National Library of Energy BETA

Sample records for operation date shutdown

  1. Shutdown of Departmental Operations Upon Failure by Congress to Enact Appropriations

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

    1992-05-18

    To establish the procedure for the orderly shutdown of Department of Energy (DOE) operations in the absence of needed appropriations during a fiscal year. Cancels DOE 5500.6A. Canceled by DOE O 137.1 dated 9-4-98.

  2. Shutdown and low-power operation at commercial nuclear power plants in the United States. Final report

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

    The report contains the results of the NRC Staff`s evaluation of shutdown and low-power operations at US commercial nuclear power plants. The report describes studies conducted by the staff in the following areas: Operating experience related to shutdown and low-power operations, probabilistic risk assessment of shutdown and low-power conditions and utility programs for planning and conducting activities during periods the plant is shut down. The report also documents evaluations of a number of technical issues regarding shutdown and low-power operations performed by the staff, including the principal findings and conclusions. Potential new regulatory requirements are discussed, as well as potential changes in NRC programs. A draft report was issued for comment in February 1992. This report is the final version and includes the responses to the comments along with the staff regulatory analysis of potential new requirements.

  3. Control of radio-iodine at the German reprocessing plant WAK during operation and after shutdown

    SciTech Connect (OSTI)

    Herrmann, F.J.; Herrmann, B.; Kuhn, K.D.

    1997-08-01

    During 20 years of operation 207 metric tons of oxide fuel from nuclear power reactors with 19 kg of iodine-129 had been reprocessed in the WAK plant near Karlsruhe. In January 1991 the WAK Plant was shut down. During operation iodine releases of the plant as well as the iodine distribution over the liquid and gaseous process streams had been determined. Most of the iodine is evolved into the dissolver off-gas in volatile form. The remainder is dispersed over many aqueous, organic and especially gaseous process and waste streams. After shut down of the plant in January 1991, iodine measurements in the off-gas streams have been continued up to now. Whereas the iodine-129 concentration in the dissolver off-gas dropped during six months after shutdown by three orders of magnitude, the iodine concentrations in the vessel ventilation system of the PUREX process and the cell vent system decreased only by a factor of 10 during the same period. Iodine-129 releases of the liquid high active waste storage tanks did not decrease distinctly. The removal efficiencies of the silver impregnated iodine filters in the different off-gas streams of the WAK plant depend on the iodine concentration in the off-gas. The reason of the observed dependence of the DF on the iodine-129 concentration might be due to the presence of organic iodine compounds which are difficult to remove. 13 refs., 3 figs.

  4. Fermilab | Tevatron | Shutdown Process

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

    The Shutdown Process Fermilab's Accelerator Chain The Tevatron and Fermilab's other accelerators are operated from the Main Control Room. Prior to its shutdown on Sept. 30, 2011, accelerator operators at Fermilab created particle collisions by sending beams of protons and antiprotons in opposite directions through the Tevatron ring. These beams created collisions at the centers of the CDF and DZero particle detectors. Every 10 hours or so, operators discarded the remainder of the particles

  5. Shutdown 2013

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

    three superbend magnets (and one spare) need to be replaced every 18 months or so, a factor that must be considered when setting the ALS shutdown schedule. These "cold heads"...

  6. Date

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

    Template Revised: 6/12/2014 Template Reviewed: 6/12/2014 Operated for the U.S. Department of Energy by Sandia Corporation P.O. Box 5800 MS-1461 Albuquerque, New Mexico 87185-1461 Date Contractor Name Address Attention: Based on our earlier discussions, the Contract Audit Department at Sandia Corporation, which operates Sandia National Laboratories (Sandia) will audit costs incurred through your fiscal year ending XXXXXX on the following contracts placed with your company: Contract(s) Type of

  7. Confirmation of shutdown cooling effects

    SciTech Connect (OSTI)

    Sato, Kotaro Tabuchi, Masato; Sugimura, Naoki; Tatsumi, Masahiro

    2015-12-31

    After the Fukushima accidents, all nuclear power plants in Japan have gradually stopped their operations and have long periods of shutdown. During those periods, reactivity of fuels continues to change significantly especially for high-burnup UO{sub 2} fuels and MOX fuels due to radioactive decays. It is necessary to consider these isotopic changes precisely, to predict neutronics characteristics accurately. In this paper, shutdown cooling (SDC) effects of UO{sub 2} and MOX fuels that have unusual operation histories are confirmed by the advanced lattice code, AEGIS. The calculation results show that the effects need to be considered even after nuclear power plants come back to normal operation.

  8. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal events during mid-loop operations, Appendices E (Sections E.1--E.8). Volume 2, Part 3A

    SciTech Connect (OSTI)

    Chu, T.L.; Musicki, Z.; Kohut, P.

    1994-06-01

    During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this report is to document the approach utilized in the Surry plant and discuss the results obtained. A parallel report for the Grand Gulf plant is prepared by SNL. This study shows that the core-damage frequency during mid-loop operation at the Surry plant is comparable to that of power operation. The authors recognize that there is very large uncertainty in the human error probabilities in this study. This study identified that only a few procedures are available for mitigating accidents that may occur during shutdown. Procedures written specifically for shutdown accidents would be useful.

  9. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal events during mid-loop operations, Appendices A--D. Volume 2, Part 2

    SciTech Connect (OSTI)

    Chu, T.L.; Musicki, Z.; Kohut, P.

    1994-06-01

    During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the Potential risks during low Power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the Plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this report is to document the approach utilized in the Surry plant and discuss the results obtained. A parallel report for the Grand Gulf plant is prepared by SNL. This study shows that the core-damage frequency during mid-loop operation at the Surry plant is comparable to that of power operation. We recognize that there is very large uncertainty in the human error probabilities in this study. This study identified that only a few procedures are available for mitigating accidents that may occur during shutdown. Procedures written specifically for shutdown accidents would be useful. This document, Volume 2, Pt. 2 provides appendices A through D of this report.

  10. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Evaluation of severe accident risks for plant operational state 5 during a refueling outage. Main report and appendices, Volume 6, Part 1

    SciTech Connect (OSTI)

    Brown, T.D.; Kmetyk, L.N.; Whitehead, D.; Miller, L.; Forester, J.; Johnson, J.

    1995-03-01

    Traditionally, probabilistic risk assessments (PRAS) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Recent studies and operational experience have, however, implied that accidents during low power and shutdown could be significant contributors to risk. In response to this concern, in 1989 the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The program consists of two parallel projects being performed by Brookhaven National Laboratory (Surry) and Sandia National Laboratories (Grand Gulf). The program objectives include assessing the risks of severe accidents initiated during plant operational states other than full power operation and comparing the estimated risks with the risk associated with accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program is that of a Level-3 PRA. The subject of this report is the PRA of the Grand Gulf Nuclear Station, Unit 1. The Grand Gulf plant utilizes a 3833 MWt BUR-6 boiling water reactor housed in a Mark III containment. The Grand Gulf plant is located near Port Gibson, Mississippi. The regime of shutdown analyzed in this study was plant operational state (POS) 5 during a refueling outage, which is approximately Cold Shutdown as defined by Grand Gulf Technical Specifications. The entire PRA of POS 5 is documented in a multi-volume NUREG report (NUREG/CR-6143). The internal events accident sequence analysis (Level 1) is documented in Volume 2. The Level 1 internal fire and internal flood analyses are documented in Vols 3 and 4, respectively.

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

    SciTech Connect (OSTI)

    Whitehead, D.W.; Staple, B.D.; Daniel, S.L.

    1995-07-01

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

  12. EMERGENCY SHUTDOWN FOR NUCLEAR REACTORS

    DOE Patents [OSTI]

    Paget, J.A.; Koutz, S.L.; Stone, R.S.; Stewart, H.B.

    1963-12-24

    An emergency shutdown or scram apparatus for use in a nuclear reactor that includes a neutron absorber suspended from a temperature responsive substance that is selected to fail at a preselected temperature in excess of the normal reactor operating temperature, whereby the neutron absorber is released and allowed to fall under gravity to a preselected position within the reactor core is presented. (AEC)

  13. DATE:

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

    POLICY FLASH 2013-45 DATE: April 16, 2013 TO: Procurement Directors FROM: Director Contract and Financial Assistance Policy Division Office of Policy Office of Acquisition and ...

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

    61 DATE: June 19, 2013 TO: Procurement Directors FROM: Director Policy Division Office of Procurement and Assistance Policy Office of Acquisition and Project Management SUBJECT: ...

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

    5 DATE: April 10, 2014 TO: Procurement Directors FROM: Director Contract and Financial Assistance Policy Division Office of Policy Office of Acquisition and Project Management ...

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

    1 DATE: March 10, 2014 TO: Procurement Directors FROM: Director Contract and Financial Assistance Policy Division Office of Policy Office of Acquisition and Project Management ...

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

    3-12 DATE: December 7, 2012 TO: Procurement Directors FROM: Director Contract and Financial Assistance Policy Division Office of Policy Office of Acquisition and Project Management ...

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

    4-35 DATE: July 09, 2014 TO: Procurement Directors FROM: Director Contract and Financial Assistance Policy Division Office of Policy Office of Acquisition and Project Management ...

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

    36 DATE: April 23, 2012 TO: Procurement Directors FROM: Director, Policy Division Office of Procurement and Assistance Policy Office of Procurement and Assistance Management...

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

    DATE: February 1, 2012 TO: Procurement Directors FROM: Director, Office of Procurement and Assistance Policy Office of Procurement and Assistance Management SUBJECT: Acquisition...

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

    38 DATE: May 03, 2012 TO: Procurement Directors FROM: Director, Contract and Financial Assistance Policy Division Office of Policy Office of Procurement and Assistance Management...

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    Office of Legacy Management (LM)

    -RL5- DATE: September 13, 1990 TO: Alexander Williams (w 39 fusrap6 I FROM: Ed Mitchellzm SUBJECT: Elimination Recommendation for American Machine and Foundry in New York City The...

  3. DATE:

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

    0 By Julia Raymer at 7:58 am, Nov 05, 2013 Nov 05, 2013 DATE: of 1 RPP-RPT-54981, Revision 0 i Table of Contents 1. Summary .................................................................................................................................. 1 2. Introduction ............................................................................................................................. 3 3. Discussion

  4. Fuel cell system logic for differentiating between rapid and normal shutdown commands

    DOE Patents [OSTI]

    Keskula, Donald H.; Doan, Tien M.; Clingerman, Bruce J.

    2000-01-01

    A method of controlling the operation of a fuel cell system wherein each shutdown command for the system is subjected to decision logic which determines whether the command should be a normal shutdown command or rapid shutdown command. If the logic determines that the shutdown command should be a normal shutdown command, then the system is shutdown in a normal step-by-step process in which the hydrogen stream is consumed within the system. If the logic determines that the shutdown command should be a rapid shutdown command, the hydrogen stream is removed from the system either by dumping to atmosphere or routing to storage.

  5. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit-1: Analysis of core damage frequency from internal events during mid-loop operations. Appendix I, Volume 2, Part 5

    SciTech Connect (OSTI)

    Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J.; Bley, D.; Johnson, D.; Holmes, B.

    1994-06-01

    Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Lab. (BNL) and Sandia National Labs. (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this volume of the report is to document the approach utilized in the level-1 internal events PRA for the Surry plant, and discuss the results obtained. A phased approach was used in the level-1 program. In phase 1, which was completed in Fall 1991, a coarse screening analysis examining accidents initiated by internal events (including internal fire and flood) was performed for all plant operational states (POSs). The objective of the phase 1 study was to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenarios, and to provide a foundation for a detailed phase 2 analysis.

  6. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Volume 5: Analysis of core damage frequency from seismic events for plant operational state 5 during a refueling outage

    SciTech Connect (OSTI)

    Budnitz, R.J.; Davis, P.R.; Ravindra, M.K.; Tong, W.H.

    1994-08-01

    In 1989 the US Nuclear Regulatory Commission (NRC) initiated an extensive program to examine carefully the potential risks during low-power and shutdown operations. The program included two parallel projects, one at Sandia National Laboratories studying a boiling water reactor (Grand Gulf), and the other at Brookhaven National Laboratory studying a pressurized water reactor (Surry Unit 1). Both the Sandia and Brookhaven projects have examined only accidents initiated by internal plant faults---so-called ``internal initiators.`` This project, which has explored the likelihood of seismic-initiated core damage accidents during refueling outage conditions, is complementary to the internal-initiator analyses at Brookhaven and Sandia. This report covers the seismic analysis at Grand Gulf. All of the many systems modeling assumptions, component non-seismic failure rates, and human effort rates that were used in the internal-initiator study at Grand Gulf have been adopted here, so that the results of the study can be as comparable as possible. Both the Sandia study and this study examine only one shutdown plant operating state (POS) at Grand Gulf, namely POS 5 representing cold shutdown during a refueling outage. This analysis has been limited to work analogous to a level-1 seismic PRA, in which estimates have been developed for the core-damage frequency from seismic events during POS 5. The results of the analysis are that the core-damage frequency for earthquake-initiated accidents during refueling outages in POS 5 is found to be quite low in absolute terms, less than 10{sup {minus}7}/year.

  7. Evaluation of potential severe accidents during low power and shutdown operations at Surry: Unit 1, Volume 1

    SciTech Connect (OSTI)

    Chu, T.L.; Pratt, W.T.; Musicki, Z.

    1995-10-01

    This document contains a summarization of the results and insights from the Level 1 accident sequence analyses of internally initiated events, internally initiated fire and flood events, seismically initiated events, and the Level 2/3 risk analysis of internally initiated events (excluding fire and flood) for Surry, Unit 1. The analysis was confined to mid-loop operation, which can occur during three plant operational states (identified as POSs R6 and R10 during a refueling outage, and POS D6 during drained maintenance). The report summarizes the Level 1 information contained in Volumes 2--5 and the Level 2/3 information contained in Volume 6 of NUREG/CR-6144.

  8. Dated:

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

    cause appearing, IT IS HEREBY ORDERED: 1. The Schedule Scheduling Order is stayed pending execution of a settlement agreement and stipulated final order. Dated: ~ /,/ .,2015 Christopher T. Saucedo Hearing Officer 3 Complainant, v. UNITED STATES DEPARTMENT OF ENERGY, and NUCLEAR WASTE PARTNERSHIP, LLC, Respondents. No. HWB 14-21 (CO) CERTIFICATE OF SERVICE I hereby certify that a copy of the STIPULATED JOINT MOTION TO STAY THE SCHEDULING ORDER has been sent electronically to the following on May

  9. DATE

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

    2011 Buildings Energy Data Book March 2012 Prepared for the Buildings Technologies Program Energy Efficiency and Renewable Energy U.S. Department of Energy by D&R International, Ltd. under contract to Pacific Northwest National Laboratory This version is dated: March 2012 This document was designed for the internal use of the United States Department of Energy. This document will be occasionally updated and, therefore, this copy may not reflect the most current version. This document was

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    Office of Environmental Management (EM)

    2-22 DATE: February 1, 2012 TO: Procurement Directors FROM: Director, Office of Procurement and Assistance Policy Office of Procurement and Assistance Management SUBJECT: Acquisition Letter AL 2012-07/Financial Acquisition Letter FAL 2012-01 Congressional Notification of Pending Award of a Contract Action, Announcement of Selected Applications for Negotiation of Financial Assistance Awards, or to Award a Financial Assistance Action in Excess of $1 Million SUMMARY: AL 2012-07/FAL 2012-01 (AL/FAL)

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    Office of Environmental Management (EM)

    3-45 DATE: April 16, 2013 TO: Procurement Directors FROM: Director Contract and Financial Assistance Policy Division Office of Policy Office of Acquisition and Project Management SUBJECT: DOE Acquisition Guide Chapter 15.1 Source Selection Guide SUMMARY: Attached is a revised Source Selection Guide. The Guide has been updated to reflect changes to DOE policies and practices and includes new topics such as Flow of the Source Selection Process, Source Selection Official Designation,

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

    POLICY FLASH 2014-35 DATE: July 09, 2014 TO: Procurement Directors FROM: Director Contract and Financial Assistance Policy Division Office of Policy Office of Acquisition and Project Management SUBJECT: Rescission of American Recovery and Reinvestment Act Reporting Requirements. SUMMARY: Financial Assistance Letter (FAL) 2014-xx provides COs with: 1) notice of the recession of the reporting requirements for recipients of ARRA funds in accordance with the recently passed P.L. 113- 76,

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    Office of Legacy Management (LM)

    DATE: AUG 12 1991 REPLY TO ATTN OF: EM-421 (J. Wagoner, 3-8147) SUBIECT: Elimination of the Duriron Company Site TO: The File I have reviewed the attached site summary and elimination recommendation for the Duriron Company Site in Dayton, Ohio. I have determined that there is little likelihood of radioactive contamination at this site. Based on the above, the Ouriron Company Site is hereby eliminated from further consideration under the Formerly Utilized Sites Remedial Action Program. W.

  14. Shutdown 2013 Update

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

    three superbend magnets (and one spare) need to be replaced every 18 months or so, a factor that must be considered when setting the ALS shutdown schedule. These "cold heads"...

  15. DATE

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

    Standards and Corrective Action Requirements for Owners and Operators of Underground Storage Tanks"). These actions do not include rebuilding or modifying substantial portions of...

  16. DATE

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

    12 SECTION A. Project Title: Reactor Power Up Rate, Compressor Replacement, Neutron ... compressor to improve reliability of the reactor operation and purchase a liquid ...

  17. DATE

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

    References: B1.31 Installation or relocation and operation of machinery and equipment (including, but not limited to, laboratory equipment, electronic hardware, manufacturing ...

  18. DATE

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

    ... References: B1.31 Installation or relocation and operation of machinery and equipment (including, but not limited to, laboratory equipment, electronic hardware, manufacturing ...

  19. DATE:

    Office of Legacy Management (LM)

    -RL5- DATE: September 13, 1990 TO: Alexander Williams (w 39 fusrap6 I FROM: Ed Mitchellzm SUBJECT: Elimination Recommendation for American Machine and Foundry in New York City The purpose of this note is to provide the following with respect to the former American Machine and Foundry Company (AMF) in New York City, New York--FUSRAP Considered Site Recommendation (g/13/90). 1 he recommendation is to eliminate the AMF New York City sites. If you agree, then please return an "approved"

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    Office of Legacy Management (LM)

    OOE F 1325.3 m e m o randum DATE: SEP 23 1988 Department of Energy IL_. 9 REPLY TO AlTN OF, NE-23 SUElJECT. Owner Searches for Potential Sites in Chicago IL, (7 TO: W . Cottrell, ORNL 0. Kozlouski, OTS W h ile in Chicago, Illinois, on September 13, 14, and 15, 1988, I drove to the suspected addresses of several potential FUSRAP sites. No owners were contacted during this activity because most of the work was done after normal working hours or while on the way to the airport when tim e would not

  1. DATE:

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

    x JDA 1/31/13 Jan 31, 2013 DATE: 01/31/2013 x Aardal, Janis D Y-Public, See below. Approved for Public Release; Further Dissemination Unlimited By Janis D. Aardal at 1:25 pm, Jan 31, 2013 DOE/RL-2001-41 Revision 6 SITEWIDE INSTITUTIONAL CONTROLS PLAN FOR HANFORD CERCLA RESPONSE ACTIONS AND RCRA CORRECTIVE ACTIONS Prepared for the U.S. Department of Energy Assistant Secretary for Environmental Management P.O. Box 550 Richland, Washington 99352 Approved for Public Release; Further Dissemination

  2. DATE

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

    ... requirements in PRD-5030, the generators can be operated up to 12 months or less, regardless of size, at the project location without being subject to air permitting requirements. ...

  3. DATE

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

    3 SECTION A. Project Title: Development and Integration of Light Water Reactor (LWR) Materials Corrosion Degradation Codes into Grizzly - University of California at Berkeley SECTION B. Project Description The University of California, Berkeley proposes to develop deterministic, physico chemical models for predicting the accumulation of localized corrosion damage in the primary coolant circuits of the currently operating fleet of light water reactors. The successful modeling of the accumulation

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

    28 SECTION A. Project Title: Localized Imaging, Surveying and Mapping for Nuclearized Underwater Robots - Carnegie Mellon University SECTION B. Project Description Carnegie Mellon University proposes to develop, demonstrate, and infuse a leap of sensing, robotics, spatial positioning and visualization capability into underwater nuclear operations relevant to DOE environmental management. The program will develop and demonstrate a prototype robotic system to maneuver in a water-filled basin,

  5. DATE

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

    4 SECTION A. Project Title: Wireless Reactor Power Distribution Measurement System Utilizing an In-Core Radiation and Temperature Tolerant Wireless Transmitter and a Gamma-Harvesting Power Supply - Westinghouse Electric Company SECTION B. Project Description Westinghouse Electric Company, in collaboration with the Pennsylvania State, proposes to design, manufacture, and operate a vacuum micro-electronic- (VME) based wireless transmitter that continuously broadcasts vanadium self-powered neutron

  6. DATE

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

    0 SECTION A. Project Title: High Temperature Tribological Performance of Ni Alloys Under Helium Environment for Very High Temperature Gas Cooled Reactors (VHTRs) [RC-2.3] Helium Tribology for HTGRs - Texas A&M University SECTION B. Project Description Texas A&M University proposes to systematically evaluate the tribological response of 800H and 617 alloys at relevant reactor operating temperatures (700 o -950 o C) and in the presence of helium coolant. To achieve this objective, the

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

    8 SECTION A. Project Title: Mechanistic Understanding of Silver Sorbent Aging Processes in Off-Gas Treatment - Syracuse University SECTION B. Project Description Syracuse University proposes to develop an understanding of the different mechanisms of silver-aging processes on adsorbents exposed to off-gas streams to enable prediction of long-term operation of gas treatment systems. Experiments to be conducted on silver-exchanged mordenite (Ag0Z) and silver-functionalized silica aerogel

  8. DATE

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

    0 SECTION A. Project Title: Alloying Agents to Stabilize Lanthanides Against Fuel Cladding Chemical Interaction: Tellurium and Antimony Studies - Ohio State University SECTION B. Project Description Ohio State University proposes to develop new minor additives which can form high-temperature stabilizing compounds with lanthanide fission products during operation. The proposed additives are expected to have the capability of immobilizing lanthanide fission products and preventing their transport

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

    4-001 SECTION A. Project Title: INL - Idaho Completion Project Environmental and Regulatory Services Activities SECTION B. Project Description The proposed action addresses the site-wide sampling and monitoring and waste characterization sampling programs that support the Idaho Completion Project (ICP) operations. Actions include:  groundwater monitoring,  day-to-day monitoring activities (i.e., measurement of liquid or gaseous effluents for purposes of characterizing and quantifying

  10. DATE

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

    4 SECTION A. Project Title: Materials and Fuels Complex (MFC) Infrastructure Upgrades - Technical Support Building SECTION B. Project Description: Materials and Fuels Complex (MFC) Infrastructure Upgrades - General The number of researchers and operators at the Materials and Fuels Complex has significantly increased, and is projected to increase further in the future to support the expanding research activities at the facility. These activities will require infrastructure upgrades (office space,

  11. DATE

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

    5 SECTION A. Project Title: Materials and Fuel Complex (MFC) Infrastructure Upgrades: Modular Office Units SECTION B. Project Description: MFC Infrastructure Upgrades - General The number of researchers and operators at MFC has significantly increased, and is projected to increase further in the future to support the expanding research activities at the facility. These activities will require Infrastructure upgrades (office space, potable water, wastewater treatment, communications, etc.) to

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

    DOE-ID-ICP-16-001 R1 SECTION A. Project Title: INTEC - Macroencapsulation/Overpack Operations in CPP-659 and CPP-1617, Rev. 1 SECTION B. Project Description The proposed action will treat mixed low-level waste (MLLW) at the Idaho Nuclear Technology and Engineering Center (INTEC). The treatment process, macroencapsulation, will result in the waste stream meeting the treatment standards for debris and radioactive lead solids (RLS) for disposition at the Nevada National Security Site (NNSS). The

  13. DATE

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

    4 SECTION A. Project Title: Integral System Testing for Prismatic Block Core Design HTGR - Oregon State University SECTION B. Project Description Oregon State University proposes to complete eight integral thermal-fluid tests investigating a range of gas reactor events. This is planned as a two-year project and will be conducted in a gas-reactor thermal-fluid facility that is already in operation. The overall objective of the test program will be to collect data that will fully cover the

  14. DATE

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

    1 SECTION A. Project Title: Tribal DOE Program/Agreement-In-Principle - Shoshone-Bannock Tribes SECTION B. Project Description The Tribal DOE Program will continue to operate under the Cooperative Agreement No. DE-NE000587, which was negotiated between the Fort Hall Business Council and the Department of Energy-Idaho Office on December 18, 2012 for a 5-year period under the Agreement-In-Principle (AIP). The Tribal DOE AIP Program mission for FY2016 involves oversight and monitoring of DOE

  15. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Evaluation of severe accident risks for plant operational state 5 during a refueling outage. Supporting MELCOR calculations, Volume 6, Part 2

    SciTech Connect (OSTI)

    Kmetyk, L.N.; Brown, T.D.

    1995-03-01

    To gain a better understanding of the risk significance of low power and shutdown modes of operation, the Office of Nuclear Regulatory Research at the NRC established programs to investigate the likelihood and severity of postulated accidents that could occur during low power and shutdown (LP&S) modes of operation at commercial nuclear power plants. To investigate the likelihood of severe core damage accidents during off power conditions, probabilistic risk assessments (PRAs) were performed for two nuclear plants: Unit 1 of the Grand Gulf Nuclear Station, which is a BWR-6 Mark III boiling water reactor (BWR), and Unit 1 of the Surry Power Station, which is a three-loop, subatmospheric, pressurized water reactor (PWR). The analysis of the BWR was conducted at Sandia National Laboratories while the analysis of the PWR was performed at Brookhaven National Laboratory. This multi-volume report presents and discusses the results of the BWR analysis. The subject of this part presents the deterministic code calculations, performed with the MELCOR code, that were used to support the development and quantification of the PRA models. The background for the work documented in this report is summarized, including how deterministic codes are used in PRAS, why the MELCOR code is used, what the capabilities and features of MELCOR are, and how the code has been used by others in the past. Brief descriptions of the Grand Gulf plant and its configuration during LP&S operation and of the MELCOR input model developed for the Grand Gulf plant in its LP&S configuration are given.

  16. Safety shutdown separators

    DOE Patents [OSTI]

    Carlson, Steven Allen; Anakor, Ifenna Kingsley; Farrell, Greg Robert

    2015-06-30

    The present invention pertains to electrochemical cells which comprise (a) an anode; (b) a cathode; (c) a solid porous separator, such as a polyolefin, xerogel, or inorganic oxide separator; and (d) a nonaqueous electrolyte, wherein the separator comprises a porous membrane having a microporous coating comprising polymer particles which have not coalesced to form a continuous film. This microporous coating on the separator acts as a safety shutdown layer that rapidly increases the internal resistivity and shuts the cell down upon heating to an elevated temperature, such as 110.degree. C. Also provided are methods for increasing the safety of an electrochemical cell by utilizing such separators with a safety shutdown layer.

  17. Shutdown Energizes CAMD

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

    “Shut-down” Energizes CAMD The Center for Advanced Microstructures and Devices (CAMD) undertook a period of extended shutdown of its storage-ring from January 22 to February 26, 2007 for repair and installation of equipment. A shutdown had been planned to begin the end of February to install a new dipole chamber to increase the radiation flux to the CAMD infrared beamline; however, during the Christmas break, it was discovered that the vacuum chamber that insulates the liquid helium and

  18. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit-1: Analysis of core damage frequency from internal events during mid-loop operations. Appendices F-H, Volume 2, Part 4

    SciTech Connect (OSTI)

    Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J.; Bley, D.; Johnson, D.; Holmes, B.

    1994-06-01

    Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The scope of the level-1 study includes plant damage state analysis, and uncertainty analysis. Volume 1 summarizes the results of the study. Internal events analysis is documented in Volume 2. It also contains an appendix that documents the part of the phase 1 study that has to do with POSs other than mid-loop operation. Internal fire and internal flood analyses are documented in Volumes 3 and 4. A separate study on seismic analysis, documented in Volume 5, was performed for the NRC by Future Resources Associates, Inc. Volume 6 documents the accident progression, source terms, and consequence analysis.

  19. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Evaluation of severe accident risk during mid-loop operations. Main report. Volume 6. Part 1

    SciTech Connect (OSTI)

    Jo, J.; Lin, C.C.; Neymotin, L.

    1995-05-01

    During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. A phased approach was used in the level-1 program. In phase 1 which was completed in Fall 1991, a coarse screening analysis including internal fire and flood was performed for all plant operational states (POSs). The objective of the phase 1 study was to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenarios, and to provide a foundation for a detailed phase 2 analysis. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The results of the phase 2 level 2/3 study are the subject of this volume of NUREG/CR-6144, Volume 6.

  20. PRELIMINARY Run Shutdown BL Commissioning

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

    PRELIMINARY Run Shutdown BL Commissioning Maintenance AP SPEAR Down Injector Startup University Holidays Spear Down SPEAR Startup MA Sep Oct 2011 2012 MA Mar Apr May Jun Jul...

  1. Controlled shutdown of a fuel cell

    DOE Patents [OSTI]

    Clingerman, Bruce J.; Keskula, Donald H.

    2002-01-01

    A method is provided for the shutdown of a fuel cell system to relieve system overpressure while maintaining air compressor operation, and corresponding vent valving and control arrangement. The method and venting arrangement are employed in a fuel cell system, for instance a vehicle propulsion system, comprising, in fluid communication, an air compressor having an outlet for providing air to the system, a combustor operative to provide combustor exhaust to the fuel processor.

  2. Nuclear reactor shutdown system

    DOE Patents [OSTI]

    Bhate, Suresh K.; Cooper, Martin H.; Riffe, Delmar R.; Kinney, Calvin L.

    1981-01-01

    An inherent shutdown system for a nuclear reactor having neutron absorbing rods affixed to an armature which is held in an upper position by a magnetic flux flowing through a Curie temperature material. The Curie temperature material is fixedly positioned about the exterior of an inner duct in an annular region through which reactor coolant flows. Elongated fuel rods extending from within the core upwardly toward the Curie temperature material are preferably disposed within the annular region. Upon abnormal conditions which result in high neutron flux and coolant temperature, the Curie material loses its magnetic permeability, breaking the magnetic flux path and allowing the armature and absorber rods to drop into the core, thus shutting down the fissioning reaction. The armature and absorber rods are retrieved by lowering the housing for the electromagnet forming coils which create a magnetic flux path which includes the inner duct wall. The coil housing then is raised, resetting the armature.

  3. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Volume 2, Part 1C: Analysis of core damage frequency from internal events for plant operational State 5 during a refueling outage, Main report (Sections 11--14)

    SciTech Connect (OSTI)

    Whitehead, D.; Darby, J.; Yakle, J.

    1994-06-01

    This document contains the accident sequence analysis of internally initiated events for Grand Gulf, Unit 1 as it operates in the Low Power and Shutdown Plant Operational State 5 during a refueling outage. The report documents the methodology used during the analysis, describes the results from the application of the methodology, and compares the results with the results from two full power analyses performed on Grand Gulf.

  4. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    SciTech Connect (OSTI)

    Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul E.

    2013-09-30

    This report fulfills the M2 milestone M2FT-13PN0912022, “Stranded Sites De-Inventorying Report.” In January 2013, the U.S. Department of Energy (DOE) issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (DOE 2013). Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America’s Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses (BRC 2012). Shutdown sites are defined as those commercial nuclear power reactor sites where the nuclear power reactors have been shut down and the site has been decommissioned or is undergoing decommissioning. In this report, a preliminary evaluation of removing used nuclear fuel from 12 shutdown sites was conducted. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. These sites have no other operating nuclear power reactors at their sites and have also notified the U.S. Nuclear Regulatory Commission that their reactors have permanently ceased power operations and that nuclear fuel has been permanently removed from their reactor vessels. Shutdown reactors at sites having other operating reactors are not included in this evaluation.

  5. Fuel cell system shutdown with anode pressure control

    DOE Patents [OSTI]

    Clingerman, Bruce J.; Doan, Tien M.; Keskula, Donald H.

    2002-01-01

    A venting methodology and pressure sensing and vent valving arrangement for monitoring anode bypass valve operating during the normal shutdown of a fuel cell apparatus of the type used in vehicle propulsion systems. During a normal shutdown routine, the pressure differential between the anode inlet and anode outlet is monitored in real time in a period corresponding to the normal closing speed of the anode bypass valve and the pressure differential at the end of the closing cycle of the anode bypass valve is compared to the pressure differential at the beginning of the closing cycle. If the difference in pressure differential at the beginning and end of the anode bypass closing cycle indicates that the anode bypass valve has not properly closed, a system controller switches from a normal shutdown mode to a rapid shutdown mode in which the anode inlet is instantaneously vented by rapid vents.

  6. Shutdown 2013 Update

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

    "cold heads" cool the 1.5-ton superbends to an operating temperature of 4K, pumping in liquid phase nitrogen and helium. To replace the cold heads, each must first be warmed up...

  7. Quality assurance program plan fuel supply shutdown

    SciTech Connect (OSTI)

    Metcalf, I.L.

    1998-09-21

    This Quality Assurance Program plan (QAPP) describes how the Fuel Supply Shutdown (FSS) project organization implements the quality assurance requirements of HNF-MP-599, Project Hanford Quality Assurance Program Description (QAPD) and the B and W Hanford Company Quality Assurance Program Plan (QAPP), FSP-MP-004. The QAPP applies to facility structures, systems, and components and to activities (e.g., design, procurement, testing, operations, maintenance, etc.) that could affect structures, systems, and components. This QAPP also provides a roadmap of applicable Project Hanford Policies and Procedures (PHPP) which may be utilized by the FSS project organization to implement the requirements of this QAPP.

  8. Low Power and Shutdown Risk Assessment Benchmarking Study

    SciTech Connect (OSTI)

    J.Mitman, J. Julius, R. Berucio, M. Phillips, J. Grobbelaaar, D. Bley, R. Budniz

    2002-12-15

    (B204)Probabilistic risk assessment (PRA) insights are now used by the United States Nuclear Regulatory Commission (USNRC) to confirm the level of safety for plant operations and to justify changes in nuclear power plant operating requirements, both on an exception basis and as changeds to a plant's licensing basis. This report examines qualitative and quantitative risk assessments during shutdown plant states, providing feedback to utilities in the use of qualitative models for outage risk management, and also providing input to the development of the American Nuclear Society (ANS) Low Power and Shutdown PRA Standard.

  9. The Fast Flux Test Facility shutdown program plan

    SciTech Connect (OSTI)

    Guttenberg, S.; Jones, D.H.; Midgett, J.C.; Nielsen, D.L.

    1995-01-01

    The Fast Flux Test Facility (FFTF) is a 400 MWt sodium-cooled research reactor owned by the US Department of Energy (DOE) and operated by the Westinghouse Hanford Company (WHC) on the Hanford Site in southeastern Washington State. The decision was made by the DOE in December, 1993, to initiate shutdown of the FFTF. This paper describes the FFTF Transition Project Plan (1) (formerly the FFTF Shutdown Program Plan) which provides the strategy, major elements, and project baseline for transitioning the FFTF to an industrially and radiologically safe shutdown condition. The Plan, and its resource loaded schedule, indicate this transition can be achieved in a period of six to seven years at a cost of approximately $359 million. The transition activities include reactor defueling, fuel offload to dry cask storage, sodium drain and reaction, management of sodium residuals, shutdown of auxiliary systems, and preparation of appropriate environmental and regulatory documentation. Completion of these activities will involve resolution of many challenging and unique issues associated with shutdown of a large sodium reactor facility. At the conclusion of these activities, the FFTF will be in a safe condition for turnover to the Hanford Site Environmental Restoration Contractor for a long term surveillance and maintenance phase and decommissioning.

  10. Experimental and analytical studies of passive shutdown heat removal systems

    SciTech Connect (OSTI)

    Pedersen, D.; Tessier, J.; Heineman, J.; Stewart, R.; Anderson, T.; August, C.; Chawla, T.; Cheung, F.B.; Despe, O.; Haupt, H.J.

    1987-01-01

    Using a naturally circulating air stream to remove shutdown decay heat from a nuclear reactor vessel is a key feature of advanced liquid metal reactor (LMR) concepts developed by potential vendors selected by the Department of Energy. General Electric and Rockwell International continue to develop innovative design concepts aimed at improving safety, lowering plant costs, simplifying plant operation, reducing construction times, and most of all, enhancing plant licensability. The reactor program at Argonne National Laboratory (ANL) provides technical support to both organizations. The method of shutdown heat removal proposed employs a totally passive cooling system that rejects heat from the reactor by radiation and natural convection to air. The system is inherently reliable since it is not subject failure modes associated with active decay cooling systems. The system is designed to assure adequate cooling of the reactor under abnormal operating conditions associated with loss of heat removal through other heat transport paths.

  11. Wind energy and power system operations: a review of wind integration studies to date

    SciTech Connect (OSTI)

    Cesaro, Jennifer de; Porter, Kevin; Milligan, Michael

    2009-12-15

    Wind integration will not be accomplished successfully by doing ''more of the same.'' It will require significant changes in grid planning and operations, continued technical evolution in the design and operation of wind turbines, further adoption and implementation of wind forecasting in the control room, and incorporation of market and policy initiatives to encourage more flexible generation. (author)

  12. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown...

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

    Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites Prepared for U.S. ... Evaluation of Removing Used Nuclear Fuel from Shutdown Sites October 1, 2014 iii ...

  13. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal floods during mid-loop operations. Volume 4

    SciTech Connect (OSTI)

    Kohut, P.

    1994-07-01

    The major objective of the Surry internal flood analysis was to provide an improved understanding of the core damage scenarios arising from internal flood-related events. The mean core damage frequency of the Surry plant due to internal flood events during mid-loop operations is 4.8E-06 per year, and the 5th and 95th percentiles are 2.2E-07 and 1.8E-05 per year, respectively. Some limited sensitivity calculations were performed on three plant improvement options. The most significant result involves modifications of intake-level structure on the canal, which reduced core damage frequency contribution from floods in mid-loop by about 75%.

  14. Run Spear Down Low-alpha Shutdown

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

    Spear Down Low-alpha Shutdown Maintenance / AP University Holidays Sep Oct S 1 Mar Apr May Jun Jul Aug 4/6/2012 SPEAR OPERATING SCHEDULE 2011-2012 2011 2012 Sep Oct Nov Dec Jan Feb 1 2 M 3 1 1 1 S 2 4 1 3 1 AP 2 2 2 W 5 2 4 2 AP AP 3 3 AP 1 3 T 3 5 3 4 1 4 2 4 1 6 4 F 2 7 5 2 1 5 3 1 5 2 T 1 6 4 S 3 8 5 3 7 5 4 1 6 3 2 6 4 2 6 8 5 S 4 9 6 8 6 low 2 7 4 3 7 5 3 7 5 9 MA MA 9 7 M 5 10 3 8 5 4 alpha 8 6 4 T 6 11 8 6 10 8 7 4 9 MA 6 5 9 MA AP 7 13 11 9 W 7 12 9 5 10 AP 7 6 AP 10 8 6 AP 10 AP 7 AP 13

  15. Passive shut-down heat removal system

    DOE Patents [OSTI]

    Hundal, Rolv; Sharbaugh, John E.

    1988-01-01

    An improved shut-down heat removal system for a liquid metal nuclear reactor of the type having a vessel for holding hot and cold pools of liquid sodium is disclosed herein. Generally, the improved system comprises a redan or barrier within the reactor vessel which allows an auxiliary heat exchanger to become immersed in liquid sodium from the hot pool whenever the reactor pump fails to generate a metal-circulating pressure differential between the hot and cold pools of sodium. This redan also defines an alternative circulation path between the hot and cold pools of sodium in order to equilibrate the distribution of the decay heat from the reactor core. The invention may take the form of a redan or barrier that circumscribes the inner wall of the reactor vessel, thereby defining an annular space therebetween. In this embodiment, the bottom of the annular space communicates with the cold pool of sodium, and the auxiliary heat exchanger is placed in this annular space just above the drawn-down level that the liquid sodium assumes during normal operating conditions. Alternatively, the redan of the invention may include a pair of vertically oriented, concentrically disposed standpipes having a piston member disposed between them that operates somewhat like a pressure-sensitive valve. In both embodiments, the cessation of the pressure differential that is normally created by the reactor pump causes the auxiliary heat exchanger to be immersed in liquid sodium from the hot pool. Additionally, the redan in both embodiments forms a circulation flow path between the hot and cold pools so that the decay heat from the nuclear core is uniformly distributed within the vessel.

  16. Shutdown system for a nuclear reactor

    DOE Patents [OSTI]

    Groh, Edward F.; Olson, Arne P.; Wade, David C.; Robinson, Bryan W.

    1984-01-01

    An ultimate shutdown system is provided for termination of neutronic activity in a nuclear reactor. The shutdown system includes bead chains comprising spherical containers suspended on a flexible cable. The containers are comprised of mating hemispherical shells which provide a ruggedized enclosure for reactor poison material. The bead chains, normally suspended above the reactor core on storage spools, are released for downward travel upon command from an external reactor monitor. The chains are capable of horizontal movement, so as to flow around obstructions in the reactor during their downward motion.

  17. Shutdown system for a nuclear reactor

    DOE Patents [OSTI]

    Groh, E.F.; Olson, A.P.; Wade, D.C.; Robinson, B.W.

    1984-06-05

    An ultimate shutdown system is provided for termination of neutronic activity in a nuclear reactor. The shutdown system includes bead chains comprising spherical containers suspended on a flexible cable. The containers are comprised of mating hemispherical shells which provide a ruggedized enclosure for reactor poison material. The bead chains, normally suspended above the reactor core on storage spools, are released for downward travel upon command from an external reactor monitor. The chains are capable of horizontal movement, so as to flow around obstructions in the reactor during their downward motion. 8 figs.

  18. Experimental and analytical studies of a passive shutdown heat removal system for advanced LMRs

    SciTech Connect (OSTI)

    Heineman, J.; Kraimer, M.; Lottes, P.; Pedersen, D.; Stewart, R.; Tessier, J.

    1988-01-01

    A facility designed and constructed to demonstrate the viability of natural convection passive heat removal systems as a key feature of innovative LMR Shutdown Heat Removal (SHR) systems is in operation at Argonne National Laboratory (ANL). This Natural Convection Shutdown Heat Removal Test Facility (NSTF) is being used to investigate the heat transfer performance of the GE/PRISM and the RI/SAFR passive designs. This paper presents a description of the NSTF, the pretest analysis of the Radiant Reactor Vessel Auxiliary Cooling System (RVACS) in support of the GE/PRISM IFR concept, and experiment results for the RVACS simulation. Preliminary results show excellent agreement with predicted system performance.

  19. Securing the Future of Seversk and Zheleznogorsk After Reactor Shutdown. Conference Handbook

    SciTech Connect (OSTI)

    Hund, Gretchen; Stein, Steven L.

    2005-01-31

    Seversk and Zheleznogorsk, two Russian closed nuclear cities, are home to the last three operating plutonium production reactors in Russia. The reactors are now scheduled for shutdown. Closing these reactors presents the world community with a significant nonproliferation achievement, but at the same time poses environmental, economic, and security challenges for the local communities. This conference is an opportunity for the international community to provide crucial support to facilitate these aspects of the plutonium reactor shutdown. Projects proposed complement the reactor shutdown process or assist with worker transition from plutonium production to nonweapons-related careers. Switzerland graciously offered to host the conference with the participation of both the Federal Atomic Energy Agency, Russian Federation and the United States Department of Energy. The one-and-a-half day event was held in Spiez, Switzerland, 8-9 February 2005. Dr. Alec Baer of Switzerland moderated the conference.

  20. Control rod drive for reactor shutdown

    DOE Patents [OSTI]

    McKeehan, Ernest R.; Shawver, Bruce M.; Schiro, Donald J.; Taft, William E.

    1976-01-20

    A means for rapidly shutting down or scramming a nuclear reactor, such as a liquid metal-cooled fast breeder reactor, and serves as a backup to the primary shutdown system. The control rod drive consists basically of an in-core assembly, a drive shaft and seal assembly, and a control drive mechanism. The control rod is driven into the core region of the reactor by gravity and hydraulic pressure forces supplied by the reactor coolant, thus assuring that common mode failures will not interfere with or prohibit scramming the reactor when necessary.

  1. Rodded shutdown system for a nuclear reactor

    DOE Patents [OSTI]

    Golden, Martin P.; Govi, Aldo R.

    1978-01-01

    A top mounted nuclear reactor diverse rodded shutdown system utilizing gas fed into a pressure bearing bellows region sealed at the upper extremity to an armature. The armature is attached to a neutron absorber assembly by a series of shafts and connecting means. The armature is held in an uppermost position by an electromagnet assembly or by pressurized gas in a second embodiment. Deenergizing the electromagnet assembly, or venting the pressurized gas, causes the armature to fall by the force of gravity, thereby lowering the attached absorber assembly into the reactor core.

  2. FFTF (Fast Flux Test Facility) reactor shutdown system reliability reevaluation

    SciTech Connect (OSTI)

    Pierce, B.F.

    1986-07-01

    The reliability analysis of the Fast Flux Test Facility reactor shutdown system was reevaluated. Failure information based on five years of plant operating experience was used to verify original reliability numbers or to establish new ones. Also, system modifications made subsequent to performance of the original analysis were incorporated into the reevaluation. Reliability calculations and sensitivity analyses were performed using a commercially available spreadsheet on a personal computer. The spreadsheet was configured so that future failures could be tracked and compared with expected failures. A number of recommendations resulted from the reevaluation including both increased and decreased surveillance intervals. All recommendations were based on meeting or exceeding existing reliability goals. Considerable cost savings will be incurred upon implementation of the recommendations.

  3. Development of Probabilistic Risk Assessment Model for BWR Shutdown Modes 4 and 5 Integrated in SPAR Model

    SciTech Connect (OSTI)

    S. T. Khericha; S. Sancakter; J. Mitman; J. Wood

    2010-06-01

    Nuclear plant operating experience and several studies show that the risk from shutdown operation during modes 4, 5, and 6 can be significant This paper describes development of the standard template risk evaluation models for shutdown modes 4, and 5 for commercial boiling water nuclear power plants (BWR). The shutdown probabilistic risk assessment model uses full power Nuclear Regulatory Commissions (NRCs) Standardized Plant Analysis Risk (SPAR) model as the starting point for development. The shutdown PRA models are integrated with their respective internal events at-power SPAR model. This is accomplished by combining the modified system fault trees from SPAR full power model with shutdown event tree logic. For human reliability analysis (HRA), the SPAR HRA (SPAR-H) method is used which requires the analysts to complete relatively straight forward worksheet, including the performance shaping factors (PSFs). The results are then used to estimate HEP of interest. The preliminary results indicate the risk is dominated by the operators ability to diagnose the events and provide long term cooling.

  4. Wind Power Impacts on Electric Power System Operating Costs: Summary and Perspective on Work to Date; Preprint

    SciTech Connect (OSTI)

    Smith, J. C.; DeMeo, E. A.; Parsons, B.; Milligan, M.

    2004-03-01

    Electric utility system planners and operators are concerned that variations in wind plant output may increase the operating costs of the system. This concern arises because the system must maintain an instantaneous balance between the aggregate demand for electric power and the total power generated by all power plants feeding the system. This is a highly sophisticated task that utility operators and automatic controls perform routinely, based on well-known operating characteristics for conventional power plants and a great deal of experience accumulated over many years. System operators are concerned that variations in wind plant output will force the conventional power plants to provide compensating variations to maintain system balance, thus causing the conventional power plants to deviate from operating points chosen to minimize the total cost of operating the system. The operators' concerns are compounded by the fact that conventional power plants are generally under their control and thus are dispatchable, whereas wind plants are controlled instead by nature. Although these are valid concerns, the key issue is not whether a system with a significant amount of wind capacity can be operated reliably, but rather to what extent the system operating costs are increased by the variability of the wind.

  5. Nuclear reactor shutdown control rod assembly

    DOE Patents [OSTI]

    Bilibin, Konstantin

    1988-01-01

    A temperature responsive, self-actuated nuclear reactor shutdown control rod assembly 10. The upper end 18 of a lower drive line 17 fits within the lower end of an upper drive line 12. The lower end (not shown) of the lower drive line 17 is connected to a neutron absorber. During normal temperature conditions the lower drive line 17 is supported by detent means 22,26. When an overtemperature condition occurs thermal actuation means 34 urges ring 26 upwardly sufficiently to allow balls 22 to move radially outwardly thereby allowing lower drive line 17 to move downwardly toward the core of the nuclear reactor resulting in automatic reduction of the reactor powder.

  6. Magnetic latch trigger for inherent shutdown assembly

    DOE Patents [OSTI]

    Sowa, Edmund S.

    1976-01-01

    An inherent shutdown assembly for a nuclear reactor is provided. A neutron absorber is held ready to be inserted into the reactor core by a magnetic latch. The latch includes a magnet whose lines of force are linked by a yoke of material whose Curie point is at the critical temperature of the reactor at which the neutron absorber is to be inserted into the reactor core. The yoke is in contact with the core coolant or fissionable material so that when the coolant or the fissionable material increase in temperature above the Curie point the yoke loses its magnetic susceptibility and the magnetic link is broken, thereby causing the absorber to be released into the reactor core.

  7. Self-actuating reactor shutdown system

    DOE Patents [OSTI]

    Barrus, Donald M.; Brummond, Willian A; Peterson, Leslie F.

    1988-01-01

    A control system for the automatic or self-actuated shutdown or "scram" of a nuclear reactor. The system is capable of initiating scram insertion by a signal from the plant protection system or by independent action directly sensing reactor conditions of low-flow or over-power. Self-actuation due to a loss of reactor coolant flow results from a decrease of pressure differential between the upper and lower ends of an absorber element. When the force due to this differential falls below the weight of the element, the element will fall by gravitational force to scram the reactor. Self-actuation due to high neutron flux is accomplished via a valve controlled by an electromagnet and a thermionic diode. In a reactor over-power, the diode will be heated to a change of state causing the electromagnet to be shorted thereby actuating the valve which provides the changed flow and pressure conditions required for scramming the absorber element.

  8. Experimental and analytical studies of passive shutdown heat removal from advanced LMRs (liquid metal reactors)

    SciTech Connect (OSTI)

    Pedersen, D.; Heineman, J.; Stewart, R.; Anderson, T.; Lottes, P.; Tessier, J.

    1988-01-01

    A facility designed and constructed to demonstrate the viability of natural convection passive heat removal systems as a key feature of innovative LMR Shutdown Heat Removal (SHR) systems is in operation at Argonne National Laboratory (ANL). This Natural Convection Shutdown Heat Removal Test Facility (NSTF) has investigated the heat transfer performance of the GE/PRISM passive design. This initial series of experiments simulates the air-side geometry of the PRISM Radiant Reactor Vessel Auxiliary Cooling System (RVACS). The NSTF operates in either a uniform heat flux mode and a uniform temperature mode at the air/guard vessel interface. Analysis of the RVACS performance data indicates excellent agreement with pretest analytical predictions. Correlation analysis presents the heat transfer data in a form suitable for use in LMR design and verification of analytical studies.

  9. How Does the WIPP Shutdown Impact New Mexico, Idaho, and South...

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

    How Does the WIPP Shutdown Impact New Mexico, Idaho, and South Carolina How Does the WIPP Shutdown Impact New Mexico, Idaho, and South Carolina Topic: Southwest Research and ...

  10. Thermionic switched self-actuating reactor shutdown system

    DOE Patents [OSTI]

    Barrus, Donald M. (San Jose, CA); Shires, Charles D. (San Jose, CA); Brummond, William A. (Livermore, CA)

    1989-01-01

    A self-actuating reactor shutdown system incorporating a thermionic switched electromagnetic latch arrangement which is responsive to reactor neutron flux changes and to reactor coolant temperature changes. The system is self-actuating in that the sensing thermionic device acts directly to release (scram) the control rod (absorber) without reference or signal from the main reactor plant protective and control systems. To be responsive to both temperature and neutron flux effects, two detectors are used, one responsive to reactor coolant temperatures, and the other responsive to reactor neutron flux increase. The detectors are incorporated into a thermionic diode connected electrically with an electromagnetic mechanism which under normal reactor operating conditions holds the the control rod in its ready position (exterior of the reactor core). Upon reaching either a specified temperature or neutron flux, the thermionic diode functions to short-circuit the electromagnetic mechanism causing same to lose its holding power and release the control rod, which drops into the reactor core region under gravitational force.

  11. Office of Enterprise Assessments Operational Awareness Record of the Observation of the Waste Isolation Pilot Plant Horizon-14 Exercise, January 2015

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

    Operational Awareness Record Report Number: EA-WIPP-2014-12-08 Site: Waste Isolation Pilot Plant Subject: Observation of the WIPP Horizon-14 Exercise Dates of Activity : December 8-11, 2014 Report Preparer: Tom Rogers Activity Description/Purpose: The Office of Enterprise Assessments (EA) observed the Waste Isolation Pilot Plant (WIPP) Horizon-14 Exercise to ascertain WIPP's progress in strengthening its emergency management program since the shutdown of operations in February 2014. EA performed

  12. Staged venting of fuel cell system during rapid shutdown

    DOE Patents [OSTI]

    Clingerman, Bruce J.; Doan, Tien M.; Keskula, Donald H.

    2002-01-01

    A venting methodology and system for rapid shutdown of a fuel cell apparatus of the type used in a vehicle propulsion system. H.sub.2 and air flows to the fuel cell stack are slowly bypassed to the combustor upon receipt of a rapid shutdown command. The bypass occurs over a period of time (for example one to five seconds) using conveniently-sized bypass valves. Upon receipt of the rapid shutdown command, the anode inlet of the fuel cell stack is instantaneously vented to a remote vent to remove all H.sub.2 from the stack. Airflow to the cathode inlet of the fuel cell stack gradually diminishes over the bypass period, and when the airflow bypass is complete the cathode inlet is also instantaneously vented to a remote vent to eliminate pressure differentials across the stack.

  13. Staged venting of fuel cell system during rapid shutdown

    DOE Patents [OSTI]

    Keskula, Donald H.; Doan, Tien M.; Clingerman, Bruce J.

    2004-09-14

    A venting methodology and system for rapid shutdown of a fuel cell apparatus of the type used in a vehicle propulsion system. H.sub.2 and air flows to the fuel cell stack are slowly bypassed to the combustor upon receipt of a rapid shutdown command. The bypass occurs over a period of time (for example one to five seconds) using conveniently-sized bypass valves. Upon receipt of the rapid shutdown command, the anode inlet of the fuel cell stack is instantaneously vented to a remote vent to remove all H.sub.2 from the stack. Airflow to the cathode inlet of the fuel cell stack gradually diminishes over the bypass period, and when the airflow bypass is complete the cathode inlet is also instantaneously vented to a remote vent to eliminate pressure differentials across the stack.

  14. International Collaboration with the Shutdown of the BN-350 Reactor

    SciTech Connect (OSTI)

    J. A. Michelbacher; P.B. Wells; N. Organ; D. Wells

    2005-08-01

    Representatives from the United States and the United Kingdom discussed areas where collaboration on the shutdown of the BN-350 Reactor in Aktau, Kazakhstan would benefit not only Kazakhstan, but would also help to assure the successful shutdown of the reactor. A fundamental understanding of the basis for collaboration has been for each side to add value to each of the project areas, rather than simply substitute for each others experience. This approach has brought distinct technical and management benefits to the decommissioning activities in Kazakhstan.

  15. Preliminary Evaluation of Removing Used Nuclear Fuel From Shutdown Sites

    Broader source: Energy.gov [DOE]

    In January 2013, the Department of Energy issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste. Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites.

  16. A safety and regulatory assessment of generic BWR and PWR permanently shutdown nuclear power plants

    SciTech Connect (OSTI)

    Travis, R.J.; Davis, R.E.; Grove, E.J.; Azarm, M.A.

    1997-08-01

    The long-term availability of less expensive power and the increasing plant modification and maintenance costs have caused some utilities to re-examine the economics of nuclear power. As a result, several utilities have opted to permanently shutdown their plants. Each licensee of these permanently shutdown (PSD) plants has submitted plant-specific exemption requests for those regulations that they believe are no longer applicable to their facility. This report presents a regulatory assessment for generic BWR and PWR plants that have permanently ceased operation in support of NRC rulemaking activities in this area. After the reactor vessel is defueled, the traditional accident sequences that dominate the operating plant risk are no longer applicable. The remaining source of public risk is associated with the accidents that involve the spent fuel. Previous studies have indicated that complete spent fuel pool drainage is an accident of potential concern. Certain combinations of spent fuel storage configurations and decay times, could cause freshly discharged fuel assemblies to self heat to a temperature where the self sustained oxidation of the zircaloy fuel cladding may cause cladding failure. This study has defined four spent fuel configurations which encompass all of the anticipated spent fuel characteristics and storage modes following permanent shutdown. A representative accident sequence was chosen for each configuration. Consequence analyses were performed using these sequences to estimate onsite and boundary doses, population doses and economic costs. A list of candidate regulations was identified from a screening of 10 CFR Parts 0 to 199. The continued applicability of each regulation was assessed within the context of each spent fuel storage configuration and the results of the consequence analyses.

  17. Record of Decision, Shutdown of the River Water System at the...

    Office of Environmental Management (EM)

    ... Record of Decision, Shutdown of the River Water System at the Savannah River Site, ... for the Shutdown of the River Water System (RWEIS) at the Savannah River Site (SRS). ...

  18. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internal events for Plant Operational State 5 during a refueling outage. Volume 2, Part 3: Internal Events Appendices I and J

    SciTech Connect (OSTI)

    Yakle, J.; Darby, J.; Whitehead, D.; Staple, B.

    1994-06-01

    This report provides supporting documentation for various tasks associated with the performance of the probablistic risk assessment for Plant Operational State 5 during a refueling outage at Grand Gulf, Unit 1 as documented in Volume 2, Part 1 of NUREG/CR-6143.

  19. Summary of Information Presented at an NRC-Sponsored Low-Power Shutdown Public Workshop, April 27, 1999, Rockville, Maryland

    SciTech Connect (OSTI)

    Wheeler, Timothy A.; Whitehead, Donnie W.; Lois, Erasmia

    1999-07-01

    This report summarizes a public workshop that was held on April 27, 1999, in Rockville, Maryland. The workshop was conducted as part of the US Nuclear Regulatory Commission's (NRC) efforts to further develop its understanding of the risks associated with low power and shutdown operations at US nuclear power plants. A sufficient understanding of such risks is required to support decision-making for risk-informed regulation, in particular Regulatory Guide 1.174, and the development of a consensus standard. During the workshop the NRC staff discussed and requested feedback from the public (including representatives of the nuclear industry, state governments, consultants, private industry, and the media) on the risk associated with low-power and shutdown operations.

  20. MEMORANDUM DATE

    Office of Legacy Management (LM)

    E FINCIL PRODUCT W4STE & RESIDUE . AEC,' MED INVOLVEMENT CIT 5 I TE ---...---... Control w Health Physics Protection 0 CIECMED managed operations (-J Little or None ...

  1. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    SciTech Connect (OSTI)

    Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul E.; Massaro, Lawrence M.; Jensen, Philip J.

    2014-10-01

    This report presents a preliminary evaluation of removing used nuclear fuel (UNF) from 12 shutdown nuclear power plant sites. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites are Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. The evaluation was divided into four components: characterization of the UNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory; a description of the on-site infrastructure and conditions relevant to transportation of UNF and GTCC waste; an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing UNF and GTCC waste, including identification of gaps in information; and, an evaluation of the actions necessary to prepare for and remove UNF and GTCC waste. The primary sources for the inventory of UNF and GTCC waste are the U.S. Department of Energy (DOE) RW-859 used nuclear fuel inventory database, industry sources such as StoreFUEL and SpentFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of site and near-site transportation infrastructure and experience included observations and information collected during visits to the Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion sites; information provided by managers at the shutdown sites; Facility Interface Data Sheets compiled for DOE in 2005; Services Planning Documents prepared for DOE in 1993 and 1994; industry publications such as Radwaste Solutions; and Google Earth. State and Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative participated in six of the shutdown site

  2. Control assembly for controlling a fuel cell system during shutdown and restart

    DOE Patents [OSTI]

    Venkataraman, Ramki; Berntsen, George; Carlson, Glenn L.; Farooque, Mohammad; Beachy, Dan; Peterhans, Stefan; Bischoff, Manfred

    2010-06-15

    A fuel cell system and method in which the fuel cell system receives and an input oxidant gas and an input fuel gas, and in which a fuel processing assembly is provided and is adapted to at least humidify the input fuel gas which is to be supplied to the anode of the fuel cell of the system whose cathode receives the oxidant input gas via an anode oxidizing assembly which is adapted to couple the output of the anode of the fuel cell to the inlet of the cathode of the fuel cell during normal operation, shutdown and restart of the fuel cell system, and in which a control assembly is further provided and is adapted to respond to shutdown of the fuel cell system during which input fuel gas and input oxidant gas cease to be received by the fuel cell system, the control assembly being further adapted to, when the fuel cell system is shut down: control the fuel cell system so as to enable a purging gas to be able to flow through the fuel processing assembly to remove humidified fuel gas from the processing assembly and to enable a purging gas to be able to flow through the anode of the fuel cell.

  3. HEMORANDUH TO: FILE DATE

    Office of Legacy Management (LM)

    HEMORANDUH TO: FILE DATE 1123 lLjl ---WV-------------- FROM: P. s&w+ -------v-----s-- SUBJECT: lJ+ - e;& SITE NAME: LJo"zL - /L,' de Cd -J--h=- ALTERNATE l --e-e-- ------w------- ---,,,' ,m--, NAME: ---------------------- CITY: LL-pL~ ------------ ------------- STATE3 e--w-- OWNER tS) -----w-- Past I --k-!!.l~ -pa L . -v-----w------- Current: Owner contac?-ed 0 yes 0 no; if yes, I+Lff A zid;&m - -------------------------- date contacted ------B--m--- TYPE OF OPERATION

  4. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    SciTech Connect (OSTI)

    Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul E.; Massaro, Lawrence M.; Jensen, Philip J.

    2015-09-30

    A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power reactor sites was conducted. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: (1) characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory, (2) a description of the on-site infrastructure and conditions relevant to transportation of SNF and GTCC waste, (3) an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing SNF and GTCC waste, including identification of gaps in information, and (4) an evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. Every site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an important source of information used to identify the transportation mode options for the sites. Especially important in conducting the evaluation were site visits, through which information was obtained that would not have been available otherwise. Extensive photographs taken during the site visits proved to be particularly useful in documenting the current conditions at or near the sites. It is expected that additional site visits will be conducted to add to the information presented in the evaluation.

  5. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

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

    Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites Prepared for U.S. Department of Energy Nuclear Fuels Storage and Transportation Planning Project Steven J. Maheras (PNNL) Ralph E. Best (PNNL) Steven B. Ross (PNNL) Kenneth A. Buxton (PNNL) Jeffery L. England (SRNL) Paul E. McConnell (SNL) Lawrence M. Massaro (FRA) Philip J. Jensen (PNNL) October 1, 2014 FCRD- NFST-2014-000091 Rev. 1 PNNL-22676 Rev. 4 DISCLAIMER This information was prepared as an account of work sponsored

  6. A dynamic process model of a natural gas combined cycle -- Model development with startup and shutdown simulations

    SciTech Connect (OSTI)

    Liese, Eric; Zitney, Stephen E.

    2013-01-01

    Research in dynamic process simulation for integrated gasification combined cycles (IGCC) with carbon capture has been ongoing at the National Energy Technology Laboratory (NETL), culminating in a full operator training simulator (OTS) and immersive training simulator (ITS) for use in both operator training and research. A derivative work of the IGCC dynamic simulator has been a modification of the combined cycle section to more closely represent a typical natural gas fired combined cycle (NGCC). This paper describes the NGCC dynamic process model and highlights some of the simulator’s current capabilities through a particular startup and shutdown scenario.

  7. Dates Fact Sheet.cdr

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

    Concept DATES is a detection and security information/event management (SIEM) solution enabling asset owners to protect their energy control systems at the network, host, and device level from cyber attacks. DATES complements traditional, signature-based detection with multiple detection algorithms, including model- based and flow anomaly detection and cross-site attack correlation. The DATES detection and SIEM solution gives operators succinct and intuitive attack visualization, with attacks

  8. Audit of Shutdown and Transition of the Mound Plant, IG-0408 | Department

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

    of Energy Shutdown and Transition of the Mound Plant, IG-0408 Audit of Shutdown and Transition of the Mound Plant, IG-0408 Audit of Shutdown and Transition of the Mound Plant, IG-0408 (68.17 KB) More Documents & Publications EIS-0302: Notice of Intent to Prepare an Environmental Impact Statement EIS-0302: Withdrawal of Notice of Intent to Prepare an Environmental Impact Statement Semiannual Report to Congress: April 1 - September 30, 1997

  9. Date | Open Energy Information

    Open Energy Info (EERE)

    Date Jump to: navigation, search Properties of type "Date" Showing 48 properties using this type. A Property:ASHRAE 169 End Date Property:ASHRAE 169 Start Date B Property:Building...

  10. Preliminary Evaluation of Removing Used Nuclear Fuel From Nine Shutdown Sites

    SciTech Connect (OSTI)

    Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul

    2013-04-30

    The Blue Ribbon Commission on America’s Nuclear Future identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses. In this report, a preliminary evaluation of removing used nuclear fuel from nine shutdown sites was conducted. The shutdown sites included Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion. At these sites a total of 7649 used nuclear fuel assemblies and a total of 2813.2 metric tons heavy metal (MTHM) of used nuclear fuel are contained in 248 storage canisters. In addition, 11 canisters containing greater-than-Class C (GTCC) low-level radioactive waste are stored at these sites. The evaluation was divided in four components: • characterization of the used nuclear fuel and GTCC low-level radioactive waste inventory at the shutdown sites • an evaluation of the onsite transportation conditions at the shutdown sites • an evaluation of the near-site transportation infrastructure and experience relevant to the shipping of transportation casks containing used nuclear fuel from the shutdown sites • an evaluation of the actions necessary to prepare for and remove used nuclear fuel and GTCC low-level radioactive waste from the shutdown sites. Using these evaluations the authors developed time sequences of activities and time durations for removing the used nuclear fuel and GTCC low-level radioactive waste from a single shutdown site, from three shutdown sites located close to each other, and from all nine shutdown sites.

  11. Risk-based evaluation of Allowed Outage Times (AOTs) considering risk of shutdown

    SciTech Connect (OSTI)

    Mankamo, T.; Kim, I.S.; Samanta, P.K.

    1992-12-31

    When safety systems fail during power operation, Technical Specifications (TS) usually limit the repair within Allowed Outage Time (AOT). If the repair cannot be completed within the AOT, or no AOT is allowed, the plant is required to be shut down for the repair. However, if the capability to remove decay heat is degraded, shutting down the plant with the need to operate the affected decay-heat removal systems may impose a substantial risk compared to continued power operation over a usual repair time. Thus, defining a proper AOT in such situations can be considered as a risk-comparison between the repair in frill power state with a temporarily increased level of risk, and the altemative of shutting down the plant for the repair in zero power state with a specific associated risk. The methodology of the risk-comparison approach, with a due consideration of the shutdown risk, has been further developed and applied to the AOT considerations of residual heat removal and standby service water systems of a boiling water reactor (BWR) plant. Based on the completed work, several improvements to the TS requirements for the systems studied can be suggested.

  12. Risk-based evaluation of Allowed Outage Times (AOTs) considering risk of shutdown

    SciTech Connect (OSTI)

    Mankamo, T. ); Kim, I.S.; Samanta, P.K. )

    1992-01-01

    When safety systems fail during power operation, Technical Specifications (TS) usually limit the repair within Allowed Outage Time (AOT). If the repair cannot be completed within the AOT, or no AOT is allowed, the plant is required to be shut down for the repair. However, if the capability to remove decay heat is degraded, shutting down the plant with the need to operate the affected decay-heat removal systems may impose a substantial risk compared to continued power operation over a usual repair time. Thus, defining a proper AOT in such situations can be considered as a risk-comparison between the repair in frill power state with a temporarily increased level of risk, and the altemative of shutting down the plant for the repair in zero power state with a specific associated risk. The methodology of the risk-comparison approach, with a due consideration of the shutdown risk, has been further developed and applied to the AOT considerations of residual heat removal and standby service water systems of a boiling water reactor (BWR) plant. Based on the completed work, several improvements to the TS requirements for the systems studied can be suggested.

  13. Office of Inspector General report on audit of shutdown and transition of the Mound Plant

    SciTech Connect (OSTI)

    1997-06-24

    With the end of the Cold War, the Department of Energy (Department) has greatly reduced the production of nuclear weapons and redirected the capabilities and focus of the weapons complex. As part of this redirection, the Mound Plant was transferred from a Defense Program site to an Environmental Management site with emphasis on accelerated cleanup and transition of facilities and personal property to the local community. This audit was initiated to determine if the shutdown and transition of the Mound Plant was progressing effectively and efficiently. The Department prepared a Nonnuclear Consolidation Plan (NCP) designed to reduce its costs of operation by closing and consolidating facilities. In contrast to the goal of the NCP, the Department plans to keep a portion of the Mound Plant open solely to perform work for other Federal agencies. Specifically, the Department has decided to continue assembling and testing isotopic heat sources and radioisotope thermoelectric generators (HS/RTG) at the Mound Plant despite the transfer or planned transfer of all other production operations.The Office of Nuclear Energy, Science and Technology decided to continue its HS/RTG operations at the Mound Plant without adequately considering the overall economic goals of the Department. As a result, the Department may not achieve the savings envisioned by the NCP. Also, the Department may incur between $4 million and $8.5 million more than necessary each year to continue its HS/RTG operations at the Mound Plant. Additionally, if the HS/RTG operations stay at the Mound Plant, the Department will spend more than $3 million to consolidate these operations into one location.

  14. Advanced wind turbine with lift cancelling aileron for shutdown

    DOE Patents [OSTI]

    Coleman, Clint; Juengst, Theresa M.; Zuteck, Michael D.

    1996-06-18

    An advanced aileron configuration for wind turbine rotors featuring an independent, lift generating aileron connected to the rotor blade. The aileron has an airfoil profile which is inverted relative to the airfoil profile of the main section of the rotor blade. The inverted airfoil profile of the aileron allows the aileron to be used for strong positive control of the rotation of the rotor while deflected to angles within a control range of angles. The aileron functions as a separate, lift generating body when deflected to angles within a shutdown range of angles, generating lift with a component acting in the direction opposite the direction of rotation of the rotor. Thus, the aileron can be used to shut down rotation of the rotor. The profile of the aileron further allows the center of rotation to be located within the envelope of the aileron, at or near the centers of pressure and mass of the aileron. The location of the center of rotation optimizes aerodynamically and gyroscopically induced hinge moments and provides a fail safe configuration.

  15. Advanced wind turbine with lift-destroying aileron for shutdown

    DOE Patents [OSTI]

    Coleman, Clint; Juengst, Theresa M.; Zuteck, Michael D.

    1996-06-18

    An advanced aileron configuration for wind turbine rotors featuring an aileron with a bottom surface that slopes upwardly at an angle toward the nose region of the aileron. The aileron rotates about a center of rotation which is located within the envelope of the aileron, but does not protrude substantially into the air flowing past the aileron while the aileron is deflected to angles within a control range of angles. This allows for strong positive control of the rotation of the rotor. When the aileron is rotated to angles within a shutdown range of deflection angles, lift-destroying, turbulence-producing cross-flow of air through a flow gap, and turbulence created by the aileron, create sufficient drag to stop rotation of the rotor assembly. The profile of the aileron further allows the center of rotation to be located within the envelope of the aileron, at or near the centers of pressure and mass of the aileron. The location of the center of rotation optimizes aerodynamically and gyroscopically induced hinge moments and provides a fail safe configuration.

  16. DATE: | Department of Energy

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

    DATE: DATE: PDF icon DATE: More Documents & Publications Policy Flash 2013-2 Policy Flash 2013-51 311 Notice Aquisition Letter 2013-05 Financial Assistance Letter 2013-03 ...

  17. LIQUID PHASE FISCHER-TROPSCH (III & IV) DEMONSTRATION IN THE LAPORTE ALTERNATIVE FUELS DEVELOPMENT UNIT. Final Topical Report. Volume I/II: Main Report. Task 1: Engineering Modifications (Fischer-Tropsch III & IV Demonstration) and Task 2: AFDU Shakedown, Operations, Deactivation (Shut-Down) and Disposal (Fischer-Tropsch III & IV Demonstration).

    SciTech Connect (OSTI)

    Bharat L. Bhatt

    1999-06-01

    Slurry phase Fischer-Tropsch technology was successfully demonstrated in DOE's Alternative Fuels Development Unit (AFDU) at LaPorte, Texas. Earlier work at LaPorte, with iron catalysts in 1992 and 1994, had established proof-of-concept status for the slurry phase process. The third campaign (Fischer-Tropsch III), in 1996, aimed at aggressively extending the operability of the slurry reactor using a proprietary cobalt catalyst. Due to an irreversible plugging of catalyst-wax separation filters as a result of unexpected catalyst fines generation, the operations had to be terminated after seven days on-stream. Following an extensive post-run investigation by the participants, the campaign was successfully completed in March-April 1998, with an improved proprietary cobalt catalyst. These runs were sponsored by the U. S. Department of Energy (DOE), Air Products & Chemicals, Inc., and Shell Synthetic Fuels, Inc. (SSFI). A productivity of approximately 140 grams (gm) of hydrocarbons (HC)/ hour (hr)-liter (lit) of expanded slurry volume was achieved at reasonable system stability during the second trial (Fischer-Tropsch IV). The productivity ranged from 110-140 at various conditions during the 18 days of operations. The catalyst/wax filters performed well throughout the demonstration, producing a clean wax product. For the most part, only one of the four filter housings was needed for catalyst/wax filtration. The filter flux appeared to exceed the design flux. A combination of use of a stronger catalyst and some innovative filtration techniques were responsible for this success. There was no sign of catalyst particle attrition and very little erosion of the slurry pump was observed, in contrast to the Fischer-Tropsch III operations. The reactor operated hydrodynamically stable with uniform temperature profile and gas hold-ups. Nuclear density and differential pressure measurements indicated somewhat higher than expected gas hold-up (45 - 50 vol%) during Fischer-Tropsch IV

  18. Posting Date: OPEN Posting Close Date: OPEN

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

    OPEN Posting Close Date: OPEN North American Industry Classification System (NAICS) code for the request: TBD Estimated Subcontract/PO Value: TBD Estimated Period of Performance N/A Estimated RFP/RFQ Release Date: TBD Estimated Award Date: TBD Competition Type: Full Set-Aside Buyer Contact Email: business@lanl.gov Title: General Construction Services Description of Product or Service Required Looking for small business construction companies in all sectors of construction. Must be familiar with

  19. EA-0993: Shutdown of the Fast Flux Testing Facility, Richland, Washington

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the U.S. Department of Energy's Hanford Site's proposal to place the Fast Flux Test Facility (FFTF) in a radiologically and industrially safe shutdown...

  20. Current status of experimental breeder reactor-II [EBR-II] shutdown planning

    SciTech Connect (OSTI)

    McDermott, M. D.; Griffin, C. D.; Michelbacher, J. A.; Earle, O. K.

    2000-05-08

    The Experimental Breeder Reactor--II (EBR-II) at Argonne National Laboratory--West (ANL-W) in Idaho, was shutdown in September, 1994 as mandated by the US Department of Energy. This sodium cooled reactor had been in service since 1964, and was to be placed in an industrially and radiologically safe condition for ultimate decommissioning. The deactivation of a liquid metal reactor presents unique concerns. The first major task associated with the project was the removal of all fueled assemblies. In addition, sodium must be drained from systems and processed for ultimate disposal. Residual quantities of sodium remaining in systems must be deactivated or inerted to preclude future hazards associated with pyrophoricity and generation of potentially explosive hydrogen gas. A Sodium Process Facility was designed and constructed to react the elemental sodium from the EBR-II primary and secondary systems to sodium hydroxide for disposal. This facility has a design capacity to allow the reaction of the complete inventory of sodium at ANL-W in less than two years. Additional quantities of sodium from the Fermi-1 reactor are also being treated at the Sodium Process Facility. The sodium environment and the EBR-II configuration, combined with the radiation and contamination associated with thirty years of reactor operation, posed problems specific to liquid metal reactor deactivation. The methods being developed and implemented at EBR-II can be applied to other similar situations in the US and abroad.

  1. Self-actuated nuclear reactor shutdown system using induction pump to facilitate sensing of core coolant temperature

    DOE Patents [OSTI]

    Sievers, Robert K.; Cooper, Martin H.; Tupper, Robert B.

    1987-01-01

    A self-actuated shutdown system incorporated into a reactivity control assembly in a nuclear reactor includes pumping means for creating an auxiliary downward flow of a portion of the heated coolant exiting from the fuel assemblies disposed adjacent to the control assembly. The shutdown system includes a hollow tubular member which extends through the outlet of the control assembly top nozzle so as to define an outer annular flow channel through the top nozzle outlet separate from an inner flow channel for primary coolant flow through the control assembly. Also, a latching mechanism is disposed in an inner duct of the control assembly and is operable for holding absorber bundles in a raised position in the control assembly and for releasing them to drop them into the core of the reactor for shutdown purposes. The latching mechanism has an inner flow passage extending between and in flow communication with the absorber bundles and the inner flow channel of the top nozzle for accommodating primary coolant flow upwardly through the control assembly. Also, an outer flow passage separate from the inner flow passage extends through the latching mechanism between and in flow communication with the inner duct and the outer flow channel of the top nozzle for accommodating inflow of a portion of the heated coolant from the adjacent fuel assemblies. The latching mechanism contains a magnetic material sensitive to temperature and operable to cause mating or latching together of the components of the latching mechanism when the temperature sensed is below a known temperature and unmating or unlatching thereof when the temperature sensed is above a given temperature. The temperature sensitive magnetic material is positioned in communication with the heated coolant flow through the outer flow passage for directly sensing the temperature thereof. Finally, the pumping means includes a jet induction pump nozzle and diffuser disposed adjacent the bottom nozzle of the control assembly

  2. Interim Safety Basis for Fuel Supply Shutdown Facility

    SciTech Connect (OSTI)

    BENECKE, M.W.

    2000-09-07

    This ISB, in conjunction with the IOSR, provides the required basis for interim operation or restrictions on interim operations and administrative controls for the facility until a SAR is prepared in accordance with the new requirements or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines.

  3. One-of-a-Kind Facility Now in Safe Shutdown | Department of Energy

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

    One-of-a-Kind Facility Now in Safe Shutdown One-of-a-Kind Facility Now in Safe Shutdown January 1, 2013 - 12:00pm Addthis Members of the team that helped safely close the Toxic Substances Control Act Incinerator at Oak Ridge gather for a photo. The team is from URS|CH2M, Oak Ridge, the prime contractor for the Oak Ridge Office of Environmental Management. Members of the team that helped safely close the Toxic Substances Control Act Incinerator at Oak Ridge gather for a photo. The team is from

  4. Mitigation Measures Following a Loss-of-Residual-Heat-Removal Event During Shutdown

    SciTech Connect (OSTI)

    Seul, Kwang Won; Bang, Young Seok; Kim, Hho Jung

    2000-10-15

    The transient following a loss-of-residual-heat-removal event during shutdown was analyzed to determine the containment closure time (CCT) to prevent uncontrolled release of fission products and the gravity-injection path and rate (GIPR) for effective core cooling using the RELAP5/MOD3.2 code. The plant conditions of Yonggwang Units 3 and 4, a pressurized water reactor (PWR) of 2815-MW(thermal) power in Korea, were reviewed, and possible event sequences were identified. From the CCT analysis for the five cases of typical plant configurations, it was estimated for the earliest CCT to be 40 min after the event in a case with a large cold-leg opening and emptied steam generators (SGs). However, the case with water-filled SGs significantly delayed the CCT through the heat removal to the secondary side. From the GIPR analysis for the six possible gravity-injection paths from the refueling water storage tank (RWST), the case with the injection point and opening on the other leg side was estimated to be the most suitable path to avoid core boiling. In addition, from the sensitivity study, it was evaluated for the plant to be capable of providing the core cooling for the long-term transient if nominal RWST water is available. As a result, these analysis methods and results will provide useful information in understanding the plant behavior and preparing the mitigation measures after the event, especially for Combustion Engineering-type PWR plants. However, to directly apply the analysis results to the emergency procedure for such an event, additional case studies are needed for a wide range of operating conditions such as reactor coolant inventory, RWST water temperature, and core decay heat rate.

  5. Cooling/heating augmentation during turbine startup/shutdown using a seal positioned by thermal response of turbine parts and consequent relative movement thereof

    DOE Patents [OSTI]

    Schmidt, Mark Christopher

    2000-01-01

    In a turbine rotor, a thermal mismatch between various component parts of the rotor occurs particularly during transient operations such as shutdown and startup. A thermal medium flows past and heats or cools one part of the turbine which may have a deleterious thermal mismatch with another part. By passively controlling the flow of cooling medium past the one part in response to relative movement of thermally responsive parts of the turbine, the flow of thermal medium along the flow path can be regulated to increase or reduce the flow, thereby to regulate the temperature of the one part to maintain the thermal mismatch within predetermined limits.

  6. Brawley 10MW Geothermal Plant Plant Manual for Southern California Edison Company and Union Oil Company of California: Systems Start-up and Operations, Volume II

    SciTech Connect (OSTI)

    1980-11-28

    Each system within the facility is considered from an operation viewpoint. There are five subsegments within this operation's viewpoint. Prerequisite conditions, start-up, normal operating, emergency and shutdown.

  7. How Does the WIPP Shutdown Impact New Mexico, Idaho, and South Carolina

    Broader source: Energy.gov [DOE]

    Southwest Research and Information Center presented on the Impact of the WIPP shutdown on the states of New Mexico, Idaho, and South Carolina, the presenter was Don Hancock. Information provided covered: budget numbers, waste storage numbers, safety, and what needs to be done to reopen WIPP.

  8. Dating the Vinland Map

    ScienceCinema (OSTI)

    None

    2013-07-17

    Scientists from Brookhaven National Laboratory, the University of Arizona, and the Smithsonian Institution used carbon-dating technology to determine the age of a controversial parchment that might be the first-ever map of North America.

  9. DATE: REPLY TO

    Office of Legacy Management (LM)

    DOE F 1325.8 (NW ed States Governhent ilmemorandum DATE: REPLY TO ' bPfl29 1993 Al-fN OF: EM-421 (W. W illiams, 903-8149) SUBJECT: Authorization for Remedial Action at the Former...

  10. DATE SUBMITTED: GRADE LEVEL:

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

    two total hours per visit. For more students than that, please plan a visit on another date. To make a request, please complete the form below and submit it to...

  11. Evaluation of respiratory variables in smelter and control workers before and during a shutdown period

    SciTech Connect (OSTI)

    Holness, D.L.; Batten, B.; Broder, I.; Corey, P.; Mintz, S.

    1985-05-01

    Thirty-six smelter workers examined in this pilot study were found to have a higher prevalence of cough and dyspnea and lower baseline lung function than did 31 controls. They also experienced decreases in forced vital capacity (FVC) and forced expiratory volume in 1s (FEV1) over the workweek while the controls did not. Baseline airflow rates and change in FVC and FEV1 over the workweek varied with levels of sulfur dioxide and particulates. Twenty-three smelter workers and 21 controls were seen on a second occasion, six months into an extended shutdown. The smelter workers continued to have a higher prevalence of cough and dyspnea and lower baseline lung function than the controls. There was, however, a slight increase in lung function in both the exposed workers and the controls during the shutdown. The results suggest that smelter workers may develop both acute and chronic work-related pulmonary effects and that the chronic effects may be nonreversible.

  12. Design criteria for a self-actuated shutdown system to ensure limitation of core damage. [LMFBR

    SciTech Connect (OSTI)

    Deane, N.A.; Atcheson, D.B.

    1981-09-01

    Safety-based functional requirements and design criteria for a self-actuated shutdown system (SASS) are derived in accordance with LOA-2 success criteria and reliability goals. The design basis transients have been defined and evaluated for the CDS Phase II design, which is a 2550 MWt mixed oxide heterogeneous core reactor. A partial set of reactor responses for selected transients is provided as a function of SASS characteristics such as reactivity worth, trip points, and insertion times.

  13. FRAP-T5 predictions during reactor shutdown events. [PWR; BWR

    SciTech Connect (OSTI)

    Peeler, G.B.; Laats, E.T.

    1980-01-01

    The Transient Fuel Rod Analysis Program, FRAP-T5, was recently assessed by EG and G Idaho, Inc. As part of this assessment, the measured and FRAP-T5 predicted fuel centerline temperature response during reactor shutdown events were compared. For these events either forced convection or nucleate boiling boundary conditions existed, resulting in a negligible effect on fuel behavior from cladding temperature and deformation uncertainties. This allowed the assessment of internal heat transfer to be emphasized.

  14. Enhanced autonomic shutdown of Li-ion batteries by polydopamine coated polyethylene microspheres

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

    Baginska, Marta; Blaiszik, Benjamin J.; Rajh, Tijana; Sottos, Nancy R.; White, Scott R.

    2014-07-17

    Thermally triggered autonomic shutdown of a Lithium-ion (Li-ion) battery is demonstrated using polydopamine (PDA)-coated polyethylene microspheres applied onto a battery anode. The microspheres are dispersed in a buffered 10 mM dopamine salt solution and the pH is raised to initiate the polymerization and coat the microspheres. Coated microspheres are then mixed with an aqueous binder, applied onto a battery anode surface, dried, and incorporated into Li-ion coin cells. FTIR and Raman spectroscopy are used to verify the presence of the polydopamine on the surface of the microspheres. Scanning electron microscopy is used to examine microsphere surface morphology and resulting anodemore » coating quality. Charge and discharge capacity, as well as impedance, are measured for Li-ion coin cells as a function of microsphere content. Autonomous shutdown is achieved by applying 1.7 mg cm–2 of PDA-coated microspheres to the electrode. Furthermore, the PDA coating significantly reduces the mass of microspheres for effective shutdown compared to our prior work with uncoated microspheres.« less

  15. Enhanced autonomic shutdown of Li-ion batteries by polydopamine coated polyethylene microspheres

    SciTech Connect (OSTI)

    Baginska, Marta; Blaiszik, Benjamin J.; Rajh, Tijana; Sottos, Nancy R.; White, Scott R.

    2014-07-17

    Thermally triggered autonomic shutdown of a Lithium-ion (Li-ion) battery is demonstrated using polydopamine (PDA)-coated polyethylene microspheres applied onto a battery anode. The microspheres are dispersed in a buffered 10 mM dopamine salt solution and the pH is raised to initiate the polymerization and coat the microspheres. Coated microspheres are then mixed with an aqueous binder, applied onto a battery anode surface, dried, and incorporated into Li-ion coin cells. FTIR and Raman spectroscopy are used to verify the presence of the polydopamine on the surface of the microspheres. Scanning electron microscopy is used to examine microsphere surface morphology and resulting anode coating quality. Charge and discharge capacity, as well as impedance, are measured for Li-ion coin cells as a function of microsphere content. Autonomous shutdown is achieved by applying 1.7 mg cm–2 of PDA-coated microspheres to the electrode. Furthermore, the PDA coating significantly reduces the mass of microspheres for effective shutdown compared to our prior work with uncoated microspheres.

  16. Posting Date: 28 May, 2015 Posting Close Date: TBD

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

    PO Value: TBD Estimated Period of Performance: TBD Estimated RFPRFQ Release Date: FY 2016 Estimated Award Date: TBD Competition Type: TBD Buyer Contact Email:...

  17. MEMORANDUfl J: FILE DATE

    Office of Legacy Management (LM)

    J: FILE DATE r so ---...w------m FROM: 9. 34oyc -w---...v----- SUBJECT: D3 Bo;s CL&;C J mL-;+J; - Rcc cap 049 'A :j: &336;s L-.fh w-f L-1 ALE"nirTE ---...

  18. NEUTRONIC REACTOR CONSTRUCTION AND OPERATION

    DOE Patents [OSTI]

    West, J.M.; Weills, J.T.

    1960-03-15

    A method is given for operating a nuclear reactor having a negative coefficient of reactivity to compensate for the change in reactor reactivity due to the burn-up of the xenon peak following start-up of the reactor. When it is desired to start up the reactor within less than 72 hours after shutdown, the temperature of the reactor is lowered prior to start-up, and then gradually raised after start-up.

  19. DATE: TO: FROM:

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

    POLICY FLASH 2015-30 DATE: TO: FROM: June 18, 2015 Procurement Directors/Contracting Officers ~~-- Chief Contract and Financial Assistance Policy Division Office of Policy Office of Acquisition and Project Management SUBJECT: Clarification on the Drug Testing Custody and Control Form for Department of Energy Contractors SUMMARY: Effective immediately, please ensure that all DOE contractors use the Forensic Drug Testing Custody and Control Form for their drug testing programs to comply with the

  20. Building Number/Name: Date prepared: Responsible Contractor...

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

    3-E Jan 28, 2012 WRPS C M Smith; E A Hill PAST OPERATIONS Beryllium brought in facility: YES Form of beryllium: SOLID Period of beryllium operations (dates): Start: Early 1980s ...

  1. Building Number/Name: Date prepared: Responsible Contractor...

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

    22-S February 2, 2012 WRPS C M Smith; E A Hill PAST OPERATIONS Beryllium brought in facility: YES Form of beryllium: LIQUID matrix Period of beryllium operations (dates): (1) ...

  2. Building Number/Name: Date prepared: Responsible Contractor...

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

    07-SX Jan 29, 2012 WRPS C M Smith; E A Hill PAST OPERATIONS Beryllium brought in facility: YES Form of beryllium: SOLID Period of beryllium operations (dates): Start: Early 1980s ...

  3. Building Number/Name: Date prepared: Responsible Contractor...

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

    2-AW Feb 10,2012 WRPS C M Smith; E A Hill PAST OPERATIONS Beryllium brought in facility: YES Form of beryllium: SOLID Period of beryllium operations (dates): Start: Early 1980s ...

  4. Building Number/Name: Date prepared: Responsible Contractor...

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

    WA February 7, 2012 WRPS C M Smith; E A Hill PAST OPERATIONS Beryllium brought in facility: YES Form of beryllium: SOLID Period of beryllium operations (dates): Start: Early 1980s ...

  5. Building Number/Name: Date prepared: Responsible Contractor...

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

    101-HV Feb 8 201 WRPS C M Smith; E A Hill PAST OPERATIONS Beryllium brought in facility: YES Form of beryllium: SOLID Period of beryllium operations (dates): Start: Early 1980s ...

  6. Building Number/Name: Date prepared: Responsible Contractor...

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

    S Feb 10, 2012 WRPS C M Smith; E A Hill PAST OPERATIONS Beryllium brought in facility: YES Form of beryllium: SOLID Period of beryllium operations (dates): Start: Early 1980s End: ...

  7. TO: FILE DATE

    Office of Legacy Management (LM)

    c AECRED overviewed operations &+--Contractor had total control a unknown q Health Physics Protection ; c Little or None : c AECMED responsibility qContractoi'responsibility ...

  8. MEMORANDUM TO: FILE DATE

    Office of Legacy Management (LM)

    AECMED INVOLVEMEVT AT SITE ---... ----- ---. ----- ----- Control v Health Physics Protection - Cl AEWMED managed operations 0 AECMED responsible for dLittle or None ...

  9. TO: FILE DATE------

    Office of Legacy Management (LM)

    ---... -- Cantrol k tiiait6 Physics Protection . q AECHED managed operation; ... 17. 1944 Deer Colonel Ruhoff: The Physics Group nttachoj 10 our project is very ...

  10. United States Government DATE:

    Office of Legacy Management (LM)

    5oE(E;,8 ' 0 H .2+ L-1 United States Government DATE: MAR 0 8 1994 REPLY TO AlTN OF: EM-421 (W. A. Williams, 903-8149) SUBJECT: Authority Determination -- Former Herring-Hall-Marvin Safe Co., Hamilton, Ohio TO: The File The attached review documents the basis for determining whether the Department of Energy (DOE) has authority for taking remedial action at the former Herring-Hall-Marvin Safe Co. facility in Hamilton, Ohio, under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The

  11. SPECIAL DATE AND TIME

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

    SPECIAL DATE AND TIME Evolving views of the outer solar system: new insights from NASA's New Horizons mission's historic first Pluto fly-by Dr. Kimberly Ennico Smith NASA Ames Research Center, Astrophysics Branch April 11, 2016 2:00 p.m. - Wilson Hall, One West On July 14, 2015, after a 9.5 year trek across the solar system, NASA's New Horizons spacecraft successfully flew by Pluto and its system of moons, taking imagery, spectra and in-situ particle data. In this internet- information age, this

  12. MEMORANDUM TO: FILE DATE

    Office of Legacy Management (LM)

    ' .I",. ,,' , ..I> .; .Whd I' NVO&tllT PIT SITE Control q Health Physics Protection 0 AECMED managed operations ,gLittle or None 0 AECMED responsible for c ...

  13. A SCOPING STUDY: Development of Probabilistic Risk Assessment Models for Reactivity Insertion Accidents During Shutdown In U.S. Commercial Light Water Reactors

    SciTech Connect (OSTI)

    S. Khericha

    2011-06-01

    This report documents the scoping study of developing generic simplified fuel damage risk models for quantitative analysis from inadvertent reactivity insertion events during shutdown (SD) in light water pressurized and boiling water reactors. In the past, nuclear fuel reactivity accidents have been analyzed both mainly deterministically and probabilistically for at-power and SD operations of nuclear power plants (NPPs). Since then, many NPPs had power up-rates and longer refueling intervals, which resulted in fuel configurations that may potentially respond differently (in an undesirable way) to reactivity accidents. Also, as shown in a recent event, several inadvertent operator actions caused potential nuclear fuel reactivity insertion accident during SD operations. The set inadvertent operator actions are likely to be plant- and operation-state specific and could lead to accident sequences. This study is an outcome of the concern which arose after the inadvertent withdrawal of control rods at Dresden Unit 3 in 2008 due to operator actions in the plant inadvertently three control rods were withdrawn from the reactor without knowledge of the main control room operator. The purpose of this Standardized Plant Analysis Risk (SPAR) Model development project is to develop simplified SPAR Models that can be used by staff analysts to perform risk analyses of operating events and/or conditions occurring during SD operation. These types of accident scenarios are dominated by the operator actions, (e.g., misalignment of valves, failure to follow procedures and errors of commissions). Human error probabilities specific to this model were assessed using the methodology developed for SPAR model human error evaluations. The event trees, fault trees, basic event data and data sources for the model are provided in the report. The end state is defined as the reactor becomes critical. The scoping study includes a brief literature search/review of historical events, developments of

  14. Media contact: Release date

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

    4, 2010 media@wch-rcc.com Local veteran-owned small business gets ARRA funds to upgrade ERDF RICHLAND, Wash.-Washington Closure Hanford has awarded a subcontract worth nearly $7 million to ERLFowler, a local small business, to design and build an operations center and three maintenance facilities at Hanford's Environmental Restoration Disposal Facility. The new facilities are part of a $100 million expansion and upgrade of ERDF funded by the American Recovery and Reinvestment Act. The expansion

  15. The Multi-Step CADIS method for shutdown dose rate calculations and uncertainty propagation

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

    Ibrahim, Ahmad M.; Peplow, Douglas E.; Grove, Robert E.; Peterson, Joshua L.; Johnson, Seth R.

    2015-12-01

    Shutdown dose rate (SDDR) analysis requires (a) a neutron transport calculation to estimate neutron flux fields, (b) an activation calculation to compute radionuclide inventories and associated photon sources, and (c) a photon transport calculation to estimate final SDDR. In some applications, accurate full-scale Monte Carlo (MC) SDDR simulations are needed for very large systems with massive amounts of shielding materials. However, these simulations are impractical because calculation of space- and energy-dependent neutron fluxes throughout the structural materials is needed to estimate distribution of radioisotopes causing the SDDR. Biasing the neutron MC calculation using an importance function is not simple becausemore » it is difficult to explicitly express the response function, which depends on subsequent computational steps. Furthermore, the typical SDDR calculations do not consider how uncertainties in MC neutron calculation impact SDDR uncertainty, even though MC neutron calculation uncertainties usually dominate SDDR uncertainty.« less

  16. The Multi-Step CADIS method for shutdown dose rate calculations and uncertainty propagation

    SciTech Connect (OSTI)

    Ibrahim, Ahmad M.; Peplow, Douglas E.; Grove, Robert E.; Peterson, Joshua L.; Johnson, Seth R.

    2015-12-01

    Shutdown dose rate (SDDR) analysis requires (a) a neutron transport calculation to estimate neutron flux fields, (b) an activation calculation to compute radionuclide inventories and associated photon sources, and (c) a photon transport calculation to estimate final SDDR. In some applications, accurate full-scale Monte Carlo (MC) SDDR simulations are needed for very large systems with massive amounts of shielding materials. However, these simulations are impractical because calculation of space- and energy-dependent neutron fluxes throughout the structural materials is needed to estimate distribution of radioisotopes causing the SDDR. Biasing the neutron MC calculation using an importance function is not simple because it is difficult to explicitly express the response function, which depends on subsequent computational steps. Furthermore, the typical SDDR calculations do not consider how uncertainties in MC neutron calculation impact SDDR uncertainty, even though MC neutron calculation uncertainties usually dominate SDDR uncertainty.

  17. Posting Date: 3/15/2016 Posting Close Date: 4

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

    3/15/2016 Posting Close Date: 4 th QTR 2016 North American Industry Classification System (NAICS) code for the request: 236210 Estimated Subcontract/PO Value: TBD Estimated Period of Performance: TBD Estimated RFP/RFQ Release Date: 4 th QTR 2016 Estimated Award Date: TBD Competition Type: TBD Buyer Contact Email: shanej@lanl.gov Title: Transuranic (TRU) Liquid Waste (TLW) Project Description of Product or Service Required The Transuranic (TRU) Liquid Waste (TLW) Project is a congressionally

  18. Posting Date: July 16, 2015 Posting Close Date: TBD

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

    July 16, 2015 Posting Close Date: TBD North American Industry Classification System (NAICS) code for the request: 812332 Estimated Subcontract/PO Value TBD Estimated Period of Performance 8-03-15 Estimated RFP/RFQ Release Date: TBD Estimated Award Date: FY 2018 Competition Type: Open Buyer Contact Email: pbeauparlant@lanl.gov Title: Radioactive Laundry and Respirator Services Description of Product or Service Required Radioactive Laundry and Respirator Services * Current forecasted bid

  19. Posting Date: July 16, 2015 Posting Close Date: TBD

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

    July 16, 2015 Posting Close Date: TBD North American Industry Classification System (NAICS) code for the request: 812332 Estimated SubcontractPO Value TBD Estimated Period of...

  20. Posting Date: 28 May, 2015 Posting Close Date: TBD

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

    7 Estimated Award Date: TBD Competition Type: TBD Buyer Contact Email: Itmartinez@lanl.gov Title: QA Support Description of Product or Service Required QA Support (Current...

  1. Dates Fact Sheet.cdr

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

    The DATES monitoring platform uses multiple algorithms to examine packet headers, including a Snort sensor enhanced with a SCADA-aware rule set, stateful protocol analysis, and a ...

  2. Property:Deployment Date | Open Energy Information

    Open Energy Info (EERE)

    Deployment Date Jump to: navigation, search Property Name Deployment Date Property Type String Retrieved from "http:en.openei.orgwindex.php?titleProperty:DeploymentDate&oldid...

  3. Property:Achievement Date | Open Energy Information

    Open Energy Info (EERE)

    Achievement Date Jump to: navigation, search Property Name Achievement Date Property Type String Retrieved from "http:en.openei.orgwindex.php?titleProperty:AchievementDate&ol...

  4. Posting Date: 28 May, 2015 Posting Close Date: TBD

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

    300M Estimated Period of Performance: 5 Years Estimated RFP/RFQ Release Date: 2 nd QTR 2018 Estimated Award Date: TBD Competition Type: TBD Buyer Contact Email: pia@lanl.gov Title: Staff Augmentation Services Description of Product or Service Required Staff Augmentation Services (Current subcontract expires 2019) * Current forecasted bid opportunities are subject to change or cancellation due to scope, mission, or funding requirements. * Some procurements are reserved for small businesses. Note

  5. Posting Date: 28 May, 2015 Posting Close Date: TBD

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

    700K Estimated Period of Performance: TBD Estimated RFP/RFQ Release Date: FY 2018 Estimated Award Date: TBD Competition Type: TBD Buyer Contact Email: m_armijo@lanl.gov Title: Poly Com Phones Description of Product or Service Required Poly Com Phones (Current subcontracts expires 2019) * Current forecasted bid opportunities are subject to change or cancellation due to scope, mission, or funding requirements. * Some procurements are reserved for small businesses. Note the competition type on the

  6. Shutdown Dose Rate Analysis Using the Multi-Step CADIS Method

    SciTech Connect (OSTI)

    Ibrahim, Ahmad M.; Peplow, Douglas E.; Peterson, Joshua L.; Grove, Robert E.

    2015-01-01

    The Multi-Step Consistent Adjoint Driven Importance Sampling (MS-CADIS) hybrid Monte Carlo (MC)/deterministic radiation transport method was proposed to speed up the shutdown dose rate (SDDR) neutron MC calculation using an importance function that represents the neutron importance to the final SDDR. This work applied the MS-CADIS method to the ITER SDDR benchmark problem. The MS-CADIS method was also used to calculate the SDDR uncertainty resulting from uncertainties in the MC neutron calculation and to determine the degree of undersampling in SDDR calculations because of the limited ability of the MC method to tally detailed spatial and energy distributions. The analysis that used the ITER benchmark problem compared the efficiency of the MS-CADIS method to the traditional approach of using global MC variance reduction techniques for speeding up SDDR neutron MC calculation. Compared to the standard Forward-Weighted-CADIS (FW-CADIS) method, the MS-CADIS method increased the efficiency of the SDDR neutron MC calculation by 69%. The MS-CADIS method also increased the fraction of nonzero scoring mesh tally elements in the space-energy regions of high importance to the final SDDR.

  7. Shutdown Dose Rate Analysis Using the Multi-Step CADIS Method

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

    Ibrahim, Ahmad M.; Peplow, Douglas E.; Peterson, Joshua L.; Grove, Robert E.

    2015-01-01

    The Multi-Step Consistent Adjoint Driven Importance Sampling (MS-CADIS) hybrid Monte Carlo (MC)/deterministic radiation transport method was proposed to speed up the shutdown dose rate (SDDR) neutron MC calculation using an importance function that represents the neutron importance to the final SDDR. This work applied the MS-CADIS method to the ITER SDDR benchmark problem. The MS-CADIS method was also used to calculate the SDDR uncertainty resulting from uncertainties in the MC neutron calculation and to determine the degree of undersampling in SDDR calculations because of the limited ability of the MC method to tally detailed spatial and energy distributions. The analysismore » that used the ITER benchmark problem compared the efficiency of the MS-CADIS method to the traditional approach of using global MC variance reduction techniques for speeding up SDDR neutron MC calculation. Compared to the standard Forward-Weighted-CADIS (FW-CADIS) method, the MS-CADIS method increased the efficiency of the SDDR neutron MC calculation by 69%. The MS-CADIS method also increased the fraction of nonzero scoring mesh tally elements in the space-energy regions of high importance to the final SDDR.« less

  8. Date

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

    ... We will provide a letter template to you. Sandia will treat all aspects of this engagement as privileged and confidential. We will not disclose any engagement-related information ...

  9. DATE

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

    of Impact The action consists of purchasing equipment to be used in research and teaching. The action would not create additional environmental impacts above those already...

  10. DATE

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

    CAES-061 292012 Rev. 04 CAES Microscopy & Characterization Suite (MaCS) Service Request Form Page 1 of 2 Contact Information: Requestor Name: *Researcher Name: Requestor Email:...

  11. DATE

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

    ... Transuranic elements are accumulated in the electrorefining salt and extracted as a uraniumtransuranicrare earth product using a liquid cadmium cathode (LCC) in order to acquire ...

  12. DATE:

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

    For questions concerning this policy flash, contact Kevin M. Smith at (202) 287-1614 or at Kevin.M.Smith@hq.doe.gov. Contracting Officers should contact their field counsel, the ...

  13. DATE

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

    with a pressure relief valve that discharges to the gas flare or fume hood exhaust. ... from the hydrogen line pressure relief valve to prevent uncontrolled accumulation or ...

  14. DATE

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

    Air System Drain Line Modification and Valve Replacement SECTION B. Project ... on M-6, M-8 and M-9; install a new check valve in the compressed air system auxiliary ...

  15. Date:

    Office of Legacy Management (LM)

    Tetra Tech developed design flow rates from these rainfall depths and evaluated the ... Design precipitation depths of 3.7 and 5.5 inches yielded runoff depths of 2.3 and 3.9 ...

  16. DATE

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

    The cooling unit will be specified to meet ASHRAE 90.1, "Energy Standard for Buildings Except Low-Rise Residential Buildings" or "DOE Energy Star" as appropriate. SECTION D. ...

  17. DATE

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

    4 SECTION A. Project Title: In situ Raman Spectroscopy to Enhance Nuclear Materials Research and Education - University of Nevada Reno SECTION B. Project Description The University ...

  18. DATE

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

    removed would be evaluated (mercury switches) and managed appropriately. Polychlorinated Biphenyls (PCBs) may be encountered in items painted prior to 1980. All waste would be ...

  19. DATE

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

    ... Any switches that are removed would be evaluated (mercury switches) and managed appropriately. Polychlorinated Biphenyls (PCBs) and lead may be encountered in items painted prior ...

  20. DATE:

    Office of Legacy Management (LM)

    Ohio TO: W. Seay, DOE Oak Ridge Field Office The former Associate Aircraft Tool and Manufacturing, Inc., site at 3660 Dixie Highway, Fairfield, Ohio, is designated for remedial...

  1. DATE

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

    successfully form dense U 3 Si 2 pellets with a density greater than 94% of theoretical. ... apparatus into dense ceramic pellets for characterization by spark plasma sintering. ...

  2. DATE

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

    A container(s) of hazardous debris andor RLS is placed inside the macrobagliner system and void space filler (e.g. vermiculite, foam pellets, etc.) is added to fill the package ...

  3. DATE:

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

    has been revised. The subject form has been posted on the DOE Financial Assistance web page on the Recipients Page under the Financial Assistance Forms and Information for...

  4. DATE

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    water system and will be coated on both exterior and interior surfaces to prevent corrosion. All valves and lines will be closed off to the construction area until the new tank...

  5. DATE

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    09 SECTION A. Project Title: High Temperature Melt Solution Calorimeter: The Thermodynamic Characterization of Oxides n Nuclear Energy - Clemson University SECTION B. Project...

  6. DATE

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    The craftsmen also need another wash sink in the East Bay. The current method of ... The East Bay will require a new power panel with power run from the main distribution ...

  7. DATE

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    generate high fidelity thermal stratification and flow field data under various geometric and physical conditions for scaled modes of outlet plena in sodium-cooled fast reactors. ...

  8. DATE

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    CX Posting No.: DOE-ID-INL-10-008 SECTION A. Project Title: Maintenance and Modification ... provide corrective and preventative maintenance that would prevent or minimize future ...

  9. DATE

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    SECTION A. Project Title: ICP Routine Maintenance SECTION B. Project Description The ... types of actions, such as routine maintenance, minor modifications, and custodial ...

  10. Dated:

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    CERTIFICATE OF SERVICE I hereby certify that a copy of the STIPULATED JOINT MOTION TO STAY THE SCHEDULING ORDER has been sent electronically to the following on May 12, 2015:...

  11. DATE

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    This security building is located on Taylor Blvd approximately one mile south of the Materials and Fuels Complex (MFC) and already houses a Vehicle Explosives Detection System...

  12. DATE

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    6-002 SECTION A. Project Title: Experimental Verification of Post-Accident iPWR Aerosol Behavior - Electric Power Research Institute, Inc. SECTION B. Project Description EPRI ...

  13. DATE

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    42 SECTION A. Project Title: Innovative Manufacturing Process for Improving the Erosion/Corrosion Resistance of Power Plant Components via Powder Metallurgy & Hot Isostatic Processing Methods - Electric Power Research Institute SECTION B. Project Description The objective of this project is to conduct the necessary design, processing, manufacturing, and validation studies to assess powder metallurgy/hot isostatic processing (PM/HIP) as a method to produce very large near-net shaped (NNS)

  14. DATE

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    2 SECTION A. Project Title: Development of a Research and Education Facility for Evaluation of Environmental Degradation of Advanced Nuclear Materials in Simulated LWR Conditions - University of Idaho SECTION B. Project Description The University of Idaho proposes to a) upgrade the existing static autoclave system in order to simulate the light water reactor conditions without contaminating the high temperature waster with corrosion products; b) install a rotating a cylinder system in the

  15. DATE

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    5 SECTION A. Project Title: Nuclear Materials Science and Instrumentation Research Infrastructure Upgrade at Pennsylvania State University SECTION B. Project Description Pennsylvania State University proposes to purchase and install an inductively coupled plasma - atomic emission spectrometer (ICP- AES), glass melting furnace and crucible, and data acquisition system for use in research and education. SECTION C. Environmental Aspects / Potential Sources of Impact Chemical Use/Storage / Chemical

  16. DATE

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    8 SECTION A. Project Title: Integrated Approach to Fluoride High Temperature Reactor (FHR) Technology and Licensing Challenges - Georgia Tech SECTION B. Project Description Georgia Tech, in collaboration with Ohio State University, Texas A&M, Texas A&M - Kingsville, Oak Ridge National Laboratory and several industry and international partners, proposes to follow an integrated approach to address several key technology gaps associated with fluoride high temperature reactors, thereby

  17. DATE

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    4 SECTION A. Project Title: Solving Critical Challenges to Enable the Xe-100 Pebble Bed Advanced Reactor Concept - X Energy, LLC SECTION B. Project Description X Energy, in collaboration with BWXT Nuclear Energy, Inc. (BWXT), Oak Ridge National Laboratory (ORNL), Idaho National Laboratory (INL), and Oregon State University (OSU), proposes to leverage prior and current DOE programs and previous Xe-100 design investments to further key pebble-bed high temperature gas-cooled reactor (HTGR)

  18. DATE

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    5 SECTION A. Project Title: DOE-EM Traineeship in Robotics - Carnegie Mellon University SECTION B. Project Description Carnegie Mellon University (CMU) proposes to develop an Environmental Management (EM) Traineeship in robotics. The traineeship will build on the existing core robotics curricula while introducing specialized topics that ensure a thorough understanding of EM-relevant concerns. The proposed program will also incorporate supervised research opportunities with CMU faculty advisors

  19. DATE

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    07 SECTION A. Project Title: Experimentally Validated Computational Modeling of Creep and Creep-Cracking for Nuclear Concrete Structures - Texas Engineering Experiment Station (TEES - TAMU) SECTION B. Project Description Texas A&M University proposes to 1) devise new, 3D concrete material constitutive models base on 3D creep and cracking experiments, 2) establish an improved large-scale structural modeling approach that considers full 3D stress fields rather than plane stress as has been

  20. DATE

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    2 SECTION A. Project Title: CFA-16-12043: Using Radioiodine Speciation to Address Environmental Remediation and Waste Stream Sequestration Problems at the Fukushima Daiichi Nuclear Power Plant and a DOE Site, MS-EM-1: Radioactive Waste Management - Texas A&M University - Galveston SECTION B. Project Description Texas A&M University - Galveston proposes to 1) measure radioiodine speciation to provide information that will be used in the development of species-specific stabilization

  1. DATE

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    4 SECTION A. Project Title: CFA-16-10285: Tribological Damage Mechanisms from Experiments and Validated Simulations of Alloy 800H and Inconel 617 in a Simulated HTGR/VHTR Helium Environment - Purdue University SECTION B. Project Description Purdue University proposes to perform a series of tribological experiments on Alloy 800H and Inconel 617 in a simulated He environment with controlled concentrations of gaseous species follow by microstructure characterization using electron microscopy,

  2. DATE

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

    5 SECTION A. Project Title: Integrated Computational Materials Engineering (ICME) and In-site Process Monitoring for Rapid Qualification of Components Made by Laser-Based Powder Bed Additive Manufacturing (AM) Processes for Nuclear Structural and Pressure Boundary Applications - Electric Power Research Institute SECTION B. Project Description The Electric Power Research Institute (EPRI) proposes to develop an innovative qualification strategy for complex nuclear components produced by laser

  3. DATE

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    6 SECTION A. Project Title: Online Monitoring System for Concrete Structures Affected by Alkali-Silica Reaction (ASR) - University of Nebraska, Lincoln SECTION B. Project Description The University of Nebraska, in collaboration with the University of Alabama, proposes to develop and employ two highly sensitive active and passive stress wave sensing techniques and advanced signal processing algorithms to monitor and quantify alkali-silica reaction-induced microcracking damage in concrete. SECTION

  4. DATE

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

    8 SECTION A. Project Title: Feasibility of Combined Ion-Neutron Irradiation for Accessing High Dose Levels - University of Michigan SECTION B. Project Description The University of Michigan, in collaboration with the Oak Ridge National Laboratory (ORNL), proposes to assess the feasibility of re-irradiating existing neutron irradiated alloys 304SS and 316SS to high dose levels using ion irradiation, for the purpose of achieving microstructures that represent those from reactor irradiation to

  5. DATE

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    19 SECTION A. Project Title: Validation of RELAP-7 for forced convection and natural circulation reactor flows - University of Illinois at Urbana-Champaign SECTION B. Project Description The University of Illinois at Urbana-Champaign proposes to aid in the development of RELAP-7 through required experimental and computational efforts. The validation of the two-phase modeling capability of RELAP-7 will be accomplished through a series of tasks which include synthesis of existing forced convective

  6. DATE

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

    0 SECTION A. Project Title: Overcoming Kinetic Barriers to Actinide Recovery in ALSEP - Colorado School of Mines SECTION B. Project Description The Colorado School of Mines, in collaboration with the Argonne National Laboratory, proposes to test the hypothesis that slow kinetics in the solvent separation process ALSEP and its related separation systems, for the recovery of Am from the fission product lanthanide elements, originate in the poor ability of the aqueous complexants to penetrate and

  7. DATE

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    2 SECTION A. Project Title: Immobilization of High-Level Waste Salt in Dechlorinated Zeolite Waste Forms - University of Utah SECTION B. Project Description The University of Utah, in collaboration with Idaho National Laboratory, proposes to evaluate the main challenges associated with the disposal of electrorefiner salt: maximization of fission products in a final waste form and the associated processing costs. The proposed research will focus on two main objectives to overcome these process-

  8. DATE

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    3 SECTION A. Project Title: ASME Code Application of the Compact Heat Exchanger for High Temperature Nuclear Service - North Carolina State University SECTION B. Project Description North Carolina State University proposes to characterize the high temperature materials properties of a diffusion welded laminated structure and to develop the ASME Code methodologies for preventing failure of a printed channel and hybrid compact heat exchangers under sustained and cyclic pressure and thermal loading

  9. DATE

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

    30 SECTION A. Project Title: Additive Manufacturing of Functional Materials and Sensor Devices for Nuclear Energy Applications - Boise State University SECTION B. Project Description Boise State University proposes to procure an aerosol jet printer and establish additive manufacturing capability to accelerate research and development of integrated sensor systems for nuclear energy applications. Procuring a versatile aerosol jet printer that can directly print functional semiconductors, metals,

  10. DATE

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

    2 SECTION A. Project Title: An Integrated Multiscale Experimental-Numerical Analysis on Reconsolidation of Salt-Clay Mixture for Disposal of Heat-Generating Waste - Columbia University SECTION B. Project Description Columbia University, in collaboration with Sandia National Laboratory, proposes to improve the understanding of the thermal- hydrological-mechanical-chemical (THMC) coupling effect on the reconsolidation of granular salt-clay mixture used for the seal systems of shafts and drifts in

  11. DATE

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    4 SECTION A. Project Title: Integration of Microwave Readout into Nuclear Process Monitoring - University of Colorado, Boulder SECTION B. Project Description The University of Colorado, in collaboration with Los Alamos National Laboratory and Savannah River National Laboratory, proposes to demonstrate that high-resolution γ-ray spectroscopy, based on emerging microcalorimeter sensors, can determine elemental and isotopic fractions with accuracy comparable to much slower mass spectrometry and

  12. DATE

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    5 SECTION A. Project Title: Calorimeter for Nuclear Energy Teaching and Research - Washington State University SECTION B. Project Description Washington State University proposes to purchase and setup a new calorimeter for use with radioactive material at the university. The project would improve the capability of the university's Department of Chemistry for nuclear-related teaching and research. SECTION C. Environmental Aspects / Potential Sources of Impact The action consists of purchasing

  13. DATE

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    6 SECTION A. Project Title: Fission Product Transport in TRISO Fuel - University of Michigan SECTION B. Project Description The University of Michigan, in collaboration with Idaho National Laboragtory, proposes to measure diffusion coefficients of fission products in SiC under thermal and irradiation conditions, as well as, synergistic effects of radiation damage, and fission products behavior at the IPyC/SiC interface. The project will use a multi-layered diffusion couple developed at a NSUF

  14. DATE

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    7 SECTION A. Project Title: Development of a Comprehensive Two-phase Flow Database for the Validation of NEK-2P - Virginia Tech SECTION B. Project Description Virginia Polytechnic Institute and State University, in collaboration with Ohio State University and Argonne National Laboratory, proposes to perform detailed uncertainty quantification to determine the applicable ranges and associated measurement uncertainties in simulated two-phase boiling flows. The best combination of these techniques

  15. DATE

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    8 SECTION A. Project Title: Feasibility of Combined Ion-Neutron Irradiation for Accessing High Dose Levels - Florida International University SECTION B. Project Description Florida International University, in collaboration with the Idaho National Laboratory (INL), proposes to achieve the separation of Am from lanthanides by electrochemical oxidation of Am(III) to its higher oxidation states, Am(V) and AM(VI), through the design, and testing of new high surface area electrodes and porous sorbent

  16. DATE

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

    40 SECTION A. Project Title: Quantifying Properties for a Mechanistic, Predictive Understanding of Aqeous Impact on Ageing of Medium and Low Voltage AC and DC Cabling in Nuclear Power Plants - University of Minnesota, Duluth SECTION B. Project Description The University of Minnesota, Duluth proposes to develop a mechanistic, predictive model for medium and low voltage cable failure based on the primary environmental degradation parameters of aqueous immersion time, temperature, and the oxidation

  17. DATE

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

    1 SECTION A. Project Title: Development of Reactor Thermal-Hydraulics and Safety Research Facilities at Kansas State University SECTION B. Project Description Kansas State University proposes to purchase advanced instrumentation for thermalhydraulics and reactor safety-related fundamental experiments. This instrumentation includes a high-speed multispectral infrared imaging system, a high-speed imaging system capable of recording up to 500,000 frames per second for flow visualization, a laser

  18. DATE

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    3 SECTION A. Project Title: An Experimental Study of Design and Performance for the Water-based Reactor Cavity Cooling System - Texas A&M University SECTION B. Project Description Texas A&M University, in collaboration with the University of Wisconsin and Ultra Safe Nuclear Corporation, proposes to extend and enhance the experimental tests previously conducted using the existing water-cooled Reactor Cavity Cooling System (RCCS) in close collaboration with the water-cooled research team

  19. DATE

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    5 SECTION A. Project Title: CFD and System Code Benchmark Data for Plenum-to-Plenum Flow Under Natural Mixed and Forced Circulation Conditions SECTION B. Project Description The project will conduct computer modeling, as well as experimental initiatives. The experimental initiatives include modifications to the current Utah State University experimental wind tunnel to evaluate flows and buoyancy-driven phenomena present in Very High Temperature Reactors during Loss of flow accident conditions.

  20. DATE

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    8 SECTION A. Project Title: Earth Abundant High Temperature Materials for Radiological Power Conversion System SECTION B. Project Description The project consists of performing research and development using earth abundant elements to increase efficiencies to 20-30% through solid state alloying and composites of high temperature materials, thereby improving thermoelectric generator system performance without the need to invest in a single-purpose supply chain. Earth abundant high temperature

  1. DATE

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    49 SECTION A. Project Title: Tribological Behavior of Structural Materials in High Temperature Helium Gas-Cooled Reactor Environments SECTION B. Project Description The project will investigate the wear mechanisms of surface treatments for alloys 800H and 617 will be investigated to: (i) mitigate tribological damage in High Temperature Gas Reactor (HTGR) environments, (ii) minimize sensitivity of corrosion to various impurity regimes and provide greater predictability in wear behavior, (iii)

  2. DATE

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    1 SECTION A. Project Title: Effect of Gamma Irradiation on the Microstructure and Mechanical Properties of Nano-modified Concrete - Vanderbilt University SECTION B. Project Description Vanderbilt University, in collaboration with Oak Ridge National Laboratory, proposes to perform gamma irradiation of nano-modified concrete and appropriate control reference samples that are also relevant to current and historic concrete mixes. The research plan will consist of multiscale chemical and mechanical

  3. DATE

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    3 SECTION A. Project Title: CFA-16-10885: Turbulent MHD flow modeling in annular linear induction pumps with validation experiments SECTION B. Project Description The scope of work consists of modeling and constructing an experimental flow loop facility and diagnostic tools to benchmark to refine and validate the predictions of computational fluid mechanics analyses. This task also involves fabrication of a modular annular linear induction pump (ALIP) pump that, combined with the added

  4. DATE

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    4 SECTION A. Project Title: Thermal Hydraulic & Structural Testing and Modeling of Compact diffusion-bonded heat exchanges for Supercritical CO2 Brayton Cycles SECTION B. Project Description The primary focus of this research proposal would be on validating and verifying the structural integrity of continuous channel -type PCHEs such as the Heatric zig/zag or Marbond (otherwise known as Shimtec) continuous micro-channel heat exchanger opposed to fin-type geometries. The proposed research

  5. DATE

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    5 SECTION A. Project Title: Enhancing Irradiation Tolerance of Steels Via Nanostructuring by Innovative Manufacturing Techniques - Idaho State University SECTION B. Project Description Idaho State University, in collaboration with Idaho National Laboratory, proposes to enhance the fundamental understanding of irradiation effects in ultrafine-grained or nanocrystalline steels produced by equal-channel angular pressing (ECAP) or high-pressure torsion (HPT), and to assess the potential application

  6. DATE

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    7 SECTION A. Project Title: A Science Based Approach for Selecting Dopants in FCCI-Resistant Metallic Fuel Systems SECTION B. Project Description The goal of this project is to identify minor alloying additions (dopants) for minimizing or eliminating the effect of fuel cladding chemical interactions (FCCI) in fast reactor metallic fuels. The proposed program combines the following research tasks: i) Selection of dopant elements based on using electronic structure calculated thermokinetic and

  7. DATE

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    8 SECTION A. Project Title: Versatile D-T Neutron-Generation System for Fast-Neutron Research and Education - Pennsylvania State University SECTION B. Project Description Pennsylvania State University proposes to acquire an Adelphi dual-tube 14-MeV Deuterium-Tritium (D-T) neutron-generation system. One tube has a neutron output of 10 8 n/sec, and the other tube has a neutron output of 10 10 n/sec. the lower-neutron-output part of the system will provide a capability to accurately detect the

  8. DATE

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

    0 SECTION A. Project Title: Self-powered Wireless Through-wall Data Communication for Nuclear Environments SECTION B. Project Description The proposed action consists of developing and demonstrating an enabling technology for the data communications for nuclear reactors and fuel cycle facilities using radiation and thermal energy harvesters, through-wall ultrasound communication, and harsh environment electronics. Specifically, the consist of three actions: (1) Directly harvest electrical energy

  9. DATE

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

    2 SECTION A. Project Title: Understanding fundamental science governing the development and performance of nuclear waste glasses SECTION B. Project Description This proposal aims to combine the strengths of experimental and computational materials science to address four difficult technical challenges related to development and performance of glass based radioactive waste forms. The project consists of four tasks: 1. Understanding the fundamental science governing the nucleation and growth of

  10. DATE

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

    3 SECTION A. Project Title: Microstructure, Thermal, and Mechanical Properties Relationships in U and UZr Alloys SECTION B. Project Description The proposed research will use the state-of-the-art, 3D, synchrotron-based characterization techniques, novel techniques that couple thermal and mechanical properties, existing experimental facilities, and complementary multiscale modeling to evaluate microstructure-properties relationships (both thermal and mechanical) in U and UZr alloys that have been

  11. DATE

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

    5 SECTION A. Project Title: Cask Mis-Loads Evaluation Techniques SECTION B. Project Description The main objective of this project is to develop a probabilistically-informed methodology, which involves innovative non- destructive evaluation (NDE) techniques, to determine the extent of potential damage or degradation of internal components of used nuclear fuel canisters/casks during normal conditions of transport or Hypothetical accident conditions. The University of Houston will use NDE based on

  12. DATE

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    7 SECTION A. Project Title: Research and teaching equipment for nuclear materials characterization SECTION B. Project Description The proposal to upgrade the UC Berkeley teaching and research laboratory's to enhance the understanding of mechanical and physical properties of nuclear materials on all length scales. Purchasing state-of-the-art equipment dedicate to be used on active materials allows to investigate reactor and ion beam irradiated materials to enhance accelerated materials testing

  13. DATE

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    1 SECTION A. Project Title: Experimental and Computational Studies of NEAMS Pebble Bed Reactors - Texas A&M University SECTION B. Project Description Texas A&M University proposes to perform a coordinated experimental and computational effort to quantitatively map the full-field 3-D velocity and temperature fields in the interstitial spaces within a pebble bed. The project will measure in-situ velocity and temperature distributions within a pebble bed flow system using state-of-the-art

  14. DATE

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

    2 SECTION A. Project Title: Mobile Manipulation and Survey System for H-Canyon and Other Applications Across the DOE Complex - University of Texas SECTION B. Project Description The University of Texas, in collaboration with the University of Florida, Florida International University, AREVA, and Savannah River National Laboratory, proposes to develop a hybrid mobile platform capable of maneuvering using wheels, treads or articulated legs to perform inspections and collect data in the H-Canyon

  15. DATE

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    3 SECTION A. Project Title: Upgrade of the MIT Research Reactor's Post Irradiation Examination (PIE) Capabilities - Massachusetts Institute of Technology SECTION B. Project Description The Massachusetts Institute of Technology proposes to purchase and install sample sectioning and polishing equipment and optical and electon microscopes to improve the MIT Research Reactor post-irradiation examination facilities. This will provide for preparation and initial characterization of activated materials

  16. DATE

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    4 SECTION A. Project Title: Understand the Phase Transformation of Thermally Aged and Neutron Irradiated Duplex Stainless Steels Used in LWRs - University of Florida SECTION B. Project Description The University of Florida, in collaboration with Argonne National Laboratory (ANL), proposes to use the capability of the high energy X-ray MRCAT facility at ANL, including X-ray diffraction (XRD), Extended X-ray Absorption Fine Structure Specroscopy (EXAFS) and in-situ tensile testing with wide angle

  17. DATE

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

    6 SECTION A. Project Title: Two-Phase Flow Facility for Dynamic Characterization of Thermal Hydraulics in Light Water Reactors - Texas A&M University SECTION B. Project Description Texas A&M University proposes to construct an experimental facility that will enable single and two-phase flow experimental data to be acquired in a 3x3 fuel rod array under a wide range of steady-state and transient conditions. The neutronic behavior of a light water reactor will be simulated in real-time and

  18. DATE

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

    6-007 SECTION A. Project Title: INTEC - INTEC - Transfer ATR Fuel From Wet (CPP-666) to Dry (CPP-603) Irradiated Fuel Storage Facility Fuel Conditioning Station SECTION B. Project Description The purpose of this project is to transfer approximately 1,000 ATR fuel elements from wet fuel storage located at the CPP-666 Fuel Storage Area (FSA) at the Idaho Nuclear Technology and Engineering Center (INTEC) to the dry fuel storage located within CPP-603B, Irradiated Fuels Storage Facility (IFSF). The

  19. DATE

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    EC Document No.: DOE-ID-INL-09-002 SECTION A. Project Title: Smoking Shelters SECTION B. Project Description. Install up to three prefabricated outdoor shelters for smokers. Design and install a shelter base so that shelters can be movable. The base shall be designed to prevent shelters from moving or tipping over due to high winds. Specific location for shelters is to be determined, but the shelter bases will be placed atop existing concrete or asphalt such that no subsurface soil disturbance

  20. DATE

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    09-003 SECTION A. Project Title: Removal of Central Facilities Area (CFA)-661 Interior Walls and Mezzanine. SECTION B. Project Description The initial action to be covered under this Environmental Checklist will be removal of the mezzanines from CFA-661 to provide for material storage and work space for the National and Homeland Security (N&HS) Wireless Test Bed project. More specifically, this involves storage of electronic equipment, antennas and antenna masts, personnel supplies, and a

  1. DATE

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    2 __________________________ 1 DOE's strategic plans included the Nuclear Energy Research and Development Roadmap" (2010 Predecisional draft) and reports such as "Facilities for the Future of Nuclear Energy Research: A Twenty-year Outlook". SECTION A. Project Title: Materials and Fuel Complex (MFC) Infrastructure Upgrades: Sewage Lagoons Upgrades SECTION B. Project Description: MFC Infrastructure Upgrades - MFC Sewage Lagoon Upgrades This EC focuses on upgrades to the existing 2.4

  2. DATE

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    4-017 SECTION A. Project Title: Test Reactor Area (TRA)-653 Conference Room Modifications SECTION B. Project Description: The Advanced Test Reactor (ATR) Maintenance Shop, building Test Reactor Area (TRA)-653, located at the ATR Complex, has an upstairs conference room capable of being used as one large conference room or can be split into two conference rooms by a sliding curtain divider. The current configuration causes meeting interruptions due to the one available door limiting personnel

  3. DATE

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    9 SECTION A. Project Title: INTEC - Upgrade of the Emergency Communication System SECTION B. Project Description The proposed action will design, procure, and install an upgrade to the emergency communication system (ECS) for the Idaho Nuclear Technology and Engineering Center (INTEC). The existing system does not meet the new Life Safety codes and parts are no longer available for the antiquated system. Approximately 39 buildings will be included in the system modification and upgrade of ECS

  4. DATE:

    Office of Environmental Management (EM)

    Portaledge, March 2010 | Department of Energy Audit and Attack Detection Toolkit: Bandolier and Portaledge, March 2010 Cyber Security Audit and Attack Detection Toolkit: Bandolier and Portaledge, March 2010 This project of the cyber security audit and attack detection toolkit will employ Bandolier Audit Files for optimizing security configurations and the Portaledge event detection capability for energy control systems. By building configuration audit and attack detection capabilities into

  5. DATE

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    testing, high efficiency particulate air filter testing and certification, stress tests (such as "burn-in" testing of electrical components and leak testing), and...

  6. DATE

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    action will abandon inactive wells and injection wells at the Idaho National Laboratory (INL) Site. Wells and injection wells will be abandoned as per MCP-1442, MCP-3480 and ...

  7. DATE

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    Welding is done in another portion of the building (weld shop, insignificant activity) served by a different ventilation system. Certified Refrigeration Technicians will use ...

  8. DATE

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    For additional information, contact Brenda Pace at 526-0916 or Hollie Gilbert at 526-2189. Interaction with WildlifeHabitat - Activities occurring off-road after May 1 have the...

  9. DATE

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    historical significance must receive a clearance before beginning the activity-see http:... historical significance must receive a clearance before beginning the activity-see http:...

  10. DATE

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

    include: 1. Physically relocate the RDM cabinet from CPP-684 to CPP-663. 2. Refurbish trailer TR-81 to accommodate wastewater laboratory activities currently being performed...