to loss (from the WP) of the following: (1) fission product neutron absorbers, or (2) moderator displacement material (principally, the iron oxide that results from the corrosion of carbon steel).

  17. Flow Test At Fish Lake Valley Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Fish Lake Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Fish Lake Valley Area (DOE GTP) Exploration Activity...

  18. Comments on DOE's Verification Testing in Support of ENERGY STAR® Draft Process Document

    Broader source: Energy.gov [DOE]

    On April 22, 2011, The U.S. Department of Energy (DOE) released a draft of DOE's Verification Testing in Support of ENERGY STAR Process Plan for 2011. DOE accepted comments through May 9, 2011 and...

  19. How Does Your Fuel Economy Compare to the Test Ratings on Fueleconomy...

    Office of Environmental Management (EM)

    Does Your Fuel Economy Compare to the Test Ratings on Fueleconomy.gov? How Does Your Fuel Economy Compare to the Test Ratings on Fueleconomy.gov? November 12, 2009 - 8:36am Addthis ...

  20. Thermal Evaluation for the Naval SNF Waste Package

    SciTech Connect (OSTI)

    T.L. Mitchell

    2000-04-25

    The purpose of this calculation is to evaluate the thermal performance of the naval long spent nuclear fuel (SNF) waste package (WP) under multiple disposal conditions in a monitored geologic repository (MGR). The scope of this calculation is limited to determination of thermal temperature profiles upon the surface of, and within, the naval long SNF WP. The objective is to develop a temperature profile history within the WP, at time increments up to 10,000 years of emplacement. The results of this calculation are intended to support the Naval SNF WP Analysis and Model Report (AMR) for Site Recommendation (SR). This calculation was performed to the specifications within its Technical Development Plan (TDP) (Ref. 8.16). This calculation is developed and documented in accordance with the AP-3.12Q/REV. 0IICN. 0 procedure, Calculations.

  1. Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

    SciTech Connect (OSTI)

    IRWIN, J.J.

    2000-11-18

    The mission of the Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying Facility (CVDF) is to achieve the earliest possible removal of free water from Multi-Canister Overpacks (MCOs). The MCOs contain metallic uranium SNF that have been removed from the 100K Area fuel storage water basins (i.e., the K East and K West Basins) at the US. Department of Energy Hanford Site in Southeastern Washington state. Removal of free water is necessary to halt water-induced corrosion of exposed uranium surfaces and to allow the MCOs and their SNF payloads to be safely transported to the Hanford Site 200 East Area and stored within the SNF Project Canister Storage Building (CSB). The CVDF is located within a few hundred yards of the basins, southwest of the 165KW Power Control Building and the 105KW Reactor Building. The site area required for the facility and vehicle circulation is approximately 2 acres. Access and egress is provided by the main entrance to the 100K inner area using existing roadways. The CVDF will remove free. water from the MCOs to reduce the potential for continued fuel-water corrosion reactions. The cold vacuum drying process involves the draining of bulk water from the MCO and subsequent vacuum drying. The MCO will be evacuated to a pressure of 8 torr or less and backfilled with an inert gas (helium). The MCO will be sealed, leak tested, and then transported to the CSB within a sealed shipping cask. (The MCO remains within the same shipping Cask from the time it enters the basin to receive its SNF payload until it is removed from the Cask by the CSB MCO handling machine.) The CVDF subproject acquired the required process systems, supporting equipment, and facilities. The cold vacuum drying operations result in an MCO containing dried fuel that is prepared for shipment to the CSB by the Cask transportation system. The CVDF subproject also provides equipment to dispose of solid wastes generated by the cold vacuum drying process and transfer process water removed

  2. NRC Transportation Security (Part 73 SNF Update and Part 37 Category...

    Office of Environmental Management (EM)

    NRC Transportation Security (Part 73 SNF Update and Part 37 Category 1 and 2 Materials) NRC Transportation Security (Part 73 SNF Update and Part 37 Category 1 and 2 Materials) PDF...

  3. A Green Approach to SNF Reprocessing: Are Common Household Reagents the Answer?

    SciTech Connect (OSTI)

    Peper, Shane M.; McNamara, Bruce K.; O'Hara, Matthew J.; Douglas, Matthew

    2008-04-03

    It has been discovered that UO2, the principal component of spent nuclear fuel (SNF), can efficiently be dissolved at room temperature using a combination of common household reagents, namely hydrogen peroxide, baking soda, and ammonia. This rather serendipitous discovery opens up the possibility, for the first time, of considering a non-acidic process for recycling U from SNF. Albeit at the early stages of development, our unconventional dissolution approach possesses many attractive features that could make it a reality in the future. With dissolution byproducts of water and oxygen, our approach poses a minimal threat to the environment. Moreover, the use of common household reagents to afford actinide oxide dissolution suggests a certain degree of economic favorability. With the use of a “closed” digestion vessel as a reaction chamber, our approach has substantial versatility with the option of using either aqueous or gaseous reactant feeds or a combination of both. Our approach distinguishes itself from all existing reprocessing technologies in two important ways. First and foremost, it is an alkaline rather than an acidic process, using mild non-corrosive chemicals under ambient conditions to effect actinide separations. Secondly, it does not dissolve the entire SNF matrix, but rather selectively solubilizes U and other light actinides for subsequent separation, resulting in potentially faster head-end dissolution and fewer downstream separation steps. From a safeguards perspective, the use of oxidizing alkaline solutions to effect actinide separations also potentially offers a degree of inherent proliferation resistance, by allowing the U to be selectively removed from the remaining dissolver solution while keeping Pu grouped with the other minor actinides and fission products. This paper will describe the design and general experimental setup of a “closed” digestion vessel for performing uranium oxide dissolutions under alkaline conditions using

  4. DOE completes environmental assessment on INL National Security Test Range

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

    (NNSA) celebrates Earth Day Tuesday, April 22, 2014 - 4:01pm DOE today celebrated Earth Day with Community Day on the DOE Pavilion. More than 20 local green exhibitors, including various DOE departments, showcased their environmental programs. Here Fred Winter and Joyce Kim promote modernizing the grid through innovative technology. DOE celebrates Earth Day Related Topics community education environment Related News Pantex makes paper into compost Concern for the Environment Department of

  5. Comparison of Real World Energy Consumption to Models and DOE Test

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

    Procedures | Department of Energy Comparison of Real World Energy Consumption to Models and DOE Test Procedures Comparison of Real World Energy Consumption to Models and DOE Test Procedures This study investigates the real-world energy performance of appliances and equipment as it compares with models and test procedures. The study looked to determine whether DOE and industry test procedures actually replicate real world conditions, whether performance degrades over time, and whether

  6. DOE Hosts Solid-State Lighting Commercial Product Testing Program Workshop

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) hosted a workshop on October 27, 2006, to introduce the DOE SSL Commercial Product Testing Program. The workshop, held in Washington, D.C., drew over 40...

  7. U.S. DOE/OE National SCADA Test Bed Supports | Department of...

    Energy Savers [EERE]

    U.S. DOEOE National SCADA Test Bed Supports U.S. DOEOE National SCADA Test Bed Supports To help advance the U.S. Department of Energy (DOE) National SCADA Test Bed's (NSTB) ...

  8. Plan for Characterization of K Basin Spent Nuclear Fuel (SNF) and Sludge (OCRWM)

    SciTech Connect (OSTI)

    TRIMBLE, D.J.

    2000-08-24

    This is an update of the plan for the characterization of spent nuclear fuel (SNF) and sludge stored in the Hanford K West and K East Basins. The purpose of the characterization program is to provide fuel and sludge data in support of the SNF Project in the effort to remove the fuel from the K Basins and place it into dry storage. Characterization of the K Basin fuel and sludge was initiated in 1994 and has been guided by the characterization plans (Abrefah 1994, Lawrence 1995a, Lawrence 1995b) and the characterization program management plan (PMP) (Lawrence 1995c, Lawrence 1998, Trimble 1999). The fuel characterization was completed in 1999. Summaries of these activities were documented by Lawrence (1999) and Suyama (1999). Lawrence (1999) is a summary report providing a road map to the detailed documentation of the fuel characterization. Suyama (1999) provides a basis for the limited characterization sample size as it relates to supporting design limits and the operational safety envelope for the SNF Project. The continuing sludge characterization is guided by a data quality objective (DQO) (Makenas 2000) and a sampling and analysis plan (SAP) (Baker, Welsh and Makenas 2000) The original intent of the characterization program was ''to provide bounding behavior for the fuel'' (Lawrence 1995a). To accomplish this objective, a fuel characterization program was planned that would provide data to augment data from the literature. The program included in-situ examinations of the stored fuel and laboratory testing of individual elements and small samples of fuel (Lawrence 1995a). Some of the planned tests were scaled down or canceled due to the changing needs of the SNF Project. The fundamental technical basis for the process that will be used to place the K Basin fuel into dry storage was established by several key calculations. These calculations characterized nominal and bounding behavior of fuel in Multi-Canister Overpacks (MCOs) during processing and storage

  9. HIC1 interacts with a specific subunit of SWI/SNF complexes, ARID1A/BAF250A

    SciTech Connect (OSTI)

    Van Rechem, Capucine; Boulay, Gaylor; Leprince, Dominique

    2009-08-07

    HIC1, a tumor suppressor gene epigenetically silenced in many human cancers encodes a transcriptional repressor involved in regulatory loops modulating p53-dependent and E2F1-dependent cell survival and stress responses. HIC1 is also implicated in growth control since it recruits BRG1, one of the two alternative ATPases (BRM or BRG1) of SWI/SNF chromatin-remodeling complexes to repress transcription of E2F1 in quiescent fibroblasts. Here, through yeast two-hybrid screening, we identify ARID1A/BAF250A, as a new HIC1 partner. ARID1A/BAF250A is one of the two mutually exclusive ARID1-containing subunits of SWI/SNF complexes which define subsets of complexes endowed with anti-proliferative properties. Co-immunoprecipitation assays in WI38 fibroblasts and in BRG1-/- SW13 cells showed that endogenous HIC1 and ARID1A proteins interact in a BRG1-dependent manner. Furthermore, we demonstrate that HIC1 does not interact with BRM. Finally, sequential chromatin immunoprecipitation (ChIP-reChIP) experiments demonstrated that HIC1 represses E2F1 through the recruitment of anti-proliferative SWI/SNF complexes containing ARID1A.

  10. CORROSION MONITORING OF PLUTONIUM OXIDE AND SNF

    SciTech Connect (OSTI)

    Douglas, D.G.; Haas, C.M.; Smith, C.M.; Ohl, P.C.

    2003-02-27

    While developing a method to measure pressure in totally sealed stainless steel containers holding spent nuclear fuel at the U.S. DOE Hanford Site, Vista Engineering Technologies, LLC (Vista Engineering) personnel adapted the central concept to corrosion monitoring techniques for the same containers. The ability to monitor corrosion within vessels containing spent nuclear fuel, plutonium and other hazardous materials is imperative for safe storage. Vista Engineering personnel have devised a way to monitor corrosion in a totally sealed stainless steel container using a Magnetically Coupled Corrosion Gauge (MCCG) Patent Pending. The MCCG can be used to detect corrosion as well as measure corrosion rate and does not require any penetration of the containment vessel, which minimizes pressure boundary surface area and sensitive weld materials in the vessels.

  11. Sandia Energy - Joint Sandia-DOE-HMRC Testing of a Floating Oscillatin...

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

    Oscillating Water Column Wave Energy Converter Device Home Renewable Energy Energy Water Power Partnership News News & Events Joint Sandia-DOE-HMRC Testing of a Floating...

  12. Flow Test At Jemez Pueblo Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Jemez Pueblo Area (DOE GTP) Exploration Activity Details Location Jemez Pueblo Area...

  13. Flow Test At Black Warrior Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Black Warrior Area (DOE GTP) Exploration Activity Details Location Black Warrior...

  14. Flow Test At Gabbs Valley Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Gabbs Valley Area (DOE GTP) Exploration Activity Details Location Gabbs Valley Area...

  15. Flow Test At Newberry Caldera Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Newberry Caldera Area (DOE GTP) Exploration Activity Details Location Newberry...

  16. Flow Test At San Emidio Desert Area (DOE GTP) | Open Energy Informatio...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At San Emidio Desert Area (DOE GTP) Exploration Activity Details Location San Emidio...

  17. Flow Test At Rye Patch Area (DOE GTP, 2011) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Rye Patch Area (DOE GTP, 2011) Exploration Activity Details Location Rye Patch Area...

  18. Flow Test At Mccoy Geothermal Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Mccoy Geothermal Area (DOE GTP) Exploration Activity Details Location Mccoy...

  19. Flow Test At Glass Buttes Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Glass Buttes Area (DOE GTP) Exploration Activity Details Location Glass Buttes Area...

  20. Flow Test At Flint Geothermal Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Flint Geothermal Area (DOE GTP) Exploration Activity Details Location Flint...

  1. Flow Test At The Needles Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At The Needles Area (DOE GTP) Exploration Activity Details Location The Needles Area...

  2. Flow Test At Crump's Hot Springs Area (DOE GTP) | Open Energy...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Crump's Hot Springs Area (DOE GTP) Exploration Activity Details Location Crump's Hot...

  3. Flow Test At Mcgee Mountain Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Mcgee Mountain Area (DOE GTP) Exploration Activity Details Location Mcgee Mountain...

  4. Flow Test At Fort Bliss Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Fort Bliss Area (DOE GTP) Exploration Activity Details Location Fort Bliss Area...

  5. Flow Test At Silver Peak Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Silver Peak Area (DOE GTP) Exploration Activity Details Location Silver Peak Area...

  6. Flow Test At Pilgrim Hot Springs Area (DOE GTP) | Open Energy...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Pilgrim Hot Springs Area (DOE GTP) Exploration Activity Details Location Pilgrim Hot...

  7. Flow Test At Hot Pot Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Hot Pot Area (DOE GTP) Exploration Activity Details Location Hot Pot Area...

  8. Flow Test At Snake River Plain Region (DOE GTP) | Open Energy...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Snake River Plain Region (DOE GTP) Exploration Activity Details Location Snake River...

  9. Flow Test At New River Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At New River Area (DOE GTP) Exploration Activity Details Location New River Area...

  10. Flow Test At Soda Lake Area (DOE GTP) | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Soda Lake Area (DOE GTP) Exploration Activity Details Location Soda Lake Area...

  11. DOE/NV/11718--1080 Nevada Test Site

    National Nuclear Security Administration (NNSA)

    ... 0% 0% Average MDC: 1189 0.139 0.027 0.007 Green shaded results are considered detected ... Dose Assessment U.S. Department of Energy (DOE) Order 450.1 Environmental ...

  12. Test 2 | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    Test 2 Web Policies Test 2 Contact Information Office of Science U.S. Department of Energy 1000 Independence Ave., SW Washington, DC 20585 P: (202) 586-5430 Test 2 Print Text Size:...

  13. CHARACTERISTICS OF NEXT-GENERATION SPENT NUCLEAR FUEL (SNF) TRANSPORT AND STORAGE CASKS

    SciTech Connect (OSTI)

    Haire, M.J.; Forsberg, C.W.; Matveev, V.Z.; Shapovalov, V.I.

    2004-10-03

    The design of spent nuclear fuel (SNF) casks used in the present SNF disposition systems has evolved from early concepts about the nuclear fuel cycle. The reality today is much different from that envisioned by early nuclear scientists. Most SNF is placed in pool storage, awaiting reprocessing (as in Russia) or disposal at a geologic SNF repository (as in the United States). Very little transport of SNF occurs. This paper examines the requirements for SNF casks from today's perspective and attempts to answer this question: What type of SNF cask would be produced if we were to start over and design SNF casks based on today's requirements? The characteristics for a next-generation SNF cask system are examined and are found to be essentially the same in Russia and the United States. It appears that the new depleted uranium dioxide (DUO2)-steel cermet material will enable these requirements to be met. Depleted uranium (DU) is uranium in which a portion of the 235U isotope has been removed during a uranium enrichment process. The DUO2-steel cermet material is described. The United States and Russia are cooperating toward the development of a next-generation, dual-purpose, storage and transport SNF system.

  14. DOE - NNSA/NFO -- Nuclear Testing Archive Fee Schedule

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

    Nuclear Testing Archive > Fee Schedule NNSANFO Language Options U.S. DOENNSA - Nevada Field Office Nuclear Testing Archive (NTA) Fee Schedule The U.S. Department of Energy ...

  15. DOE - Office of Legacy Management -- Geothermal Test Facility...

    Office of Legacy Management (LM)

    Geothermal Test Facility - 001 FUSRAP Considered Sites Site: Geothermal Test Facility (001) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site ...

  16. DOE - Office of Legacy Management -- Nevada Test Site - 023

    Office of Legacy Management (LM)

    Nevada Test Site - 023 FUSRAP Considered Sites Site: Nevada Test Site (023) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: ...

  17. DOE Issues Test Procedure Final Rule & Publishes Energy Conservation...

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

    issued a pre-publication Federal Register final rule regarding test procedures for electric motors. For more information, please visit the rulemaking page. Test Procedure: All...

  18. SNF fuel retrieval sub project safety analysis document

    SciTech Connect (OSTI)

    BERGMANN, D.W.

    1999-02-24

    This safety analysis is for the SNF Fuel Retrieval (FRS) Sub Project. The FRS equipment will be added to K West and K East Basins to facilitate retrieval, cleaning and repackaging the spent nuclear fuel into Multi-Canister Overpack baskets. The document includes a hazard evaluation, identifies bounding accidents, documents analyses of the accidents and establishes safety class or safety significant equipment to mitigate accidents as needed.

  19. Secretary Bodman's Memorandum Regarding Drug Testing at DOE

    Broader source: Energy.gov [DOE]

    Decisions regarding drug testing for Department of Energy positions that require access authorizations (Security Clearances)

  20. DOE to Build Hydrogen Fuel Test Facility at West Virginia Airport...

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

    to Build Hydrogen Fuel Test Facility at West Virginia Airport DOE to Build Hydrogen Fuel Test Facility at West Virginia Airport March 25, 2009 - 1:00pm Addthis Washington, DC - The ...

  1. DOE Announces $11 Million for Seven New Projects to Test New...

    Energy Savers [EERE]

    for Seven New Projects to Test New Options for Optimal Efficiency of the U.S. Electric Grid DOE Announces 11 Million for Seven New Projects to Test New Options for Optimal ...

  2. Preliminary Criticality Analysis of Degraded SNF Accumulations to a Waste Package (SCPB: N/A) 

    SciTech Connect (OSTI)

    J.W. Davis

    2005-12-15

    This study is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to provide input to a separate evaluation on the probability of criticality in the far-field environment. These calculations are performed in sufficient detail to provide conservatively bounding configurations to support separate probabilistic analyses. The objective of this evaluation is to provide input to a risk analysis which will show that criticalities involving commercial spent nuclear fuel (SNF) are not credible, or indicate additional measures that are required for the Engineered Barrier Segment (EBS) to make such events incredible. Minimum critical volumes and masses of UO{sub 2}/H{sub 2}O/tuff mixtures are determined without application of regulatory safety limits. This study does not address or demonstrate compliance with regulatory limits.

  3. DOE - Office of Legacy Management -- Tatum Salt Dome Test Site - MS 01

    Office of Legacy Management (LM)

    Tatum Salt Dome Test Site - MS 01 Site ID (CSD Index Number): MS.01 Site Name: Tatum Salt Dome Test Site Site Summary: Site Link: http://www.lm.doe.gov/salmon/Sites.aspx External Site Link: Alternate Name(s): Tatum Salt Dome Test Site Alternate Name Documents: Location: Salmon, Mississippi Location Documents: Historical Operations (describe contaminants): Underground nuclear test site Historical Operations Documents: Eligibility Determination: Remediated by DOE Eligibility Determination

  4. New Diabetes Testing Technology | netl.doe.gov

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

    New Diabetes Testing Technology Collaborative Technology Demonstrates Potential in Diabetes Testing Diabetes is a disease afflicting tens of millions of people. Current diagnostic testing can include expensive doctor's visits and invasive testing, which makes diagnosing and monitoring the disease anything but straightforward. One symptom of diabetes is "fruity" breath, which may occur when the body cannot produce or use insulin effectively. Glucose is our body's main source of energy,

  5. DOE - NNSA/NFO -- News & Views Tunnel Test

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

    Tunnel Tests Span 35 years of Nevada Test Site History Photo - Rainer a 1.7 kiloton tunnel test On August 10, 1957, a zero-yield safety experiment named "Saturn" was detonated in C-Tunnel. Since then tests have been conducted in 16 different tunnels in Rainier Mesa on the Nevada Test Site. Today, there is only one active tunnel used by the Defense Nuclear Agency (DNA). The DNA evaluates the effects of nuclear weapons explosions, thermal radiation, blast, shock, x-rays and gamma rays,

  6. DOE/OE National SCADA Test Bed Fiscal Year 2009 Work Plan | Department of

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

    Energy OE National SCADA Test Bed Fiscal Year 2009 Work Plan DOE/OE National SCADA Test Bed Fiscal Year 2009 Work Plan This document is designed to help guide and strengthen the DOE/OE NSTB program's research and development (R&D) of advance security tools and to heighten awareness among energy sector partners of the more than 30 NSTB projects underway in FY2009. DOE/OE National SCADA Test Bed Fiscal Year 2009 Work Plan (260.95 KB) More Documents & Publications National SCADA Test

  7. DOE Publishes Final Rule for Plumbing Products Test Procedures

    Broader source: Energy.gov [DOE]

    The Department of Energy has published a final rule regarding test procedures for showerheads, faucets, water closets, urinals, and commercial prerinse spray valves.

  8. DOE Verification Testing in Support of ENERGY STAR, April 22...

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

    Comment submitted by Hoshizaki America, Inc. regarding the Energy Star Verification Testing Program Comment submitted by the North American Association of Food Equipment ...

  9. Matrix, Drug Testing for DOE Security Clearance- September 1, 2011

    Broader source: Energy.gov [DOE]

    The following matrix identifies those individuals required to have a current negative drug test as a prerequisite for being processed for a security clearance

  10. Memorandum, Drug Testing at DOE - September 14, 2007 | Department...

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

    Q or L access authorization (security clearance) will be in Testing Designated Positions ... further consideration for a security clearance, until such time as they can demonstrate ...

  11. Assessment of Disposal Options for DOE-Managed High-Level Radioactive Waste and Spent Nuclear Fuel

    Broader source: Energy.gov [DOE]

    The Assessment of Disposal Options for DOE-Managed High-Level Radioactive Waste and Spent Nuclear Fuel report assesses the technical options for the safe and permanent disposal of high-level radioactive waste (HLW) and spent nuclear fuel (SNF) managed by the Department of Energy. Specifically, it considers whether DOE-managed HLW and SNF should be disposed of with commercial SNF and HLW in one geologic repository or whether there are advantages to developing separate geologic disposal pathways for some DOE-managed HLW and SNF. The report recommends that the Department begin implementation of a phased, adaptive, and consent-based strategy with development of a separate mined repository for some DOE-managed HLW and cooler DOE-managed SNF.

  12. Spent Nuclear Fuel (SNF) Removal Campaign Plan

    SciTech Connect (OSTI)

    PAJUNEN, A.L.

    2000-08-07

    The overall operation of the Spent Nuclear Fuel Project will include fuel removal, sludge removal, debris removal, and deactivation transition activities. Figure 1-1 provides an overview of the current baseline operating schedule for project sub-systems, indicating that a majority of fuel removal activities are performed over an approximately three-and-one-half year time period. The purpose of this document is to describe the strategy for operating the fuel removal process systems. The campaign plan scope includes: (1) identifying a fuel selection sequence during fuel removal activities, (2) identifying MCOs that are subjected to extra testing (process validation) and monitoring, and (3) discussion of initial MCO loading and monitoring in the Canister Storage Building (CSB). The campaign plan is intended to integrate fuel selection requirements for handling special groups of fuel within the basin (e.g., single pass reactor fuel), process validation activities identified for process systems, and monitoring activities during storage.

  13. DOE National SCADA Test Bed Program Multi-Year Plan | Department of Energy

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

    National SCADA Test Bed Program Multi-Year Plan DOE National SCADA Test Bed Program Multi-Year Plan This document presents the National SCADA Test Bed Program Multi-Year Plan, a coherent strategy for improving the cyber security of control systems in the energy sector. The NSTB Program is conducted within DOE's Office of Electricity Delivery and Energy Reliability (OE), which leads national efforts to modernize the electric grid, enhance the security and reliability of the energy infrastructure,

  14. Issues related to EM management of DOE spent nuclear fuel

    SciTech Connect (OSTI)

    Abbott, D.G.; Abashian, M.S.; Chakraborti, S.; Roberson, K.; Meloin, J.M.

    1993-07-01

    This document is a summary of the important issues involved in managing spent nuclear fuel (SNF) owned by the Department of Energy (DOE). Issues related to civilian SNF activities are not discussed. DOE-owned SNF is stored primarily at the Hanford Site, Idaho National Engineering Laboratory (INEL), Savannah River Site (SRS), Oak Ridge National Laboratory (ORNL), and West Valley Demonstration Project. Smaller quantities of SNF are stored at Brookhaven National Laboratory, Sandia National Laboratories, and Los Alamos National Laboratory (LANL). There is a wide variety of fuel types, including both low and high enrichment fuels from weapons production, DOE reactors, research and development programs, naval programs, and universities. Most fuel is stored in pools associated with reactor or reprocessing facilities. Smaller quantities are in dry storage. Physical conditions of the fuel range from excellent to poor or severely damaged. An issue is defined as an important question that must be answered or decision that must be made on a topic or subject relevant to achieving the complimentary objectives of (a) storing SNF in compliance with applicable regulations and orders until it can be disposed, and (b) safely disposing of DOE`s SNF. The purpose of this document is to define the issues; no recommendations are made on resolutions. As DOE`s national SNF management program is implemented, a system of issues identification, documentation, tracking, and resolution will be implemented. This document is an initial effort at issues identification. The first section of this document is an overview of issues that are common to several or all DOE facilities that manage SNF. The common issues are organized according to specific aspects of spent fuel management. This is followed by discussions of management issues that apply specifically to individual DOE facilities. The last section provides literature references.

  15. Experimental Test Plan DOE Tidal and River Reference Turbines

    SciTech Connect (OSTI)

    Neary, Vincent S; Hill, Craig; Chamorro, Leonardo; Gunawan, Budi

    2012-09-01

    Our aim is to provide details of the experimental test plan for scaled model studies in St. Anthony Falls Laboratory (SAFL) Main Channel at the University of Minnesota, including a review of study objectives, descriptions of the turbine models, the experimental set-up, instrumentation details, instrument measurement uncertainty, anticipated experimental test cases, post-processing methods, and data archiving for model developers.

  16. Hazard Evaluation for Storage of Spent Nuclear Fuel (SNF) Sludge at the Solid Waste Treatment Facility

    SciTech Connect (OSTI)

    SCHULTZ, M.V.

    2000-08-22

    As part of the Spent Nuclear Fuel (SNF) storage basin clean-up project, sludge that has accumulated in the K Basins due to corrosion of damaged irradiated N Reactor will be loaded into containers and placed in interim storage. The Hanford Site Treatment Complex (T Plant) has been identified as the location where the sludge will be stored until final disposition of the material occurs. Long term storage of sludge from the K Basin fuel storage facilities requires identification and analysis of potential accidents involving sludge storage in T Plant. This report is prepared as the initial step in the safety assurance process described in DOE Order 5480.23, Nuclear Safety Analysis Reports and HNF-PRO-704, Hazards and Accident Analysis Process. This report documents the evaluation of potential hazards and off-normal events associated with sludge storage activities. This information will be used in subsequent safety analyses, design, and operations procedure development to ensure safe storage. The hazards evaluation for the storage of SNF sludge in T-Plant used the Hazards and Operability Analysis (HazOp) method. The hazard evaluation identified 42 potential hazardous conditions. No hazardous conditions involving hazardous/toxic chemical concerns were identified. Of the 42 items identified in the HazOp study, eight were determined to have potential for onsite worker consequences. No items with potential offsite consequences were identified in the HazOp study. Hazardous conditions with potential onsite worker or offsite consequences are candidates for quantitative consequence analysis. The hazardous conditions with potential onsite worker consequences were grouped into two event categories, Container failure due to overpressure - internal to T Plant, and Spill of multiple containers. The two event categories will be developed into accident scenarios that will be quantitatively analyzed to determine release consequences. A third category, Container failure due to

  17. Template for Contracting Company Drug Testing for DOE Positions

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

    Address of Requestor Dear Sir or Madam: Subject: Last name, First name Middle initial - [last four digits of the SSN] xxx-xx-0123 This letter is in response to a request from [insert name of requestor] received on [insert date] to process [insert name] for a Department of Energy (DOE) security clearance in connection with his/her employment as [insert position] with [insert company name] under [insert site office] Contract No.: [insert contract number] Please be advised that your request for a

  18. DOE - Office of Legacy Management -- Shoal Test Site - NV 03

    Office of Legacy Management (LM)

    Shoal Test Site - NV 03 FUSRAP Considered Sites Site: SHOAL TEST SITE (NV.03 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: Sand Springs Range NV.03-1 Location: Near U.S. Highway 50 , Fallon , Nevada NV.03-2 Evaluation Year: 1987 NV.03-2 Site Operations: Underground nuclear detonation site. NV.03-1 Site Disposition: Eliminated - Potential for contamination remote NV.03-2 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: None

  19. Evaluation of codisposal viability of MOX (FFTF) DOE-owned fuel: Phase 2 -- Degraded mode calculations

    SciTech Connect (OSTI)

    Goluoglu, S.; Angers, L.; Davis, J.W.; Stockman, H.; Gottlieb, P.; Montierth, L.M.

    1999-07-01

    The authors provide the degraded criticality information that supports the disposal of spent nuclear fuel (SNF) from the US Department of Energy's (DOE's) Fast Flux Test facility (FFTF) in the potential Monitored Geologic Repository (MGR) at Yucca Mountain. FFTF is one of more than 250 forms of DOE-owned SNF. Because of the variety of the SNF, the National Spent Nuclear Fuel Program has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. The FFTF fuel is a mixture of uranium and plutonium oxides and is representative of the mixed-oxide fuel (MOX) group. The analyses were performed according to the disposal criticality analysis methodology that was documented in the topical report submitted to the US nuclear Regulatory Commission (YMP/TR-004Q). The methodology includes analyzing the geochemical and physical processes that can breach the waste package and degrade the waste forms. This paper summarizes the results of geochemistry degradation analysis and the criticality calculations using the degradation products.

  20. DOE - Office of Legacy Management -- Trinity Test Site - NM 17

    Office of Legacy Management (LM)

    Trinity Test Site - NM 17 FUSRAP Considered Sites Site: TRINITY TEST SITE (NM.17 ) Eliminated from consideration under FUSRAP - U.S. Army controls site Designated Name: Not Designated Alternate Name: None Location: missile range - 30 miles west of Carrizozo , White Sands , New Mexico NM.17-1 Evaluation Year: 1985 NM.17-1 Site Operations: Detonation of the first atomic bomb occurred at this site. NM.17-1 Site Disposition: Eliminated NM.17-1 Radioactive Materials Handled: Yes Primary Radioactive

  1. DOE - Office of Legacy Management -- Amchitka Island Test Center - AK 01

    Office of Legacy Management (LM)

    Amchitka Island Test Center - AK 01 Site ID (CSD Index Number): AK.01 Site Name: Amchitka Island Test Center Site Summary: Site Link: Amchitka Island Test Center External Site Link: Alternate Name(s): Amchitka Island Test Center Alternate Name Documents: Location: Amchitka, Alaska Location Documents: Historical Operations (describe contaminants): Underground nuclear test site Historical Operations Documents: Eligibility Determination: Remediated by DOE Eligibility Determination Documents:

  2. Electrolux Gibson Air Conditioner and Equator Clothes Washer Fail DOE Energy Star Testing

    Broader source: Energy.gov [DOE]

    DOE testing in support of the ENERGY STAR program has revealed that an Electrolux Gibson air conditioner (model GAH105Q2T1) and an Equator clothes washer (model EZ 3720 CEE), both of which claimed...

  3. DOE Issues Test Procedure Final Rule & Publishes Energy Conservation Standards NOPR for Electric Motors

    Broader source: Energy.gov [DOE]

    The Department of Energy (DOE) has issued a pre-publication Federal Register final rule regarding test procedures and published a notice of proposed rulemaking (NOPR) regarding energy conservation standards for electric motors.

  4. SNF sludge treatment system preliminary project execution plan

    SciTech Connect (OSTI)

    Flament, T.A.

    1998-03-03

    The Fluor Daniel Hanford, Inc. (FDH) Project Director for the Spent Nuclear Fuel (SNF) Project has requested Numatec Hanford Company (NHC) to define how Hanford would manage a new subproject to provide a process system to receive and chemically treat radioactive sludge currently stored in the 100 K Area fuel retention basins. The subproject, named the Sludge Treatment System (STS) Subproject, provides and operates facilities and equipment to chemically process K Basin sludge to meet Tank Waste Remediation System (TWRS) requirements. This document sets forth the NHC management approach for the STS Subproject and will comply with the requirements of the SNF Project Management Plan (HNF-SD-SNFPMP-011). This version of this document is intended to apply to the initial phase of the subproject and to evolve through subsequent revision to include all design, fabrication, and construction conducted on the project and the necessary management and engineering functions within the scope of the subproject. As Project Manager, NHC will perform those activities necessary to complete the STS Subproject within approved cost and schedule baselines and turn over to FDH facilities, systems, and documentation necessary for operation of the STS.

  5. DOE Verification Testing in Support of ENERGY STAR, April 22, 2011 |

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

    Department of Energy Verification Testing in Support of ENERGY STAR, April 22, 2011 DOE Verification Testing in Support of ENERGY STAR, April 22, 2011 This document describes ENERGY STAR verificaion testing process, dated April 22, 2011 estar_verification_process.pdf (368.74 KB) More Documents & Publications Comment submitted by Hoshizaki America, Inc. regarding the Energy Star Verification Testing Program Comment submitted by the North American Association of Food Equipment

  6. DOE Spent Nuclear Fuel Group in Support of Criticality, DBE, TSPA-LA

    SciTech Connect (OSTI)

    Henry Loo

    2000-05-01

    This report presents the basis for grouping the over 250 Department of Energy (DOE) spent nuclear fuel (SNF) types in support of analyses for final repository disposal. For each of the required analyses, the parameters needed in conducting the analyses were identified and reviewed. The grouping proposed for the three types of analyses (criticality, design basis events, and total system performance assessment) are based on the similarities of DOE SNF as a function of these parameters. As necessary, further justifications are provided to further reduce the DOE SNF grouping in support of the Office of Civilian Radioactive Waste Management System’s preclosure and postclosure safety cases.

  7. DOE Notice of Proposed Rulemaking to Amend the External Power Supply Test

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

    Procedure; Docket No. EERE-2014-BT-TP-0043 / RIN 1904-AD36 | Department of Energy Proposed Rulemaking to Amend the External Power Supply Test Procedure; Docket No. EERE-2014-BT-TP-0043 / RIN 1904-AD36 DOE Notice of Proposed Rulemaking to Amend the External Power Supply Test Procedure; Docket No. EERE-2014-BT-TP-0043 / RIN 1904-AD36 On 12/19/2014, Apple Inc. met with DOE to discuss the Notice of Proposed Rulemaking to Amend the External Power Supply Test Procedure. EPS TP Ex Parte

  8. Development of design basis capacity for SNF project systems

    SciTech Connect (OSTI)

    Pajunen, A.L.

    1996-02-27

    An estimate of the design capacity for Spent Nuclear Fuel Project systems producing Multi-Canister Overpacks is developed based on completing fuel processing in a two year period. The design basis capacity for systems relates the desired annual processing rate to potential operating inefficiencies which may be actually experienced to project a design capacity for systems. The basis for estimating operating efficiency factors is described. Estimates of the design basis capacity were limited to systems actually producing the Multi-Canister Overpack. These systems include Fuel Retrieval, K Basin SNF Vacuum Drying, Canister Storage Building support for Staging and Storage, and Hot Vacuum conditioning. The capacity of other systems are assumed to be derived from these system capacities such that systems producing a Multi-Canister Overpack are not constrained.

  9. SNF Interim Storage Canister Corrosion and Surface Environment Investigations

    SciTech Connect (OSTI)

    Bryan, Charles R.; Enos, David G.

    2015-09-01

    This progress report describes work being done at Sandia National Laboratories (SNL) to assess the localized corrosion performance of container/cask materials used in the interim storage of spent nuclear fuel (SNF). Of particular concern is stress corrosion cracking (SCC), by which a through-wall crack could potentially form in a canister outer wall over time intervals that are shorter than possible dry storage times. In order for SCC to occur, three criteria must be met. A corrosive environment must be present on the canister surface, the metal must susceptible to SCC, and sufficient tensile stress to support SCC must be present through the entire thickness of the canister wall. SNL is currently evaluating the potential for each of these criteria to be met.

  10. DOE

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

    O 580 .1 A Admin Chg 1 3 10-23 2012 U.S. Department of Energyadmin change DOE O XXX.XWashington, D.C. DOE O XXX.X Chg X: XX-XX-XXXX SUBJECT: ADMINISTRATIVE CHANGE TO DOE O XXX.X, TITLE (IN ITALICS) EXPLANATION OF CHANGES. [This information can be copied from the Approval Memo] LOCATIONS OF CHANGES: Page Paragraph Changed To [Original text that was changed] [Revised text]

  11. ORNL/TM-2012/301 Experimental Test Plan - DOE Tidal And River Reference Turbines

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

    2/301 Experimental Test Plan - DOE Tidal And River Reference Turbines August 2012 Prepared by Vincent S. Neary Craig Hill Leonardo P. Chamorro Budi Gunawan Fotis Sotiropoulos DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via the U.S. Department of Energy (DOE) Information Bridge. Web site http://www.osti.gov/bridge Reports produced before January 1, 1996, may be purchased by members of the public from the following source. National Technical

  12. DOE Issues a Supplemental Notice of Proposed Rulemaking Pertaining to Test

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

    Procedures for Cooking Products | Department of Energy Supplemental Notice of Proposed Rulemaking Pertaining to Test Procedures for Cooking Products DOE Issues a Supplemental Notice of Proposed Rulemaking Pertaining to Test Procedures for Cooking Products Cooking Products_ECS_SNOPR (571.32 KB) More Documents & Publications 2014-11-24 Issuance: Test Procedures for Conventional Cooking Products; Supplementary Notice of Proposed Rulemaking ISSUANCE 2015-06-18: Energy Conservation Program:

  13. Main Principles of the Perspective System of SNF Management in Russia - 13333

    SciTech Connect (OSTI)

    Baryshnikov, Mikhail

    2013-07-01

    For the last several years the System of the Spent Nuclear Fuel management in Russia was seriously changed. The paper describes the main principles of the changes and the bases of the Perspective System of SNF Management in Russia. Among such the bases there are the theses with the interesting names like 'total knowledge', 'pollutant pays' and 'pay and forget'. There is also a brief description of the modern Russian SNF Management Infrastructure. And an outline of the whole System. The System which is - in case of Russia - is quite necessary to adjust SNF accumulation and to utilize the nuclear heritage. (authors)

  14. Standard Contract for Disposal of SNF and/or HRW | Department of Energy

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

    for Disposal of SNF and/or HRW Standard Contract for Disposal of SNF and/or HRW The following document is a contract between the United States of America, represented by the U.S. Department of Energy, and a corporation organized and existing under the laws of a given state to dispose of Spent Nuclear Fuel (SNF) and/or High-Level Radioactive Waste (HRW). (839.73 KB) More Documents & Publications Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee Information Request,

  15. DOE Releases Data Summary Report for Groundwater and Soil Tests Conducted

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

    at the Riverton UMTRCA Site | Department of Energy Data Summary Report for Groundwater and Soil Tests Conducted at the Riverton UMTRCA Site DOE Releases Data Summary Report for Groundwater and Soil Tests Conducted at the Riverton UMTRCA Site February 19, 2013 - 12:53pm Addthis Contractor, Judy Miller, S.M. Stoller Corporation Public Affairs, (970) 248-6363, jmiller@lm.doe.gov GRAND JUNCTION, Colo. - The U.S. Department of Energy today announced the availability of a Data Summary Report of

  16. Questions concerning DOE's assignment of operating and testing responsibilities for OTEC-1

    SciTech Connect (OSTI)

    Not Available

    1981-06-30

    OTEC is one of the potential energy sources being developed to provide alternatives for reducing the Nation's dependence on imported oil. When developed, OTEC is to use the temperature variants of the ocean to produce electricity and energy intensive products. OTEC-1 is a major part of DOE's developmental program for OTEC. It is a floating test facility designed primarily for conducting sea tests of the cleanability and performance of heat exchangers, a major component of OTEC systems. Related OTEC subsystems are also being tested. OTEC-1 was to be accomplished in three phases; design (phase I); construction (phase II); and operations and testing (phase III). In July 1977, DOE contracted with TRW, Inc. to design and develop the heat exchanger to be used on OTEC-1. In September 1978, DOE contracted with Global Marine to refurbish, retrofit, and deploy an old Navy ship with OTEC subsystems including TRW's heat exchanger. Together Global Marine and TRW were the OTEC-1 design and construction contractors for phases I and II with Global Marine having overall responsibility for integrating its and TRW's work. Global Marine's contract also included an option for performing work in phase III.

  17. Energy Use Test Facility: CAC-DOE solar air heater test report

    SciTech Connect (OSTI)

    Not Available

    1981-11-01

    The solar air heater testing demonstrated an attractive application for residential space heating, especially appealing to the do-it-yourself market. Simple improvements in construction, such as caulking of the glazing, could increase collector performance at little cost. The operating cost of the fan was insignificant, being less than $0.05/week. Tested in its as-shipped configuration at 96.1 cfm (3 cfm/ft/sup 2/), the useful energy delivered averaged 20,000 Btu/day for six days in December. The electrical consumption of the fan was approximately 1 kWh. Doubling the flowrate did not increase collector performance appreciably. A TRNSYS computer simulation model for this solar air heater design was validated by comparing the measured test data on January 4, 1981 with calculated values. TRNSYS predicted the measured collector outlet temperatures within +- 1.2/sup 0/F and the energy delivered within +- 3%. The excellent agreement was obtained by adjusting the collector loss coefficient to an unrealistically low value; therefore, a parametric study is recommended to determine the model sensitivity to varying different parameters. A first-order collector efficiency curve was derived from the TRNSYS simulations which compared well with the curve defined by the clear-day measured data. In addition, a linear equation for the monthly efficiency that allows a calculation of energy savings for any location was derived from simulated data. The annual energy delivered by the air heater is calculated for three cities using hourly TRNSYS simulations and Typical Meteorological Year (TMY) data. The approximate cost of materials for the heater is $144 maximum. Discounting 40% for the federal tax credit, the cost is $86. Based on 1981 electrical rates of $0.04/kWh, 2-1/2 to 3 heating seasons are required to pay back the initial cost of one collector in the TVA region.

  18. Characterization Program Management Plan for Hanford K Basin Spent Nuclear Fuel (SNF) (OCRWM)

    SciTech Connect (OSTI)

    BAKER, R.B.; TRIMBLE, D.J.

    2000-12-12

    The management plan developed to characterize the K Basin spent nuclear fuel (SNF) and sludge was originally developed for Westinghouse Hanford Company and Pacific Northwest National Laboratory to work together on a program to provide characterization data to support removal, conditioning, and subsequent dry storage of the SNF stored at the Hanford K Basins. The plan also addressed necessary characterization for the removal, transport, and storage of the sludge from the Hanford K Basins. This plan was revised in 1999 (i.e., Revision 2) to incorporate actions necessary to respond to the deficiencies revealed as the result of Quality Assurance surveillances and audits in 1999 with respect to the fuel characterization activities. Revision 3 to this Program Management Plan responds to a Worker Assessment resolution determined in Fical Year 2000. This revision includes an update to current organizational structures and other revisions needed to keep this management plan consistent with the current project scope. The plan continues to address both the SNF and the sludge accumulated at K Basins. Most activities for the characterization of the SNF have been completed. Data validation, Office of Civilian Radioactive Waste Management (OCRWM) document reviews, and OCRWM data qualification are the remaining SNF characterization activities. The transport and storage of K Basin sludge are affected by recent path forward revisions. These revisions require additional laboratory analyses of the sludge to complete the acquisition of required supporting engineering data. Hence, this revision of the management plan provides the overall work control for these remaining SNF and sludge characterization activities given the current organizational structure of the SNF Project.

  19. Preparation for the Recovery of Spent Nuclear Fuel (SNF) at Andreeva Bay, North West Russia - 13309

    SciTech Connect (OSTI)

    Field, D.; McAtamney, N.

    2013-07-01

    Andreeva Bay is located near Murmansk in the Russian Federation close to the Norwegian border. The ex-naval site was used to de-fuel nuclear-powered submarines and icebreakers during the Cold War. Approximately 22,000 fuel assemblies remain in three Dry Storage Units (DSUs) which means that Andreeva Bay has one of the largest stockpiles of highly enriched spent nuclear fuel (SNF) in the world. The high contamination and deteriorating condition of the SNF canisters has made improvements to the management of the SNF a high priority for the international community for safety, security and environmental reasons. International Donors have, since 2002, provided support to projects at Andreeva concerned with improving the management of the SNF. This long-term programme of work has been coordinated between the International Donors and responsible bodies within the Russian Federation. Options for the safe and secure management of SNF at Andreeva Bay were considered in 2004 and developed by a number of Russian Institutes with international participation. This consisted of site investigations, surveys and studies to understand the technical challenges. A principal agreement was reached that the SNF would be removed from the site altogether and transported to Russia's reprocessing facility at Mayak in the Urals. The analytical studies provided the information necessary to develop the construction plan for the site. Following design and regulatory processes, stakeholders endorsed the technical solution in April 2007. This detailed the processes, facilities and equipment required to safely remove the SNF and identified other site services and support facilities required on the site. Implementation of this strategy is now well underway with the facilities in various states of construction. Physical works have been performed to address the most urgent tasks including weather protection over one of the DSUs, installation of shielding over the cells, provision of radiation

  20. Extracellular Matrix-Regulated Gene Expression RequiresCooperation of SWI/SNF and Transcription Factors

    SciTech Connect (OSTI)

    Xu, Ren; Spencer, Virginia A.; Bissell, Mina J.

    2006-05-25

    Extracellular cues play crucial roles in the transcriptional regulation of tissue-specific genes, but whether and how these signals lead to chromatin remodeling is not understood and subject to debate. Using chromatin immunoprecipitation (ChIP) assays and mammary-specific genes as models, we show here that extracellular matrix (ECM) molecules and prolactin cooperate to induce histone acetylation and binding of transcription factors and the SWI/SNF complex to the {beta}- and ?-casein promoters. Introduction of a dominant negative Brg1, an ATPase subunit of SWI/SNF complex, significantly reduced both {beta}- and ?-casein expression, suggesting that SWI/SNF-dependent chromatin remodeling is required for transcription of mammary-specific genes. ChIP analyses demonstrated that the ATPase activity of SWI/SNF is necessary for recruitment of RNA transcriptional machinery, but not for binding of transcription factors or for histone acetylation. Coimmunoprecipitation analyses showed that the SWI/SNF complex is associated with STAT5, C/EBP{beta}, and glucocorticoid receptor (GR). Thus, ECM- and prolactin-regulated transcription of the mammary-specific casein genes requires the concerted action of chromatin remodeling enzymes and transcription factors.

  1. DESIGN OF A CONCRETE SLAB FOR STORAGE OF SNF AND HLW CASKS

    SciTech Connect (OSTI)

    J. Bisset

    2005-02-14

    This calculation documents the design of the Spent Nuclear Fuel (SNF) and High-Level Waste (HLW) Cask storage slab for the Aging Area. The design is based on the weights of casks that may be stored on the slab, the weights of vehicles that may be used to move the casks, and the layout shown on the sketch for a 1000 Metric Ton of Heavy Metal (MTHM) storage pad on Attachment 2, Sht.1 of the calculation 170-C0C-C000-00100-000-00A (BSC 2004a). The analytical model used herein is based on the storage area for 8 vertical casks. To simplify the model, the storage area of the horizontal concrete modules and their related shield walls is not included. The heavy weights of the vertical storage casks and the tensile forces due to pullout at the anchorages will produce design moments and shear forces that will envelope those that would occur in the storage area of the horizontal modules. The design loadings will also include snow and live loads. In addition, the design will also reflect pertinent geotechnical data. This calculation will document the preliminary thickness and general reinforcing steel requirements for the slab. This calculation also documents the initial design of the cask anchorage. Other slab details are not developed in this calculation. They will be developed during the final design process. The calculation also does not include the evaluation of the effects of cask drop loads. These will be evaluated in this or another calculation when the exact cask geometry is known.

  2. DOE

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

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

  3. Spent Nuclear Fuel (SNF) Project Acceptance Criteria for Light Water Reactor Spent Fuel Storage System [OCRWM PER REV2

    SciTech Connect (OSTI)

    JOHNSON, D.M.

    2000-12-20

    As part of the decommissioning of the 324 Building Radiochemical Engineering Cells there is a need to remove commercial Light Water Reactor (LWR) spent nuclear fuel (SNF) presently stored in these hot cells. To enable fuel removal from the hot cells, the commercial LWR SNF will be packaged and shipped to the 200 Area Interim Storage Area (ISA) in a manner that satisfies site requirements for SNF interim storage. This document identifies the criteria that the 324 Building Radiochemical Engineering Cell Clean-out Project must satisfy for acceptance of the LWR SNF by the SNF Project at the 200 Area ISA. In addition to the acceptance criteria identified herein, acceptance is contingent on adherence to applicable Project Hanford Management Contract requirements and procedures in place at the time of work execution.

  4. DOE response to questions from AHAM on the supplemental proposed test procedure

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

    response to questions from AHAM on the supplemental proposed test procedure for residential clothes washers"? (1) What exactly does the language in Part B mean and what is the intent? * The intent of Part B is to use the methodology that AHAM had suggested specifically for extra-hot cycles, but to make it more broadly applicable to any temperature combination that is locked out of the Normal cycle. * The proposed Part (B) language is meant to be consistent with GE's original suggestion in

  5. US Department of Energy DOE Nevada Operations Office, Nevada Test Site: Underground safety and health standards

    SciTech Connect (OSTI)

    Not Available

    1993-05-01

    The Nevada Test Site Underground Safety and Health Standards Working Group was formed at the direction of John D. Stewart, Director, Nevada Test Site Office in April, 1990. The objective of the Working Group was to compile a safety and health standard from the California Tunnel Safety Orders and OSHA for the underground operations at the NTS, (excluding Yucca Mountain). These standards are called the NTS U/G Safety and Health Standards. The Working Group submits these standards as a RECOMMENDATION to the Director, NTSO. Although the Working Group considers these standards to be the most integrated and comprehensive standards that could be developed for NTS Underground Operations, the intent is not to supersede or replace any relevant DOE orders. Rather the intent is to collate the multiple safety and health references contained in DOE Order 5480.4 that have applicability to NTS Underground Operations into a single safety and heath standard to be used in the underground operations at the NTS. Each portion of the standard was included only after careful consideration by the Working Group and is judged to be both effective and appropriate. The specific methods and rationale used by the Working Group are outlined as follows: The letter from DOE/HQ, dated September 28, 1990 cited OSHA and the CTSO as the safety and health codes applicable to underground operations at the NTS. These mandated codes were each originally developed to be comprehensive, i.e., all underground operations of a particular type (e.g., tunnels in the case of the CTSO) were intended to be adequately regulated by the appropriate code. However, this is not true; the Working Group found extensive and confusing overlap in the codes in numerous areas. Other subjects and activities were addressed by the various codes in cursory fashion or not at all.

  6. Probabilistic Performance Assessment: SCC of SNF Interim Storage...

    Office of Scientific and Technical Information (OSTI)

    DOE Contract Number: AC04-94AL85000 Resource Type: Conference Resource Relation: Conference: Proposed for presentation at the IHLRWM held April 13-16, 2015 in Charleston, SC. ...

  7. This letter is to inform AHAM that DOE is adopting a new policy regarding DOE ENERGY STAR verification testing of models that are part of the AHAM verification program.

    Broader source: Energy.gov [DOE]

    This letter is to inform AHAM that DOE is adopting a new policy regarding DOE ENERGY STAR verification testing of models that are part of the AHAM verification program.

  8. DOE (Department of Energy) nuclear weapon R and T (research, development, and testing): Objectives, roles, and responsibilities

    SciTech Connect (OSTI)

    Otey, G.R.

    1989-07-01

    An overview of the DOE nuclear weapons research, development, and testing program is given along with a description of the program objectives and the roles and responsibilities of the various involved organizations. The relationship between the DoD and DOE is described and the division of responsibilities for weapon development as well as the coordinated planning and acquisition activities are reviewed. Execution of the RD T program at the nuclear weapons laboratories is outlined. 24 refs., 3 figs.

  9. Quantifying and Addressing the DOE Material Reactivity Requirements with Analysis and Testing of Hydrogen Storage Materials & Systems

    SciTech Connect (OSTI)

    Khalil, Y. F

    2015-01-05

    The objective of this project is to examine safety aspects of candidate hydrogen storage materials and systems being developed in the DOE Hydrogen Program. As a result of this effort, the general DOE safety target will be given useful meaning by establishing a link between the characteristics of new storage materials and the satisfaction of safety criteria. This will be accomplished through the development and application of formal risk analysis methods, standardized materials testing, chemical reactivity characterization, novel risk mitigation approaches and subscale system demonstration. The project also will collaborate with other DOE and international activities in materials based hydrogen storage safety to provide a larger, highly coordinated effort.

  10. Description of the Canadian particulate-fill waste-package (WP) system for spent-nuclear fuel (SNF) and its applicability to light-water reactor SNF WPs with depleted uranium-dioxide fill

    SciTech Connect (OSTI)

    Forsberg, C.W.

    1997-10-20

    The US is beginning work on an advanced, light-water reactor (LWR), spent nuclear fuel (SNF), waste package (WP) that uses depleted uranium dioxide (UO{sub 2}) fill. The Canadian nuclear fuel waste management program has completed a 15-year development program of its repository concept for CANadian Deuterium Uranium (CANDU) reactor SNF. As one option, Canada has developed a WP that uses a glass-bead or silica-sand fill. The Canadian development work on fill materials inside WPs can provide a guide for the development of LWR SNF WPs using depleted uranium (DU) fill materials. This report summarizes the Canadian work, identifies similarities and differences between the Canadian design and the design being investigated in the US to use DU fill, and identifies what information is applicable to the development of a DU fill for LWR SNF WPs. In both concepts, empty WPs are loaded with SNF, the void space between the fuel pins and the outer void space between SNF assemblies and the inner WP wall would be filled with small particles, the WPs are then sealed, and the WPs are placed into the repository.

  11. Technical Basis Spent Nuclear Fuel (SNF) Project Radiation and Contamination Trending Program

    SciTech Connect (OSTI)

    KURTZ, J.E.

    2000-05-10

    This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, and radiation surveys of the Cold Vacuum Drying Facility (CVD) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas.

  12. Basic data report for drilling and hydrologic testing of drillhole DOE-2 at the Waste Isolation Pilot Plant (WIIP) site

    SciTech Connect (OSTI)

    Mercer, J.W.; Beauheim, R.L.; Snyder, R.P.; Fairer, G.M.

    1987-04-01

    Drillhole DOE-2 was drilled to investigate a structural depression marked by the downward displacement of stratigraphic markers in the Salado Formation. Contrary to several hypotheses, halite layers were thicker in the lower part of the Salado, not thinner as a result of any removal of halite. The upper Castile anhydrite in Drillhole DOE-2 is anomalously thick and is strongly deformed relative to the anhydrite in adjacent drillholes. In contrast, the halite was <8 ft thick and significantly thinner than usually encountered. The lower Castile anhydrite appears to be normal. The depression within the correlated marker beds in the Salado Formation in Drillhole DOE-2 is interpreted as a result of gravity-driven deformation of the underlying Castile Formation. Several stratigraphic units were hydrologically tested in Drillhole DOE-2. Testing of the unsaturated lower portion of the Dewey Lake Red Beds was unsuccessful because of exceptionally small rates of fluid intake. Drill-stem tests were conducted in five intervals in the Rustler Formation, over the Marker Bed 138-139 interval in the Salado formation, and over three sandstone members of the Bell Canyon Formation. A pumping test was conducted in the Culebra Dolomite Member of the Rustler Formation. Pressure-pulse tests were conducted over the entire Salado Formation. Fluid samples were collected from the Culebra Dolomite Member and from the Hays Member of the Bell Canyon Formation. 31 refs., 31 figs., 5 tabs.

  13. DOE-Funded Project Testing Laser CO2 Monitoring at Carbon Storage Site

    Broader source: Energy.gov [DOE]

    A project that uses lasers to monitor carbon dioxide (CO2) is being analyzed as part of the U.S. Department of Energy’s (DOE) drive to improve greenhouse gas-monitoring abilities at CO2 storage sites. The project is managed by the DOE Office of Fossil Energy’s National Energy Technology Laboratory (NETL).

  14. DOE Prepared for Implementation of Fixed-Price Hanford 222-S Laboratory Analysis and Testing Services

    Broader source: Energy.gov [DOE]

    Cincinnati - The U.S. Department of Energy (DOE) awarded a contract on May 28, 2015 to Wastren Advantage, Inc. of Piketon, Ohio, for the purpose of providing analytical laboratory services at the Department of Energy (DOE) Hanford 222-S Laboratory located in the 200 West Area of the Hanford Site near Richland, Washington.

  15. Accelerator Test Facility (ATF) | U.S. DOE Office of Science...

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

    Accelerator Test Facility (ATF) High Energy Physics (HEP) HEP Home About Research ... Experimental Tests (FACET) Accelerator Test Facility (ATF) Facility Ops Projects, ...

  16. Quality assurance program plan for SNF characterization support project

    SciTech Connect (OSTI)

    Tanke, J.M.

    1997-05-22

    This Quality Assurance Program Plan (QAPP) provides information on how the Quality Assurance Program is implemented for the Spent Nuclear Fuel Characterization Support Project. This QAPP has been developed specifically for the Spent Nuclear Fuel Characterization Support Project, per Letter of Instruction (LOI) from Duke Engineering and Services Company, letter No. DESH-9655870, dated Nov. 22, 1996. It applies to those items and tasks which affect the completion of activities identified in the work breakdown structure of the Project Management Plan (PMP) and LOI. These activities include installation of sectioning equipment and furnace, surface and subsurface examinations, sectioning for metallography, and element drying and conditioning testing, as well as project related operations within the 327 facility as it relates to the specific activities of this project. General facility activities are covered in other appropriate QA-PPS. In addition, this QAPP supports the related quality assurance activities addressed in CM-2-14, Hazardous Material Packaging and Shipping,1261 and HSRCM-1, Hanford Site Radiological Control Manual. The 327 Building is currently transitioning from being a Pacific Northwest National Laboratory (PNNL) managed facility to a Babcock and Wilcox Hanford Company (BVMC) managed facility. During this transition process existing procedures and documents will be utilized until replaced by BVMC procedures and documents. These documents conform to the requirements found in PNL-MA-70, Quality Assurance Manual and PNL-MA-8 1, Hazardous Materials Shipping Manual. The Quality Assurance Program Index (QAPI) contained in Table 1 provides a matrix which shows how project activities relate to IO CFR 830.120 and 5700.6C criteria. Quality Assurance program requirements will be addressed separate from the requirements specified in this document. Other Hanford Site organizations/companies may be utilized in support of this project and the subject organizations are

  17. Downregulation of SWI/SNF chromatin remodeling factor subunits modulates cisplatin cytotoxicity

    SciTech Connect (OSTI)

    Kothandapani, Anbarasi; Gopalakrishnan, Kathirvel; Kahali, Bhaskar; Reisman, David; Patrick, Steve M.

    2012-10-01

    Chromatin remodeling complex SWI/SNF plays important roles in many cellular processes including transcription, proliferation, differentiation and DNA repair. In this report, we investigated the role of SWI/SNF catalytic subunits Brg1 and Brm in the cellular response to cisplatin in lung cancer and head/neck cancer cells. Stable knockdown of Brg1 and Brm enhanced cellular sensitivity to cisplatin. Repair kinetics of cisplatin DNA adducts revealed that downregulation of Brg1 and Brm impeded the repair of both intrastrand adducts and interstrand crosslinks (ICLs). Cisplatin ICL-induced DNA double strand break repair was also decreased in Brg1 and Brm depleted cells. Altered checkpoint activation with enhanced apoptosis as well as impaired chromatin relaxation was observed in Brg1 and Brm deficient cells. Downregulation of Brg1 and Brm did not affect the recruitment of DNA damage recognition factor XPC to cisplatin DNA lesions, but affected ERCC1 recruitment, which is involved in the later stages of DNA repair. Based on these results, we propose that SWI/SNF chromatin remodeling complex modulates cisplatin cytotoxicity by facilitating efficient repair of the cisplatin DNA lesions. -- Highlights: Black-Right-Pointing-Pointer Stable knockdown of Brg1 and Brm enhances cellular sensitivity to cisplatin. Black-Right-Pointing-Pointer Downregulation of Brg1 and Brm impedes the repair of cisplatin intrastrand adducts and interstrand crosslinks. Black-Right-Pointing-Pointer Brg1 and Brm deficiency results in impaired chromatin relaxation, altered checkpoint activation as well as enhanced apoptosis. Black-Right-Pointing-Pointer Downregulation of Brg1 and Brm affects recruitment of ERCC1, but not XPC to cisplatin DNA lesions.

  18. Test Facility Pilot Program | U.S. DOE Office of Science (SC...

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

    Test Facility Pilot Program High Energy Physics (HEP) HEP Home About Research Science ... Background Awards Information for Investigators Test Facility Pilot Program Workshop ...

  19. Technical Basis Spent Nuclear Fuel (SNF) Project Radiation and Contamination Trending Program

    SciTech Connect (OSTI)

    ELGIN, J.C.

    2000-10-02

    This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, radiation surveys of the Cold Vacuum Drying Facility (CVD), and radiation surveys of the Canister Storage Building (CSB) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas.

  20. DOE F 2040.3 | Department of Energy

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

    40.3 DOE F 2040.3 Form is used by employees to submit claims for loss or damage to personal property to the Office of the General Counsel. EMPLOYEE CLAIM FOR LOSS OR DAMAGE TO PERSONAL PROPERTY (10.73 KB) More Documents & Publications DOE F 1520.1 National Policy Assurances to be Incorporated as Award Terms Standard Contract for Disposal of SNF and/or HRW

  1. TEST: DOE Hydrogen Storage Technical Performance Targets for Light-Duty Vehicles

    Broader source: Energy.gov [DOE]

    This table summarizes technical performance targets for hydrogen storage systems onboard light-duty vehicles. These targets were established through the U.S. DRIVE Partnership, a partnership between the U.S. Department of Energy (DOE), the U.S. Council for Automotive Research (USCAR), energy companies, and utility companies and organizations.

  2. THERMAL EVALUATION OF THE USE OF BWR MOX SNF IN THE WASTE PACKAGE DESIGN (SCPB: N/A)

    SciTech Connect (OSTI)

    H. Wang

    1997-01-23

    This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) as specified in the Waste Package Implementation Plan (pp. 4-8,4-11,4-24, 5-1, and 5-13; Ref. 5.10) and Waste Package Plan (pp. 3-15,3-17, and 3-24; Ref. 5.9). The design data request addressed herein is: (1) Characterize the conceptual 40 BWR and 24 BWR Multi-Purpose Canister (MPC) Waste Package (WP) design to show that the design is feasible for use in the MGDS environment when loaded with BWR MOX SNF. (2) Characterize the conceptual 44 BWR and 24 BWR Uncanistered Fuel (UCF) Waste Package (WP) design to show that the design is feasible for use in the MGDS environment when loaded with BWR MOX SNF. The purpose of this analysis is to respond to a concern that the long-term disposal thermal issues for the WP Design, if used with SNF designed for a MOX fuel cycle, do not preclude WP compatibility with the MGDS. The objective of this analysis is to provide thermal parameter information for the conceptual WP design with disposal container which is loaded with BWR MOX SNF under nominal MGDS repository conditions. The results are intended to show that the design has a reasonable chance to meet the MGDS design requirements for normal MGDS operation, and to provide the required guidance to determining the major design issues for future design efforts, and to show that the BWR MOX SNF loaded WP performance is similar to an WP loaded with commercial BWR SNF.

  3. DOE Publishes Notice of Proposed Rulemaking for Commercial Refrigeration Equipment Test Procedure

    Broader source: Energy.gov [DOE]

    The Department of Energy has published a notice of proposed rulemaking regarding test procedures for commercial refrigeration equipment.

  4. DOE - Office of Legacy Management -- Central Nevada Test Site - NV 02

    Office of Legacy Management (LM)

    Central Nevada Test Site - NV 02 FUSRAP Considered Sites Site: Central Nevada Test Site (NV.02 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Central Nevada Test Area (CNTA), Nevada, Site Documents Related to Central Nevada Test Site Public Involvement Plan Post-Closure Inspection and Monitoring Report for Corrective Action Unit

  5. DOE Publishes Notice of Proposed Rulemaking Regarding the Compliance Date for the Dehumidifier Test Procedure

    Broader source: Energy.gov [DOE]

    The Department of Energy has published a notice of proposed rulemaking regarding the compliance date for the dehumidifier test procedure.

  6. Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters

    Broader source: Energy.gov [DOE]

    The report assesses the localized corrosion performance of container/cask materials used in the interim storage of used nuclear fuel.

  7. DOE Publishes 20K Hour Testing Results for 2008 GATEWAY Bridge Installation

    Energy Savers [EERE]

    Department of Energy Proposes First Revision to its NEPA Rules in More than a Decade DOE Proposes First Revision to its NEPA Rules in More than a Decade December 20, 2010 - 5:22pm Addthis Today, the Department of Energy issued a Notice of Proposed Rulemaking to amend its regulations governing compliance with the National Environmental Policy Act (NEPA). The proposals focus primarily on the Department's categorical exclusion provisions, and reflect the first update to these provisions in

  8. 2010 DOE EERE Vehicle Technologies Program Merit Review - Vehicle Systems Simulation and Testing

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

    HYBRID AND VEHICLE SYSTEMS TECHNOLOGIES Vehicle and system research provides an overarching vehicle systems perspective to the technology research and development (R&D) activities of the U.S. Department of Energy's (DOE's) vehicle research programs, and identifies major opportunities for improving vehicle efficiencies. The effort evaluates and validates the integration of technologies, provides component and vehicle benchmarking, develops and validates heavy hybrid propulsion technologies,

  9. DOE/EIS-0251; Supplemental Analysis For a Container System for the Management of DOE Spent Nuclear Fuel Located at the INEEL

    Office of Environmental Management (EM)

    ID-10636 SUPPLEMENT ANALYSIS FOR A CONTAINER SYSTEM FOR THE MANAGEMENT OF DOE SPENT NUCLEAR FUEL LOCATED AT THE INEEL March 1999 U.S. Department of Energy Idaho Operations Office Idaho Falls, Idaho DOE/ID-10636 SUPPLEMENT ANALYSIS FOR A CONTAINER SYSTEM FOR THE MANAGEMENT OF DOE SPENT NUCLEAR FUEL LOCATED AT THE INEEL March 1999 Department of Energy Idaho Operations Office Idaho Falls, Idaho SNF Supplement Analysis ii March 1999 CONTENTS Acronyms and Abbreviations

  10. DOE/NV--958 U.S. DEPARTMENT OF ENERGY NEVADA TEST SITE ENVIRONMENTAL...

    National Nuclear Security Administration (NNSA)

    ... area designated for the development of a solar energy power generation facility. * ... Furthermore, in recognition of the potential end of testing in future years, the BLM ...

  11. DOE Publishes Notice of Proposed Rulemaking for Direct Heating Equipment and Pool Heater Test Procedures

    Broader source: Energy.gov [DOE]

    The Department of Energy has published a notice of proposed rulemaking regarding test procedures for direct heating equipment and pool heaters.

  12. Using NDA Techniques to Improve Safeguards Metrics on Burnup Quantification and Plutonium Content in LWR SNF

    SciTech Connect (OSTI)

    Saavedra, Steven F; Charlton, William S; Solodov, Alexander A; Ehinger, Michael H

    2010-01-01

    Globally, there exists a long history in reprocessing in evaluation of the shipper/receiver difference (SRD) on spent nuclear fuel (SNF) received and processed. Typically, the declared shipper s values for uranium and plutonium in SNF (based on calculations involving the initial manufacturer s data and reactor operating history) are used as the input quantities to the head-end process of the facility. Problems have been encountered when comparing these values with measured results of the input accountability tank contents. A typical comparison yields a systematic bias indicated as a loss of 5 7 percent of the plutonium (Pu) and approximately 1 percent for the uranium (U). Studies suggest that such deviation can be attributed to the non-linear nature of the axial burnup values of the SNF. Oak Ridge National Laboratory and Texas A&M University are co-investigating the development of a new method, via Nondestructive Assay (NDA) techniques, to improve the accuracy in burnup and Pu content quantification. Two major components have been identified to achieve this objective. The first component calculates a measurement-based burnup profile along the axis of a fuel rod. Gamma-ray data is collected at numerous locations along the axis of the fuel rod using a High Purity Germanium (HPGe) detector designed for a wide range of gamma-ray energies. Using two fission products, 137Cs and 134Cs, the burnup is calculated at each measurement location and a profile created along the axis of the rod based on the individual measurement locations. The second component measures the U/Pu ratio using an HPGe detector configured for relatively low-energy gamma-rays including x-rays. Fluorescence x-rays from U and Pu are measured and compared to the U/Pu ratio determined from a destructive analysis of the sample. This will be used to establish a relationship between the measured and actual values. This relationship will be combined with the burnup analysis results to establish a relationship

  13. Spent Nuclear Fuel project stage and store K basin SNF in canister storage building functions and requirements. Revision 1

    SciTech Connect (OSTI)

    Womack, J.C.

    1995-10-24

    This document establishes the functions and requirements baseline for the implementation of the Canister Storage Building Subproject. The mission allocated to the Canister Storage Building Subproject is to provide safe, environmentally sound staging and storage of K Basin SNF until a decision on the final disposition is reached and implemented

  14. DOE-Sponsored Project Tests Novel Method to Increase Oil Recovery

    Office of Energy Efficiency and Renewable Energy (EERE)

    Successful laboratory tests at the Energy Department’s National Energy Technology Laboratory (NETL) have verified that the use of a brine-soluble ionic surfactant could improve the efficiency of carbon dioxide enhanced oil recovery (CO2-EOR).

  15. Novel Sorbent Achieves 90 Percent Carbon Capture in DOE-Sponsored Test

    Office of Energy Efficiency and Renewable Energy (EERE)

    The successful bench-scale test of a novel carbon dioxide capturing sorbent promises to further advance the process as a possible technological option for reducing CO2 emissions from coal-fired power plants.

  16. DOE Publishes CALiPER Report on the Photometric Testing of White...

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

    The main goal of the new study was to understand the amount of testing required to characterize a white-tunable LED lighting product. In this case, determining a sufficient ...

  17. DOE Publishes CALiPER Report on the Photometric Testing of White-Tunable LED Luminaires

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy's CALiPER program has released Report 23: Photometric Testing of White-Tunable LED Luminaires, which is the first in a planned series of investigations on color...

  18. DOE-Sponsored Field Test Finds Potential for Permanent Storage of CO2 in Lignite Seams

    Broader source: Energy.gov [DOE]

    A field test sponsored by the U.S. Department of Energy has demonstrated that opportunities to permanently store carbon in unmineable seams of lignite may be more widespread than previously documented.

  19. DOE/NV EA-1300 The Nevada Test Site Development Corporation's

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

    EA-1300 The Nevada Test Site Development Corporation's Desert Rock Sky Park at the Nevada Test Site Environmental Assessment March 2000 United States Department of Energy Nevada Operations Office Las Vegas, Nevada Available for public sale, in paper, from: U.S. Department of Commerce National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Phone: (800) 553-6847 Fax: (703) 605-6900 Email: orders@ntis.fedworld.gov Online ordering: http://www.ntis.gov/ordering.htm Available

  20. DOE - Office of Legacy Management -- Naval Ordnance Test Station - CA 06

    Office of Legacy Management (LM)

    Test Station - CA 06 FUSRAP Considered Sites Site: NAVAL ORDNANCE TEST STATION (CA.06) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: China Lake Naval Weapons Center Salt Wells Pilot Plant CA.06-1 Location: Inyokern , California CA.06-1 Evaluation Year: 1987 CA.06-1 Site Operations: Naval facility; experimental development work on shape charges and quality castings on a pilot plant scale. CA.06-1 Site Disposition: Eliminated - No indication that

  1. Reversal bending fatigue test system for investigating vibration integrity of spent nuclear fuel during transportation

    SciTech Connect (OSTI)

    Wang, Jy -An; Wang, Hong; Bevard, Bruce Balkcom; Howard, Rob L.; Flanagan, Michelle E.

    2014-09-01

    Transportation packages for spent nuclear fuel (SNF) must meet safety requirements under normal and accident conditions as specified by federal regulations. During transportation, SNF experiences unique conditions and challenges to cladding integrity due to the vibrational and impact loading during road or rail shipment. Oak Ridge National Laboratory (ORNL) has been developing testing capabilities that can be used to improve the understanding of the impacts on SNF integrity due to vibration loading, especially for high burn-up SNF in normal transportation operation conditions. This information can be used to meet the nuclear industry and U.S.Nuclear Regulatory Commission needs in the area of safety and security of SNF storage and transportation operations. The ORNL developed test system can perform reversal bending fatigue testing to evaluate both the static and dynamic mechanical response of SNF rods under simulated loads. The testing apparatus is also designed to meet the challenges of hot cell operation, including remote installation and detachment of the SNF test specimen, in situ test specimen deformation measurement, and implementation of a driving system suitable for use in a hot cell. The system contains a U frame set-up equipped with uniquely designed grip rigs to protect the SNF rod sample and to ensure valid test results, and uses three specially designed linear variable differential transformers to obtain the in situ curvature measurement. A variety of surrogate test rods have been used to develop and calibrate the test system as well as in performing a series of systematic cyclic fatigue tests. The surrogate rods include stainless steel (SS) cladding, SS cladding with cast epoxy and SS cladding with alumina pellet inserts simulating fuel pellets. Testing to date has shown that the interface bonding between the SS cladding and the alumina pellets has a significant impact on the bending response of the test rods as well as their fatigue strength. The

  2. Reversal bending fatigue test system for investigating vibration integrity of spent nuclear fuel during transportation

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

    Wang, Jy -An; Wang, Hong; Bevard, Bruce Balkcom; Howard, Rob L.; Flanagan, Michelle E.

    2014-09-01

    Transportation packages for spent nuclear fuel (SNF) must meet safety requirements under normal and accident conditions as specified by federal regulations. During transportation, SNF experiences unique conditions and challenges to cladding integrity due to the vibrational and impact loading during road or rail shipment. Oak Ridge National Laboratory (ORNL) has been developing testing capabilities that can be used to improve the understanding of the impacts on SNF integrity due to vibration loading, especially for high burn-up SNF in normal transportation operation conditions. This information can be used to meet the nuclear industry and U.S.Nuclear Regulatory Commission needs in the areamore » of safety and security of SNF storage and transportation operations. The ORNL developed test system can perform reversal bending fatigue testing to evaluate both the static and dynamic mechanical response of SNF rods under simulated loads. The testing apparatus is also designed to meet the challenges of hot cell operation, including remote installation and detachment of the SNF test specimen, in situ test specimen deformation measurement, and implementation of a driving system suitable for use in a hot cell. The system contains a U frame set-up equipped with uniquely designed grip rigs to protect the SNF rod sample and to ensure valid test results, and uses three specially designed linear variable differential transformers to obtain the in situ curvature measurement. A variety of surrogate test rods have been used to develop and calibrate the test system as well as in performing a series of systematic cyclic fatigue tests. The surrogate rods include stainless steel (SS) cladding, SS cladding with cast epoxy and SS cladding with alumina pellet inserts simulating fuel pellets. Testing to date has shown that the interface bonding between the SS cladding and the alumina pellets has a significant impact on the bending response of the test rods as well as their fatigue strength

  3. DOE Spent Nuclear Fuel Information in Support of TSPA-SR

    SciTech Connect (OSTI)

    H. H. Loo

    1999-08-01

    The Department of Energy (DOE) Office of Civilian Radioactive Waste Management (RW) has started the recommendation (SR) effort to show that Yucca Mountain could be selected as the first geologic repository for spent nuclear fuel (SNF) and high-level waste. One component of the site recommendation will be a total system performance assessment (TSPA), based on the design concept and the scientific data and analysis available, describing the repository's probable behavior relative to the overall system performance standards. Thus, all the data collected from the Exploratory Studies Facilities to-date have been incorporated into the latest TSPA model. To ensure that the DOE-owned SNF continues to be acceptable for disposal in the repository, it will be included in the TSPA-SR evaluation. A number of parameters are needed in the TSPA-SR models to predict the performance of the DOE-owned SNF materials placed into the potential repository. This report documents all of the basis and/or derivation for each of these parameters. A number of properties were not readily available at the time the TSPA-SR data were requested. Thus, expert judgement and opinion were used to determine a best property value. The performance of the DOE-owned SNF will be published as part of the TSPA-SR report.

  4. Improved Tests of the Weak Nuclear Force from Beta Decay | U.S. DOE Office

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

    of Science (SC) Improved Tests of the Weak Nuclear Force from Beta Decay Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Funding Opportunities Nuclear Science Advisory Committee (NSAC) Community Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-3613 F: (301) 903-3833 E: Email Us More Information » 08.19.16 Improved Tests of the Weak Nuclear

  5. Solid Oxide Fuel Cell Successfully Powers Truck Cab and Sleeper in DOE-Sponsored Test

    Broader source: Energy.gov [DOE]

    In a test sponsored by the U.S. Department of Energy, a Delphi auxiliary power unit employing a solid oxide fuel cell (SOFC) successfully operated the electrical system and air conditioning of a Peterbilt Model 386 truck under conditions simulating idling conditions for 10 hours.

  6. DOE Targets Rural Indiana Geologic Formation for CO2 Storage Field Test

    Broader source: Energy.gov [DOE]

    A U.S. Department of Energy team of regional partners has begun injecting 8,000 tons of carbon dioxide (CO2) to evaluate the carbon storage potential and test the enhanced oil recovery (EOR) potential of the Mississippian-aged Clore Formation in Posey County, Ind.

  7. Evaluation and compilation of DOE waste package test data: Biannual report, August 1987--January 1988

    SciTech Connect (OSTI)

    Interrante, C.; Escalante, E.; Fraker, A.; Ondik, H.; Plante, E.; Ricker, R.; Ruspi, J.

    1988-08-01

    This report summarizes results of the National Bureau of Standards (NBS) evaluations on waste packages designed for containment of radioactive high-level nuclear waste (HLW). The waste package is a proposed engineered barrier that is part of a permanent repository for HLW. Metal alloys are the principal barriers within the engineered system. Since enactment of the Budget Reconciliation Act for Fiscal Year 1988, the Yucca Mountain, Nevada, site (in which tuff is the geologic medium) is the only site that will be characterized for use as high-level nuclear waste repository. During the reporting period of August 1987 to January 1988, five reviews were completed for tuff, and these were grouped into the categories: ferrous alloys, copper, groundwater chemistry, and glass. Two issues are identified for the Yucca Mountain site: the approach used to calculate corrosion rates for ferrous alloys, and crevice corrosion was observed in a copper-nickel alloy. Plutonium can form pseudo-colloids that may facilitate transport. NBS work related to the vitrification of HLW borosilicate glass at the West Valley Demonstration Project (WVDP) and the Defense Waste Processing Facility (DWPF) and activities of the DOE Materials Characterization Center (MCC) for the 6-month reporting period are also included. 27 refs., 3 figs.

  8. Evaluation and compilation of DOE waste package test data: Biannual report, February 1987--July 1987

    SciTech Connect (OSTI)

    Interrante, C.; Escalante, E.; Fraker, A.; Hall, D.; Harrison, S.; Liggett, W.; Linzer, M.; Ricker, R.; Ruspi, J.; Shull, R.

    1988-05-01

    The waste package is a proposed engineering barrier that is part of a permanent repository for HLW. Metal alloys are the principal barriers within the engineered system. Technical discussions are given for the corrosion of metals proposed for the canister, particularly carbon steels, stainless steels, and copper. The current level of understanding of several canister materials is questioned for the candidate repository in tuff. Three issues are addressed, the possibility of the stress-induced failure of Zircaloy, the possible corrosion of copper and copper alloys, and the lack of site-specific characterization data. Discussions are given on problems concerning localized corrosion and environmentally assisted cracking of AISI 1020 steel at elevated temperatures (150{degree}C). For the proposed salt site, the importance of the duration of corrosion tests and some of the conditions that may preclude prompt initiation of needed long-term testing are two issues that are discussed. 31 refs., 5 figs.

  9. Comparison of Real World Energy Consumption to Models and DOE Test Procedures

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

    Comparison of Real World Energy Consumption to Models and Department of Energy Test Procedures September 2011 i NOTICE This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government, nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness,

  10. Protons and Neutrons for Testing at LBNL | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    Protons and Neutrons for Testing at LBNL Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Applications of Nuclear Science Applications of Nuclear Science Archives Small Business Innovation Research / Small Business Technology Transfer Funding Opportunities Nuclear Science Advisory Committee (NSAC) Community Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P:

  11. Decisions Regarding Drug Testing for DOE Positions That Require Access Authorization (Security Clearances)

    Energy Savers [EERE]

    Energy 4, 2007: NETL's Robotic Pipeline Inspection Tool December 4, 2007: NETL's Robotic Pipeline Inspection Tool December 4, 2007: NETL's Robotic Pipeline Inspection Tool December 4, 2007 The Department's National Energy Technology Laboratory announces the development of a new robotic pipeline inspection tool that could revolutionize the pipeline inspection process. The wireless, self-propelled Explorer II proved its worth when it was tested in a live 8-inch distribution main pressurized at

  12. DOE SPENT NUCLEAR FUEL DISPOSAL CONTAINER

    SciTech Connect (OSTI)

    F. Habashi

    1998-06-26

    The DOE Spent Nuclear Fuel Disposal Container (SNF DC) supports the confinement and isolation of waste within the Engineered Barrier System of the Mined Geologic Disposal System (MGDS). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the access mains, and emplaced in emplacement drifts. The DOE Spent Nuclear Fuel Disposal Container provides long term confinement of DOE SNF waste, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The DOE SNF Disposal Containers provide containment of waste for a designated period of time, and limit radionuclide release thereafter. The disposal containers maintain the waste in a designated configuration, withstand maximum handling and rockfall loads, limit the individual waste canister temperatures after emplacement. The disposal containers also limit the introduction of moderator into the disposal container during the criticality control period, resist corrosion in the expected repository environment, and provide complete or limited containment of waste in the event of an accident. Multiple disposal container designs may be needed to accommodate the expected range of DOE Spent Nuclear Fuel. The disposal container will include outer and inner barrier walls and outer and inner barrier lids. Exterior labels will identify the disposal container and contents. Differing metal barriers will support the design philosophy of defense in depth. The use of materials with different failure mechanisms prevents a single mode failure from breaching the waste package. The corrosion-resistant inner barrier and inner barrier lid will be constructed of a high-nickel alloy and the corrosion-allowance outer barrier and outer barrier lid will be made of carbon steel. The DOE Spent Nuclear Fuel Disposal Containers interface with the emplacement drift environment by transferring heat from the waste to the external environment and by protecting

  13. DOE/NV--958 U.S. DEPARTMENT OF ENERGY NEVADA TEST SITE ENVIRONMENTAL MANAGEMENT

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

    958 U.S. DEPARTMENT OF ENERGY NEVADA TEST SITE ENVIRONMENTAL MANAGEMENT END STATE VISION January 2006 Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Phone: 800.553.6847 Fax: 703.605.6900 Email: orders@ntis.gov Online ordering: http://www.ntis.gov/ordering.htm Available electronically at http://www.osti.gov/bridge Available for a processing fee to U.S. Department of Energy and its contractors, in

  14. DOE/EA-2024

    National Nuclear Security Administration (NNSA)

    ... Health and Environmental Control SNF spent nuclear fuel SRS Savannah River Site TRAGIS ... Renovation activities could include removal of: lighting distribution panels ...

  15. DOE Spent Nuclear Fuel Information In Support of TSPA-VA

    SciTech Connect (OSTI)

    A. Brewer; D. Cresap; D. Fillmore; H. Loo; M. Ebner; R. McCormack

    1998-09-01

    RW has started the viability assessment (VA) effort to determine the feasibility of Yucca Mountain as the first geologic repository for spent nuclear fuel (SNF) and high-level waste. One component of the viability assessment will be a total system performance assessment (TSPA), based on the design concept and the scientific data and analysis available, describing the repository's probable behavior relative to the overall system performance standards. Thus, all the data collected from the Exploratory Studies Facility to-date have been incorporated into the latest TSPA model. In addition, the Repository Integration Program, an integrated probabilistic simulator, used in the TSPA has also been updated by Golder Associates Incorporated at December 1997. To ensure that the Department of Energy-owned (DOE-owned) SNF continues to be acceptable for disposal in the repository, it will be included in the TSPA-VA evaluation. A number of parameters are needed in the TSPA-VA models to predict the performance of the DOE-owned SNF materials placed into the potential repository. This report documents all of the basis and/or derivation for each of these parameters. A number of properties were not readily available at the time the TSPA-VA data was requested. Thus, expert judgement and opinion was utilized to determine a best property value. The performance of the DOE-owned SNF will be published as part of the TSPA-VA report. Each DOE site will be collecting better data as the DOE SNF program moves closer to repository license application. As required by the RW-0333P, the National Spent Nuclear Fuel Program will be assisting each site in qualifying the information used to support the performance assessment evaluations.

  16. Evaluation of Maxim Module-Integrated Electronics at the DOE Regional Test Centers (Presentation)

    SciTech Connect (OSTI)

    Deline, C.; Sekulic, B.; Barkaszi, S.; Yang, J.; Kahn, S.

    2014-06-01

    Module-embedded power electronics developed by Maxim Integrated are under evaluation through a partnership with the Department of Energy's Regional Test Center (RTC) program. Field deployments of both conventional modules and electronics-enhanced modules are designed to quantify the performance advantage of Maxim's products under different amounts of interrow shading, and their ability to be deployed at a greater ground-coverage ratio than conventional modules. Simulations in PVSYST have quantified the predicted performance difference between conventional modules and Maxim's modules from interrow shading. Initial performance results have identified diffuse irradiance losses at tighter row spacing for both the Maxim and conventional modules. Comparisons with published models show good agreement with models predicting the greatest diffuse irradiance losses. At tighter row spacing, all of the strings equipped with embedded power electronics outperformed their conventional peers. An even greater performance advantage is predicted to occur in the winter months when the amount of interrow shading mismatch is at a maximum.

  17. Geology Report: Area 3 Radioactive Waste Management Site DOE/Nevada Test Site, Nye County, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2006-07-01

    Surficial geologic studies near the Area 3 Radioactive Waste Management Site (RWMS) were conducted as part of a site characterization program. Studies included evaluation of the potential for future volcanism and Area 3 fault activity that could impact waste disposal operations at the Area 3 RWMS. Future volcanic activity could lead to disruption of the Area 3 RWMS. Local and regional studies of volcanic risk indicate that major changes in regional volcanic activity within the next 1,000 years are not likely. Mapped basalts of Paiute Ridge, Nye Canyon, and nearby Scarp Canyon are Miocene in age. There is a lack of evidence for post-Miocene volcanism in the subsurface of Yucca Flat, and the hazard of basaltic volcanism at the Area 3 RWMS, within the 1,000-year regulatory period, is very low and not a forseeable future event. Studies included a literature review and data analysis to evaluate unclassified published and unpublished information regarding the Area 3 and East Branch Area 3 faults mapped in Area 3 and southern Area 7. Two trenches were excavated along the Area 3 fault to search for evidence of near-surface movement prior to nuclear testing. Allostratigraphic units and fractures were mapped in Trenches ST02 and ST03. The Area 3 fault is a plane of weakness that has undergone strain resulting from stress imposed by natural events and underground nuclear testing. No major vertical displacement on the Area 3 fault since the Early Holocene, and probably since the Middle Pleistocene, can be demonstrated. The lack of major displacement within this time frame and minimal vertical extent of minor fractures suggest that waste disposal operations at the Area 3 RWMS will not be impacted substantially by the Area 3 fault, within the regulatory compliance period. A geomorphic surface map of Yucca Flat utilizes the recent geomorphology and soil characterization work done in adjacent northern Frenchman Flat. The approach taken was to adopt the map unit boundaries (line

  18.  Topic Group Reports  DOE Program Summaries

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

    Philadelphia 1999 Meeting  Topic Group Reports  DOE Program Summaries  Discussion of SNF Storage Initiatives & Transportations Issues  Discussion of WIPP Opening  Summary of Breakout Sessions The Transportation External Coordination (TEC) Working Group held its 15th semi-annual meeting July 14-15, 1999 in Philadelphia, Pennsylvania. Over 150 members, participants, and observers representing state, tribal, and local governments, regional groups, industry and professional

  19. Evaluation of Maxim Module-Integrated Electronics at the DOE Regional Test Centers: Preprint

    SciTech Connect (OSTI)

    Deline, C.; Sekulic, B.; Stein, J.; Barkaszi, S.; Yang, J.; Kahn, S.

    2014-07-01

    Module-embedded power electronics developed by Maxim Integrated are under evaluation through a partnership with the Department of Energy's Regional Test Center (RTC) program. Field deployments of both conventional modules and electronics-enhanced modules are designed to quantify the performance advantage of Maxim's products under different amounts of inter-row shading, and their ability to be deployed at a greater ground-coverage-ratio than conventional modules. Simulations in PVSYST have quantified the predicted performance difference between conventional modules and Maxim's modules from inter-row shading. Initial performance results have identified diffuse irradiance losses at tighter row spacing for both the Maxim and conventional modules. Comparisons with published models show good agreement with models predicting the greatest diffuse irradiance losses. At tighter row spacing, all of the strings equipped with embedded power electronics outperformed their conventional peers. An even greater performance advantage is predicted to occur in the winter months when the amount of inter-row shading mismatch is at a maximum.

  20. Evaluation of Codisposal Viability for Melt and Dilute DOE-Owned Fuel

    SciTech Connect (OSTI)

    H. Radulescu

    2001-07-31

    There are more than 250 forms of U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF). Due to the variety of the spent nuclear fuel, the National Spent Nuclear Fuel Program has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment (DOE 2000b, Section 6.6.8). The Melt and Dilute (MD) SNF has been designated as the representative fuel for the high-enriched U-Al fuel group. The MD SNF consists of homogeneous cylindrical ingots with 16.5 in. (419.1 mm) maximum diameter. Two general ingot compositions are considered in the criticality and geochemistry analyses. The first composition consists of 8.2 to 18.2 wt% uranium, enriched at less than 20 wt% U-235 and 0.5 wt% gadolinium, with the balance of the ingot being aluminum. The second composition is identical to the first for uranium and gadolinium, but in this case 2.5 wt% of the ingot is hafnium, with the balance of the ingot being aluminum. The results of the analyses performed will be used to develop waste acceptance criteria. The items that are important to criticality control are identified based on the analysis needs and result sensitivities. Prior to acceptance of fuel from the high-enriched U-Al fuel group for disposal, the important items for the fuel types that are being considered for disposal under the high-enriched U-Al fuel group must be demonstrated to satisfy the conditions determined in this report. The analyses have been performed by following the disposal criticality analysis methodology, which was documented in the ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2000) submitted to the U.S. Nuclear Regulatory Commission. The methodology includes analyzing the geochemical and physical processes that can breach the waste package and degrade the waste forms and other internal components, as well as the structural, thermal, and shielding analyses, and intact and degraded component criticality

  1. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    SciTech Connect (OSTI)

    BAZINET, G.D.

    2000-11-03

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. The purpose of this revision is to document completion of verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted

  2. DRAFT DOE Training Curriculum

    Energy Savers [EERE]

    (ManagersSupervisors) PHY-128DE Basic Survey Overview PHY-130 Basic Survey VAP-335 Fundamentals of Performance Testing DOE-200DE Assessment Fundamentals DOE-210 Assessment...

  3. Reversible Bending Fatigue Test System for Investigating Vibration Integrity of Spent Nuclear Fuel during Transportation

    SciTech Connect (OSTI)

    Wang, Jy-An John; Wang, Hong; Bevard, Bruce Balkcom; Howard, Rob L; Flanagan, Michelle

    2013-01-01

    Transportation packages for spent nuclear fuel (SNF) must meet safety requirements under normal and accident conditions as specified by federal regulations. During transportation, SNF experiences unique conditions and challenges to cladding integrity due to the vibrational and impact loading during road or rail shipment. Oak Ridge National Laboratory (ORNL) has been developing testing capabilities that can be used to improve the understanding of the impacts on SNF integrity due to vibration loading, especially for high burn-up SNF in normal transportation operation conditions. This information can be used to meet the nuclear industry and U.S. Nuclear Regulatory Commission needs in the area of safety and security of spent nuclear fuel storage and transport operations. The ORNL developed test system can perform reversible-bending fatigue testing to evaluate both the static and dynamic mechanical response of SNF rods under simulated loads. The testing apparatus is also designed to meet the challenges of hot-cell operation, including remote installation and detachment of the SNF test specimen, in-situ test specimen deformation measurement, and implementation of a driving system suitable for use in a hot cell. The system contains a U-frame set-up equipped with uniquely designed grip rigs, to protect SNF rod and to ensure valid test results, and use of 3 specially designed LVDTs to obtain the in-situ curvature measurement. A variety of surrogate test rods have been used to develop and calibrate the test system as well as in performing a series of systematic cyclic fatigue tests. The surrogate rods include stainless steel (SS) cladding, SS cladding with cast epoxy, and SS cladding with alumina pellets inserts simulating fuel pellets. Testing to date has shown that the interface bonding between the SS cladding and the alumina pellets has a significant impact on the bending response of the test rods as well as their fatigue strength. The failure behaviors observed from

  4. Development of a techno-economic model to optimization DOE spent nuclear fuel disposition

    SciTech Connect (OSTI)

    Ramer, R.J.; Plum, M.M.; Adams, J.P.; Dahl, C.A.

    1997-11-01

    The purpose of the National Spent Nuclear Fuel (NSNF) Program conducted by Lockheed Martin Idaho Technology Co. (LMITCO) at the Idaho National Engineering and Environmental Laboratory (INEEL) is to evaluate what to do with the spent nuclear fuel (SNF) in the Department of Energy (DOE) complex. Final disposition of the SNF may require that the fuel be treated to minimize material concerns. The treatments may range from electrometallurgical treatment and chemical dissolution to engineering controls. Treatment options and treatment locations will depend on the fuel type and the current locations of the fuel. One of the first steps associated with selecting one or more sites for treating the SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. For this study, a set of questions was developed for the electrometallurgical treatment process for fuels at several locations. The set of questions addresses all issues associated with the design, construction, and operation of a production facility. A matrix table was developed to determine questions applicable to various fuel treatment options. A work breakdown structure (WBS) was developed to identify a treatment process and costs from initial design to shipment of treatment products to final disposition. Costs will be applied to determine the life-cycle cost of each option. This technique can also be applied to other treatment techniques for treating spent nuclear fuel.

  5. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    SciTech Connect (OSTI)

    PICKETT, W.W.

    2000-09-22

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. Because this sub-project is still in the construction/start-up phase, all verification activities have not yet been performed (e.g., canister cover cap and welding fixture system verification, MCO Internal Gas Sampling equipment verification, and As-built verification.). The verification activities identified in this report that still are to be performed will be added to the start-up punchlist and tracked to closure.

  6. Spent Nuclear Fuel (SNF) project Integrated Safety Management System phase I and II Verification Review Plan

    SciTech Connect (OSTI)

    CARTER, R.P.

    1999-11-19

    The U.S. Department of Energy (DOE) commits to accomplishing its mission safely. To ensure this objective is met, DOE issued DOE P 450.4, Safety Management System Policy, and incorporated safety management into the DOE Acquisition Regulations ([DEAR] 48 CFR 970.5204-2 and 90.5204-78). Integrated Safety Management (ISM) requires contractors to integrate safety into management and work practices at all levels so that missions are achieved while protecting the public, the worker, and the environment. The contractor is required to describe the Integrated Safety Management System (ISMS) to be used to implement the safety performance objective.

  7. Evaluation and compilation of DOE [Department of Energy] waste package test data; Biannual report, February 1988--July 1988

    SciTech Connect (OSTI)

    Interrante, C.; Escalante, E.; Fraker, A.; Plante, E.

    1989-10-01

    This report summarizes evaluations by the National Institute of Standards and Technology (NIST) of Department of Energy (DOE) activities on waste packages designed for containment of radioactive high-level nuclear waste (HLW) for the six month period February 1988 through July 1988. Activities for the DOE Materials Characterization Center are reviewed for the period January 1988 through June 1988. A summary is given of the Yucca Mountain, Nevada disposal site activities. Short discussions relating to the reviewed publications are given and complete reviews and evaluations are included. 20 refs., 1 fig., 1 tab.

  8. Final Response to Comments as sent out on SNF CR M-34-04-01.doc

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

    ... We have previously questioned whether the DOE standard at 100 nCigram properly reflects the definition of transuranic waste under Federal law, which we understand to be 10 nCi...

  9. Preparation for Testing, Safe Packing and Shipping of Spent Nuclear Fuel from IFIN-HH, Bucharest-Magurele to Russian Federation

    SciTech Connect (OSTI)

    Dragolici, C.A.; Zorliu, A.; Popa, V.; Copaciu, V.; Dragusin, M.

    2007-07-01

    The Russian Research Reactor Fuel Return (RRRFR) program is promoted by IAEA and DOE in order to repatriate of irradiated research reactor fuel originally supplied by Russia to facilities outside the country. Developed under the framework of the Global Threat Reduction Initiative (GTRI) the take-back program [1] common goal is to reduce both proliferation and security risks by eliminating or consolidating inventories of high-risk material. The main objective of this program is to support the return to Russian Federation of fresh or irradiated HEU and LEU fuel. Being part of this project, Romania is fulfilling its tasks by examining transport and transfer cask options, assessment of transport routes, and providing cost estimates for required equipment and facility modifications. Spent Nuclear Fuel (SNF) testing, handling, packing and shipping are the most common interests on which the National Institute of Research and Development for Physics and Nuclear Engineering 'Horia Hulubei' (IFIN-HH) is focusing at the moment. (authors)

  10. Spent Nuclear Fuel (SNF) Project Cask and MCO Helium Purge System Design Review Completion Report Project A.5 and A.6

    SciTech Connect (OSTI)

    ARD, K.E.

    2000-04-19

    This report documents the results of the design verification performed on the Cask and Multiple Canister Over-pack (MCO) Helium Purge System. The helium purge system is part of the Spent Nuclear Fuel (SNF) Project Cask Loadout System (CLS) at 100K area. The design verification employed the ''Independent Review Method'' in accordance with Administrative Procedure (AP) EN-6-027-01.

  11. Environmental data and analyses for the proposed management of spent nuclear fuel on the DOE Oak Ridge Reservation

    SciTech Connect (OSTI)

    Socolof, M.L.; Curtis, A.H.; Blasing, T.J.

    1995-08-01

    DOE needs to continue the safe and efficient management of SNF on ORR, based on the requirement for future SNF storage capacity and implementation of the ROD for the PEIS. DOE is proposing to implement the ROD through proper management of SNF on ORR, including the possible construction and operation of a dry cask storage facility. This report describes the potentially affected environment and analyzes impacts on various resources due to the proposed action. The information provided in this report is intended to support the Environmental Assessment being prepared for the proposed activities. Construction of the dry cask storage facility would result in minimal or no impacts on groundwater, surface water, and ecological resources. Contaminated soils excavated during construction would result in negligible risk to human health and to biota. Except for noise from trucks and equipment, operation of the dry cask storage facility would not be expected to have any impact on vegetation, wildlife, or rare plants or animals. Noise impacts would be minimal. Operation exposures to the average SNF storage facility worker would not exceed approximately 0.40 mSv/year (40 mrem/year). The off-site population dose within an 80-km (50-mile) radius of ORR from SNF operations would be less than 0.052 person-Sv/year (5.2 person-rem/year). Impacts from incident-free transportation on ORR would be less than 1.36 X 10{sup -4} occupational fatal cancers and 4.28 X 10{sup -6} public fatal cancers. Credible accident scenarios that would result in the greatest probable risks would cause less than one in a million cancer fatalities to workers and the public.

  12. DOE Publishes Notice of Proposed Rulemaking for Residential Water Heater and Certain Commercial Water Heater Test Procedures

    Broader source: Energy.gov [DOE]

    The Department of Energy has published a notice of proposed rulemaking regarding test procedures for residential water heaters and certain commercial water heaters.

  13. DOE-STD-3025-99; DOE Standard Quality Assurance Inspection and...

    Office of Environmental Management (EM)

    for HEPA filter testing performed at DOE-accepted HEPA Filter Test Facilities (FTFs). ... predecessor, entitled "DOE Filter Test Facilities Quality Program Plan (NE F 3-43)". ...

  14. Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB) Procurement Specifications [SEC 1 and 2

    SciTech Connect (OSTI)

    BAZINET, G.D.

    2000-05-01

    This specification section defines the welding, brazing, thermal treatment, examination and testing requirements for carbon steel, and stainless steel piping.

  15. Geopressured-Geothermal Drilling and Testing Plan, Volume II, Testing Plan; Dow Chemical Co. - Dept. of Energy Dow-DOE Sweezy No. 1 Well, Vermilion Parish, Louisiana

    SciTech Connect (OSTI)

    1982-02-01

    The Dow/D.O.E. L. R. Sweezy No. 1 geopressured geothermal production well was completed in August of 1981. The well was perforated and gravel packed in approximately 50 feet of sand from 13,344 feet to 13,395 feet. Permeabilities of 6 to 914 millidarcies were measured with porosity of 25 to 36%. Static surface pressure after well clean-up was 5000 psi. At 1000 B/D flow rate the drawdown was 50 psi. The water produced in clean-up contained 100,000 ppm TDS. This report details the plan for testing this well with the goal of obtaining sufficient data to define the total production curve of the small, 939 acre, reservoir. A production time of six to nine months is anticipated. The salt water disposal well is expected to be completed and surface equipment installed such that production testing will begin by April 1, 1982. The program should be finished and reports written by February 28, 1983. The brine will be produced from the No.1 well, passed through a separator where the gas is removed, then reinjected into the No.2 (SWD) well under separator pressure. Flow rates of up to 25,000 B/D are expected. The tests are divided into a two-week short-term test and six to nine-month long-term tests with periodic downhole measurement of drawdown and buildup rates. Data obtained in the testing will be relayed by phoneline computer hookup to Otis Engineering in Dallas, Texas, where the reservoir calculations and modeling will be done. At the point where sufficient data has been obtained to reach the objectives of the program, production will be ended, the wells plugged and abandoned, and a final report will be issued.

  16. Steering Committee Progress Report on Hydrogen Sensor Performance Testing and Evaluation under the Memorandum of Agreement between NREL, U.S. DOE and JRC-IET, EC

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

    Steering Committee Progress Report on Hydrogen Sensor Performance Testing and Evaluation under the Memorandum of Agreement between NREL, U.S. DOE and JRC-IET, EC W. Buttner, M. Post, R. Burgess, and C. Rivkin National Renewable Energy Laboratory L. Boon-Brett, V. Palmisano, C. Bonato and F. Harskamp Joint Research Centre Institute for Energy and Transport Technical Report NREL/TP-5600-57207 December 2012 NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency

  17. Depleted uranium: A DOE management guide

    SciTech Connect (OSTI)

    1995-10-01

    The U.S. Department of Energy (DOE) has a management challenge and financial liability in the form of 50,000 cylinders containing 555,000 metric tons of depleted uranium hexafluoride (UF{sub 6}) that are stored at the gaseous diffusion plants. The annual storage and maintenance cost is approximately $10 million. This report summarizes several studies undertaken by the DOE Office of Technology Development (OTD) to evaluate options for long-term depleted uranium management. Based on studies conducted to date, the most likely use of the depleted uranium is for shielding of spent nuclear fuel (SNF) or vitrified high-level waste (HLW) containers. The alternative to finding a use for the depleted uranium is disposal as a radioactive waste. Estimated disposal costs, utilizing existing technologies, range between $3.8 and $11.3 billion, depending on factors such as applicability of the Resource Conservation and Recovery Act (RCRA) and the location of the disposal site. The cost of recycling the depleted uranium in a concrete based shielding in SNF/HLW containers, although substantial, is comparable to or less than the cost of disposal. Consequently, the case can be made that if DOE invests in developing depleted uranium shielded containers instead of disposal, a long-term solution to the UF{sub 6} problem is attained at comparable or lower cost than disposal as a waste. Two concepts for depleted uranium storage casks were considered in these studies. The first is based on standard fabrication concepts previously developed for depleted uranium metal. The second converts the UF{sub 6} to an oxide aggregate that is used in concrete to make dry storage casks.

  18. DOE Explosives Safety Manual

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

    1996-03-29

    This Manual describes DOE's explosives safety requirements applicable to operations involving the development, testing, handling, and processing of explosives or assemblies containing explosives.

  19. Sweet Lake Geopressured-geothermal Project, Magma Gulf-Technadril/DOE Amoco Fee. Volume II. Surface installations reservoir testing. Annual report, February 28, 1981-February 10, 1982

    SciTech Connect (OSTI)

    Hoffman, K.S.

    1984-01-01

    The Magma Gulf-Technadril/Department of Energy Amoco Fee No. 1 (production) and salt water disposal wells were drilled in the period from August, 1980 to February 1981. Surface facilities were designed and constructed during March-June 1981. Flow testing began in June 1981 and continued until February, 1982. The Miogypsinoides interval contains seven discrete sands in the test well. These sands have been numbered 1 to 7, beginning at the top of the sequence. Data from wireline logs and core samples suggested that the first zone to be perforated should be Sand 5. Because of its high porosity and permeability, Sand 5 was thought to contain almost 50% of the total hydraulic capacity of the well. Flow testing of Sand 5 was performed in three stages, each of which is fully described in this report. Phase I was designed as an initial clean-up flow and a reservoir confirmation test. Phase II consisted of the reservoir limit determination test and lasted 17 days. Boundaries were confirmed which suggest that the Sweet Lake reservoir is fairly narrow, with boundaries on three sides, but is open in one direction with no closure for at least 4-1/4 miles. These boundaries approximate the shape of the graben in which the test well was drilled, but may or may not be directly related to the major faults forming the graben. Phase III testing was planned to be a long-term test at commercial design rates. Although Sand 5 alone would not support such rates, long-term production was demonstrated. Additional research not supported by DOE funding was also performed during the period covered by this report. This research, consisting of mud logging, micropaleontology, organic geochemistry, core analysis, and rock mechanics, is summarized in this report.

  20. NRC Transportation Security (Part 73 SNF Update and Part 37 Category 1 and

    Office of Environmental Management (EM)

    Forecasts | Department of Energy NOAA Teams Up with Department of Energy & Industry to Improve Wind Forecasts NOAA Teams Up with Department of Energy & Industry to Improve Wind Forecasts July 2, 2014 - 3:51pm Addthis The growth of wind-generated power in the United States is creating greater demand for improved wind forecasts. To address this need, the Department of Energy is working with NOAA and industry on the Wind Forecast Improvement Project, funded and led by DOE. "Our

  1. Reversible Bending Fatigue Testing on Zry-4 Surrogate Rods

    SciTech Connect (OSTI)

    Wang, Jy-An John; Wang, Hong; Bevard, Bruce Balkcom; Howard, Rob L

    2014-01-01

    Testing high-burnup spent nuclear fuel (SNF) presents many challenges in areas such as specimen preparation, specimen installation, mechanical loading, load control, measurements, data acquisition, and specimen disposal because these tasks are complicated by the radioactivity of the test specimens. Research and comparison studies conducted at Oak Ridge National Laboratory (ORNL) resulted in a new concept in 2010 for a U-frame testing setup on which to perform hot-cell reversible bending fatigue testing. Subsequently, the three-dimensional finite element analysis and the engineering design of components were completed. In 2013 the ORNL team finalized the upgrade of the U-frame testing setup and the integration of the U-frame setup into a Bose dual linear motor test bench to develop a cyclic integrated reversible-bending fatigue tester (CIRFT). A final check was conducted on the CIRFT test system in August 2013, and the CIRFT was installed in the hot cell in September 2013 to evaluate both the static and dynamic mechanical response of SNF rods under simulated loads. The fatigue responses of Zircaloy-4 (Zry-4) cladding and the role of pellet pellet and pellet clad interactions are critical to SNF vibration integrity, but such data are not available due to the unavailability of an effective testing system. While the deployment of the developed CIRFT test system in a hot cell will provide the opportunity to generate the data, the use of a surrogate rod has proven quite effective in identifying the underlying deformation mechanism of an SNF composite rod under an equivalent loading condition. This paper presents the experimental results of using surrogate rods under CIRFT reversible cyclic loading. Specifically, monotonic and cyclic bending tests were conducted on surrogate rods made of a Zry-4 tube and alumina pellet inserts, both with and without an epoxy bond.

  2. Tribology of improved transformation-toughened ceramics-heat engine test. Final report: DOE/ORNL Ceramic Technology Project

    SciTech Connect (OSTI)

    Lilley, E.; Rossi, G.A.; Pelletier, P.J.

    1992-04-01

    A short term study has been carried out to evaluate the suitability as cam roller followers of three ceria zirconia toughened aluminas and two yttria stabilized tetragonal zirconias (YTZPs) previously enhanced in programs supported by ORNL. Norton Si{sub 3}N{sub 4} (NBD-100) was also included in this study as a reference material, because it was known from work at Northwestern University that Si{sub 3}N{sub 4} to experienced little or no wear in this application, and NBD-100 is currently a successful commercial bearing material. The tribological studies were subcontracted to the Torrington Company. They found that in cam roller follower simulated tests that there was essentially no wear after 1 hour and 5 hours of testing detectable by weighing and concluded that all of these ceramics are, therefore, candidate materials. Because of the minute amounts of wear it was not possible to identify the wear mechanism or to make any correlations with the other physical properties which were evaluated such as MOR, K{sub IC} hardness, density and grain size. Phase transformation during rolling has been of interest in the tribology of zirconia contain materials. The least stable of the ceria zirconia toughened aluminas resulted in as much as 33% monoclinic phase after testing whereas the yttria stabilized (TTZ) contained very little of this transformed phase. The results of this study show that oxide materials can now be considered as candidates for cam roller followers in heat engines.

  3. Supplement analysis for a container system for the management of DOE spent nuclear fuel located at the INEEL

    SciTech Connect (OSTI)

    1999-03-12

    The Council on Environmental Quality (CEQ) regulations for implementing the NEPA, 40 CFR 1502.9 (c), directs federal agencies to prepare a supplement to an environmental impact statement when an agency makes substantial changes in the Proposed Action that are relevant to environmental concerns, or there are significant new circumstances or information relevant to environmental concerns and bearing on the Proposed Action or impacts. When it is unclear whether a supplemental environmental impact statement is required, DOE regulations (10 CFR 1021.314) direct the preparation of a supplement analysis to assist in making that determination. This supplement analysis evaluates the impacts of employing dual-purpose canisters (DPCs) to prepare DOE SNF located at the INEEL for interim onsite storage and transport outside the State of Idaho. Impacts associated with DPC manufacturing, loading and storage of DOE-ID SNF into DPCs, transport of loaded DPCs outside Idaho, and the cumulative impacts are compared with the impacts previously analyzed in the SNF and INEL EIS and the Navy Container System EIS. This SA provides information to determine whether: (1) an existing EIS should be supplemented; (2) a new EIS should be prepared; or (3) no further NEPA documentation is required.

  4. Facility Effluent Monitoring Plan for the Spent Nuclear Fuel (SNF) Project

    SciTech Connect (OSTI)

    HUNACEK, G.S.

    2000-08-01

    A facility effluent monitoring plan is required by the US. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document was prepared using the specific guidelines identified in Westinghouse Hanford Company (WHC)-EP-0438-1, ''A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans'', and assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the third revision to the original annual report. This document is reviewed annually even if there are no operational changes, and it is updated as necessary.

  5. Advanced Test Reactor Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Lisa Harvego; Brion Bennett

    2011-11-01

    U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Advanced Test Reactor Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. U.S. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

  6. Mechanical Fatigue Testing of High Burnup Fuel for Transportation Applications

    SciTech Connect (OSTI)

    Wang, Jy-An John; Wang, Hong

    2015-05-01

    This report describes testing designed to determine the ability of high burnup (HBU) (>45 GWd/MTU) spent fuel to maintain its integrity under normal conditions of transportation. An innovative system, Cyclic Integrated Reversible-bending Fatigue Tester (CIRFT), has been developed at Oak Ridge National Laboratory (ORNL) to test and evaluate the mechanical behavior of spent nuclear fuel (SNF) under conditions relevant to storage and transportation. The CIRFT system is composed of a U-frame equipped with load cells for imposing the pure bending loads on the SNF rod test specimen and measuring the in-situ curvature of the fuel rod during bending using a set up with three linear variable differential transformers (LVDTs).

  7. Concentration of HLLW from Future SNF Recycling for Efficient Immobilization in a CCIM

    SciTech Connect (OSTI)

    Maio, Vince; Rutledge, Roni

    2015-01-01

    Sponsored by the Department of Energy Nuclear Energys Fuel Cycle Research and Development Program, the Cold Crucible Induction Melter is being developed as the next generation of melter technology for High Level Liquid Wastes efficient immobilization in highly durable glass ceramic and ceramic forms. Concentration of the radioactive High Level Liquid Waste generated from the proposed future recycling of spent nuclear fuel, after the fuels dissolution in nitric acid, is necessary to take advantage of the inherent attributes of Cold Crucible Induction Melting technology. Based on a provided range of commercial spent nuclear fuel fission product composition data and its expected High Level Liquid Waste raffinate composition data as provided in oxide form, an analysis was completed to concentrate the waste. The analysis involved using nitric acid vapor liquid equilibrium data over a range of boiling temperatures and performing spreadsheet calculations to concentrate the High Level Liquid Waste through evaporation. The calculation results will provide a concentrated nonradioactive surrogate High Level Liquid Waste melter feed recipe for testing in Idaho National Laboratorys Cold Crucible Induction Melter Pilot Plant. This testing will provide a quantifiable verification of the relatively high feed rates of Cold Crucible Induction Melters compared to those achievable with the current ceramic lined Joule Heated Melters.

  8. Evaluation of Codisposal Viability for TH/U Carbide (Fort Saint Vrain HTGR) DOE-Owned Fuel

    SciTech Connect (OSTI)

    H. radulescu

    2001-09-28

    There are more than 250 forms of US Department of Energy (DOE)-owned spent nuclear fuel (SNF). Due to the variety of the spent nuclear fuel, the National Spent Nuclear Fuel Program has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. The Fort Saint Vrain reactor (FSVR) SNF has been designated as the representative fuel for the Th/U carbide fuel group. The FSVR SNF consists of small particles (spheres of the order of 0.5-mm diameter) of thorium carbide or thorium and high-enriched uranium carbide mixture, coated with multiple, thin layers of pyrolytic carbon and silicon carbide, which serve as miniature pressure vessels to contain fission products and the U/Th carbide matrix. The coated particles are bound in a carbonized matrix, which forms fuel rods or ''compacts'' that are loaded into large hexagonal graphite prisms. The graphite prisms (or blocks) are the physical forms that are handled in reactor loading and unloading operations, and which will be loaded into the DOE standardized SNF canisters. The results of the analyses performed will be used to develop waste acceptance criteria. The items that are important to criticality control are identified based on the analysis needs and result sensitivities. Prior to acceptance to fuel from the Th/U carbide fuel group for disposal, the important items for the fuel types that are being considered for disposal under the Th/U carbide fuel group must be demonstrated to satisfy the conditions determined in this report.

  9. DOE/LM-1469

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

    DOE/LM-1469

  10. Proceedings of the 22nd Annual DoD/DOE Seismic Research Symposium: Planning for Verification of and Compliance with the Comprehensive Nuclear-Test-Ban Treaty (CTBT)

    SciTech Connect (OSTI)

    Nichols, James W., LTC

    2000-09-15

    These proceedings contain papers prepared for the 22nd Annual DoD/DOE Seismic Research Symposium: Planning for Verification of and Compliance with the Comprehensive Nuclear-Test-Ban Treaty (CTBT), held 13-15 September 2000 in New Orleans, Louisiana. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Technical Applications Center (AFTAC), Department of Defense (DoD), US Army Space and Missile Defense Command, Defense Special Weapons Agency (DSWA), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.