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...

  1. DATE:

    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

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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,

  10. 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 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. 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...

  15. 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 ...

  16. 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 ...

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    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 ...

  18. 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"...

  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. ...

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    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. 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.

  6. 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.

  7. 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.

  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

    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.

  15. 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

  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. 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

  19. 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.

  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

    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

  7. 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.

  8. 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 ...

  9. 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 ...

  10. 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 ...

  11. DATE

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    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. ...

  12. 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 ...

  13. 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 ...

  14. 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 ...

  15. 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...

  16. 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. ...

  17. 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 ...

  18. 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...

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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...

  20. 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...

  1. 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 ...

  2. 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. ...

  3. 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 ...

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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 ...

  5. 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:...

  6. 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...

  7. DATE

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

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

  8. 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 ...

  9. DATE

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

    Manufacturability of Oxide Dispersion Strengthened Structural Materials for Nuclear Reactor Applications - Northwestern University SECTION B. Project Description Northwestern ...

  10. DATE

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

    WAI will provide ecological support to DOE-ID for land and wildlife management issues. WAI ... WaterWell Use - Use of waterwell is concurrent with the Experimental Field Station. Work ...

  11. DATE

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

    a civilian reactor station, the Light Water Breeder Reactor for the Shippingport Station. ... DOE-ID NEPA CX DETERMINATION IDAHO NATIONAL LABORATORY Page 2 of 3 CX Posting No.: ...

  12. DATE

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    at Raft River by the United States Geological Survey (USGS) in non-INL related work ... INL will collect samples of the tracers prior to injection to verify concentration, ...

  13. DATE:

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

    Corporations Section 743 Any Payment for the Election for a Federal Office or to a Political Committee Section 3003 Reporting on Conference Spending 2 The FAL addresses the ...

  14. DATE

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

    Team. The subcontractor will be required to have spill control equipment on site. A propane tank that will be relocated from CFA-666 to CFA-661 will have it's location...

  15. DATE

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

    environments. SECTION C. Environmental Aspects Potential Sources of Impact The action consists of purchasing equipment to be used in research and teaching. The action would...

  16. DATE

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

    evaluate cladding materials that may be used in more advanced accident tolerant fuels. ... consists of research and development on new cladding materials for accident tolerant fuels

  17. DATE

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

    the behavior and strength of modular steel-plate composite (SC) slabs and floor ... of Impact The research would involve assessing modular steel-plate composite performance. ...

  18. 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:...

  19. 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...

  20. DATE

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

    to purchase and install the equipment necessary to develop and benchmark a non-invasive velocity measurement technique for salt based on short-lived activation products...

  1. DATE

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

    The ATR building has a 40-ton bridge and trolley crane used to lift ATR experiment casks ... The largest cask currently handled by the 40-ton reactor-building crane is the O. G. ...

  2. DATE

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

    structure, transfer car, and overhead crane in the south corridor of building CPP-603 ... of the facility structure and existing crane rails for installation of two new 75 Ton ...

  3. DATE

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

    Testing & Molten Chloride Fast Reactor Development - Southern Company Services, Inc. ... readiness of the Molten Chloride Fast Reactor (MCFR) technology under development by ...

  4. DATE

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

    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)

  5. DATE

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

    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

  6. DATE

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

    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

  7. DATE

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

    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

  8. DATE

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

    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)

  9. DATE

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

    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

  10. DATE

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

    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

  11. DATE

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

    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

  12. DATE

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

    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,

  13. 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

  14. DATE

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

    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

  15. 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

  16. DATE

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

    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

  17. 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

  18. DATE

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

    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-

  19. DATE

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

    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

  20. 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,

  1. 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

  2. DATE

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

    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

  3. DATE

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

    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

  4. DATE

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

    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

  5. DATE

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

    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

  6. 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 - 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

  7. 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

  8. 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

  9. DATE

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

    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

  10. DATE

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

    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.

  11. DATE

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

    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

  12. DATE

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

    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)

  13. DATE

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

    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

  14. DATE

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

    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

  15. DATE

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

    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

  16. DATE

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

    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

  17. DATE

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

    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

  18. DATE

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

    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

  19. 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

  20. 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

  1. 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

  2. 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

  3. DATE

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

    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

  4. DATE

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

    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

  5. 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

  6. DATE

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

    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

  7. DATE

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

    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

  8. 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

  9. 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

  10. DATE

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

    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

  11. DATE

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

    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

  12. DATE

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

    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

  13. 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

  14. DATE

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

    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

  15. 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

  16. Date

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    ... 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 ...

  17. 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...

  18. DATE

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    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:...

  19. DATE

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

    ... by ETI-039 1RQURDG (QJLQHV WKH JHQHUDWRUV FDQ EH RSHUDWHG XS WR PRQWKV RU OHVV UHJDUGOHVV RI VLH DW WKH project location without being subject to air permitting requirements. ...

  20. DATE

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

    hazardous substances, pollutants, contaminants, or CERCLA-excluded petroleum and natural gas products that pre-exist in the environment such that there would be uncontrolled...

  1. 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 ...

  2. DATE:

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

    and Financial Assistance Policy Division Office of Policy Office of Acquisition and Project Management SUBJECT: Implementation of Division F, Title I, Title II, and Title III ...

  3. DATE:

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

    and Financial Assistance Policy Division Office of Policy Office of Acquisition and Project Management SUBJECT: Implementation of Division D, Titles III and V, and Division E, ...

  4. DATE

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    working conditions, and sanitation, such as cleaning, window washing, lawn mowing, trash collection, painting, and snow removal. Routine maintenance activities, corrective...

  5. DATE

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

    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

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

    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

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

    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

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

    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:

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

    28 am, Mar 26, 2012 119 X X RPP-40149-VOL1, Rev. 2 Integrated Waste Feed Delivery Plan Volume 1 - Process Strategy E. B. West Washington River Protection Solutions, LLC P. J. Certa, T. M. Hohl, J. S. Ritari, B. R. Thompson Washington River Protection Solutions, LLC C. C. Haass Columbia Nuclear International, LLC Richland, WA 99352 U.S. Department of Energy Contract DE-AC27-08RV14800 EDT/ECN: UC: Cost Center: Charge Code: B&R Code: Total Pages: Key Words: Abstract: The Integrated Waste Feed

  10. DATE:

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

    7:53 am, Mar 26, 2012 X X 131 RPP-40149-VOL2, Rev. 2 Integrated Waste Feed Delivery Plan Volume 2 - Campaign Plan J. S. Ritari Washington River Protection Solutions, LLC P. J. Certa, T. M. Hohl, B. R. Thompson, E. B. West Washington River Protection Solutions, LLC C. C. Haass Columbia Nuclear International, LLC Richland, WA 99352 U.S. Department of Energy Contract DE-AC27-08RV14800 EDT/ECN: UC: Cost Center: Charge Code: B&R Code: Total Pages: Key Words: Abstract: The Integrated Waste Feed

  11. DATE:

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

    8:05 am, Mar 26, 2012 X X 189 RPP-40149-VOL3, Rev. 2 Integrated Waste Feed Delivery Plan Volume 3 - Project Plan J. S. Rodriguez Washington River Protection Solutions, LLC J. W. Kelly, D. C. Larsen Washington River Protection Solutions, LLC Richland, WA 99352 U.S. Department of Energy Contract DE-AC27-08RV14800 EDT/ECN: UC: Cost Center: Charge Code: B&R Code: Total Pages: Key Words: Abstract: The Integrated Waste Feed Delivery Plan (IWFDP) describes how waste feed will be delivered to the

  12. DATE

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

    This is in accordance with the methods specified in the Rules for the Control of Air Pollution in Idaho (IDAPA 58.01.01.650-651). Since the drilling equipment qualifies as a ...

  13. DATE

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

    Potential Sources of Impact Chemical UseStorage - Work will be conducted in a chemistry laboratory using chemical reagents, acids, alkalis, and solvents. Chemical Waste...

  14. DATE

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

    Test (DBFT) Characterization Borehole Drilling and Testing, Pierce County, N.D. - ... acquisition of appropriate township, county, or state zoning and drilling permits. ...

  15. Conduct of Operations

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

    2010-06-29

    This Order defines the requirements for establishing and implementing Conduct of Operations Programs at Department of Energy (DOE), including National Nuclear Security Administration (NNSA), facilities and projects. Admin Chg 2, dated 12-3-14, supersedes Admin Chg 1.

  16. ``Sleeping reactor`` irradiations: Shutdown reactor determination of short-lived activation products

    SciTech Connect (OSTI)

    Jerde, E.A.; Glasgow, D.C.

    1998-09-01

    At the High-Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory, the principal irradiation system has a thermal neutron flux ({phi}) of {approximately} 4 {times} 10{sup 14} n/cm{sup 2} {center_dot} s, permitting the detection of elements via irradiation of 60 s or less. Irradiations of 6 or 7 s are acceptable for detection of elements with half-lives of as little as 30 min. However, important elements such as Al, Mg, Ti, and V have half-lives of only a few minutes. At HFIR, these can be determined with irradiation times of {approximately} 6 s, but the requirement of immediate counting leads to increased exposure to the high activity produced by irradiation in the high flux. In addition, pneumatic system timing uncertainties (about {+-} 0.5 s) make irradiations of < 6 s less reliable. Therefore, the determination of these ultra-short-lived species in mixed matrices has not generally been made at HFIR. The authors have found that very short lived activation products can be produced easily during the period after reactor shutdown (SCRAM), but prior to the removal of spent fuel elements. During this 24- to 36-h period (dubbed the ``sleeping reactor``), neutrons are produced in the beryllium reflector by the reaction {sup 9}Be({gamma},n){sup 8}Be, the gamma rays principally originating in the spent fuel. Upon reactor SCRAM, the flux drops to {approximately} 1 {times} 10{sup 10} n/cm{sup 2} {center_dot} s within 1 h. By the time the fuel elements are removed, the flux has dropped to {approximately} 6 {times} 10{sup 8}. Such fluxes are ideal for the determination of short-lived elements such as Al, Ti, Mg, and V. An important feature of the sleeping reactor is a flux that is not constant.

  17. Next Release Date: August 2013

    Gasoline and Diesel Fuel Update (EIA)

    in Renewable Energy Consumption and Electricity 2010 Release Date: December 11, 2012 Next Release Date: August 2013 Table 10. Renewable electric power sector net generation by energy source and State, 2009 (thousand kilowatthours) Landfill Gas/MSW Biogenic 1 Other Biomass 2 Alabama 12,535,373 - 2,050 245,980 - - - 248,030 12,783,403 Alaska 1,323,744 - - - - - 7,027 7,027 1,330,771 Arizona 6,427,345 18,299 - 136,641 - 14,145 29545 198,630 6,625,975 Arkansas 4,192,706 34,371 17,645 - - - - 52,016

  18. ,"U.S. Underground Natural Gas Storage - All Operators"

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

    U.S. Underground Natural Gas Storage - All Operators",3,"Annual",2014,"06301935" ,"Release Date:","09302015" ,"Next Release Date:","10302015" ,"Excel File...

  19. Effect of fins and repeated-rib roughness on the performance characteristics of a reactor vessel air cooling system for LMFBR shutdown heat removal

    SciTech Connect (OSTI)

    Cheung, F.B.; Chawla, T.C.; Pedersen, D.R.; Tessier, J.H.; Webb, R.L.

    1986-01-01

    The use of a totally passive cooling system for shutdown heat removal that rejects heat from the reactor vessel by radiation to the guard vessel and from the guard vessel to a circulating air stream driven by natural convection is a key feature of the US Department of Energy's liquid-metal reactor advanced design study concepts. General Electric refers to the system as the Reactor Vessel Auxiliary Cooling System (RVACS) and Rockwell International as the Reactor Auxiliary Cooling System (RACS). The circulating air stream is contained in the annular passage formed with guard vessel wall and the duct wall surrounding the guard vessel. Specifically, the RVACS/RACS is designed to assure adequate cooling of the reactor vessel under abnormal operational conditions associated with loss of heat removal through the normal heat transport path via the steam generator system or the DRACS, if available. To enhance the heat transfer, longitudinal radial fins or repeated ribs can be attached to the duct wall and/or the guard vessel. The purpose of the present paper is to summarize the status of the analytical work on the development of an optimum design configuration for the RVACS/RACS.

  20. Design Report for the ½ Scale Air-Cooled RCCS Tests in the Natural convection Shutdown heat removal Test Facility (NSTF)

    SciTech Connect (OSTI)

    Lisowski, D. D.; Farmer, M. T.; Lomperski, S.; Kilsdonk, D. J.; Bremer, N.; Aeschlimann, R. W.

    2014-06-01

    The Natural convection Shutdown heat removal Test Facility (NSTF) is a large scale thermal hydraulics test facility that has been built at Argonne National Laboratory (ANL). The facility was constructed in order to carry out highly instrumented experiments that can be used to validate the performance of passive safety systems for advanced reactor designs. The facility has principally been designed for testing of Reactor Cavity Cooling System (RCCS) concepts that rely on natural convection cooling for either air or water-based systems. Standing 25-m in height, the facility is able to supply up to 220 kW at 21 kW/m2 to accurately simulate the heat fluxes at the walls of a reactor pressure vessel. A suite of nearly 400 data acquisition channels, including a sophisticated fiber optic system for high density temperature measurements, guides test operations and provides data to support scaling analysis and modeling efforts. Measurements of system mass flow rate, air and surface temperatures, heat flux, humidity, and pressure differentials, among others; are part of this total generated data set. The following report provides an introduction to the top level-objectives of the program related to passively safe decay heat removal, a detailed description of the engineering specifications, design features, and dimensions of the test facility at Argonne. Specifications of the sensors and their placement on the test facility will be provided, along with a complete channel listing of the data acquisition system.

  1. Property:StartDate | Open Energy Information

    Open Energy Info (EERE)

    StartDate Jump to: navigation, search This is a property of type Date. Pages using the property "StartDate" Showing 25 pages using this property. (previous 25) (next 25) 4 4-County...

  2. Property:EndDate | Open Energy Information

    Open Energy Info (EERE)

    EndDate Jump to: navigation, search This is a property of type Date. Pages using the property "EndDate" Showing 25 pages using this property. (previous 25) (next 25) 4 4-County...

  3. 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: ltmartinez@lanl.gov Title: QA Support Description of Product or Service Required QA Support (Current subcontracts expires 2018) * 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 forecast matrix to determine if a procurement has been set aside or is open to fair and

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

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

    5 Estimated Award Date: TBD Competition Type: TBD Buyer Contact Email: m_armijo@lanl.gov Title: Crowdsourcing Description of Product or Service Required Crowdsourcing * 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 forecast matrix to determine if a procurement has been set aside or is open to fair and reasonable competition. * LANL

  5. Five years operating experience at the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Baumhardt, R. J.; Bechtold, R. A.

    1987-04-01

    The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year operational performance of the FFTF reactor is discussed in this report. 6 refs., 10 figs., 2 tabs.

  6. OTS NOTE DATE: TO: FROM:

    Office of Legacy Management (LM)

    The data sheets report the results of radiological monitoring conducted during operation of an oil- cooled drillinghollowing machine. The sheets record measurements during five ...

  7. P.R. No. * Date*

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

    Low Risk (Rev 6, 5/8/2015) P.R. No. * Date* Subcontract No. or PO No. * 1 EXHIBIT G LOW RISK SECURITY REQUIREMENTS G1.0 Definitions and Acronyms (Mar 2013) Definitions and acronyms may be accessed electronically at http://www.lanl.gov/resources/_assets/docs/Exhibit-G/exhibit-g-definitions-acronyms-green.pdf G2.0 Statements Applicable to Scope of Work (May 2015) CONTRACTOR represents that all of the statements listed below are factually correct and applicable to the scope of work (SOW) for this

  8. Next Release Date: August 2013

    Gasoline and Diesel Fuel Update (EIA)

    2012 Next Release Date: August 2013 Table 20. Total renewable net summer capacity by energy source and State, 2010 (megawatts) Landfill Gas/MSW 1 Other Biomass 2 Alabama 3,272 - - 583 - - - 583 3,855 Alaska 414 - - - - - 7 7 422 Arizona 2,720 4 - 29 - 20 128 181 2,901 Arkansas 1,341 9 6 312 - - - 326 1,667 California 10,141 292 97 639 2,004 475 2,812 6,319 16,460 Colorado 662 3 10 - - 41 1,294 1,348 2,010 Connecticut 122 159 - - - - - 159 281 Delaware - 8 - - - - 2 10 10 District of Columbia -

  9. MEMORANDUM I TO: FILE DATE

    Office of Legacy Management (LM)

    1 F.-t&. INVCILVEE AT SITE -,----' ---... I Control wf 1 Health Physics Protect,ion 0 AECMED managed operation5 c; Little or None G AECMED responsible for c ...

  10. Operating Plan 573.1-2

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

    OPERATING PLAN 573.1-2 Title: U.S. POSTAL MAIL, SHIPPING AND RECEIVING SECURITY Owner: Cindy Mullens, ESS&H Division, Office of Institutional Operations Approving Official: Thomas Wilson, Jr., Director, Office of Institutional Operations {signature} /s/ Thomas Wilson, Jr. Approval Date: 9/20/12 Last Reviewed Date: 9/20/12 Cancellation: None TABLE OF CONTENTS 1. PURPOSE

  11. Operating Experience Level 3, OSHA's Revised Hazard Communication...

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

    Publications Hazard Communication Training - Upcoming Implementation Date for New Hazard Communication Standard Operating Experience Level 3, Safe Management of Mercury...

  12. TPA Change Package Dates in order with explanation.xlsx

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

    M-015-00 Milestone Series: Investigation Work on the Central Plateau Milestone TPA Milestone Language Explanation TPA Old Date TPA New Date Delay M-015-92A Submit a RCRA Facility Investigation/Corrective Measures Study and Remedial Investigation/Feasibility Study work plan for the 200-EA-1 operable unit (200 East Inner Area) to Ecology. 6/30/2015 9/30/2017 2 Years M-015-21A Submit a 200-BP-5 and 200-PO-1 OU Feasibility Study Report and Proposed Plan(s) to Ecology. 6/30/2015 6/30/2018 2 Years

  13. Occurrence Reporting and Processing of Operations Information

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

    1995-09-25

    This Manual provides detailed requirements to supplement DOE O 232.1, Occurrence Reporting and Processing of Operations Information. Chg 1 dated 8-12-96.

  14. Technical information report: Plasma melter operation, reliability, and maintenance analysis

    SciTech Connect (OSTI)

    Hendrickson, D.W. [ed.

    1995-03-14

    This document provides a technical report of operability, reliability, and maintenance of a plasma melter for low-level waste vitrification, in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. A process description is provided that minimizes maintenance and downtime and includes material and energy balances, equipment sizes and arrangement, startup/operation/maintence/shutdown cycle descriptions, and basis for scale-up to a 200 metric ton/day production facility. Operational requirements are provided including utilities, feeds, labor, and maintenance. Equipment reliability estimates and maintenance requirements are provided which includes a list of failure modes, responses, and consequences.

  15. DOE-ID Operations Summary

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

    POC: Danielle Miller, (208) 526-5709. Advanced Mixed Waste Treatment Project (AMWTP) Nothing to ... pressure across the PGF. The facility was shutdown undergoing a ...

  16. Property:NEPA ApplicationDate | Open Energy Information

    Open Energy Info (EERE)

    ApplicationDate Jump to: navigation, search Property Name NEPA ApplicationDate Property Type Date This is a property of type Date. Pages using the property "NEPA ApplicationDate"...

  17. A solid oxide fuel cell power system: 1992--1993 field operation

    SciTech Connect (OSTI)

    Veyo, S.E.; Kusunoki, A.; Takeuchi, S.; Kaneko, S.; Yokoyama, H.

    1994-05-01

    Westinghouse has deployed fully integrated, automatically controlled, packaged solid oxide fuel cell (SOFC) power generation systems in order to obtain useful customer feedback. Recently, Westinghouse has deployed 20 kW class natural gas fueled SOFC generator modules integrated into two 25 kW SOFC systems, the first with The UTILITIES, a Japanese consortium. The UTILITIES 25 kW SOFC system is the focus of this paper. The unit was shipped to the Rokko Island Test Center for Advanced Energy Systems (near Kobe, Japan) operated by Kansai Electric Power Co.; testing was initiated February 1992. Module A operated for 2601 hours at an ave output 16.6 kW dc; final shutdown was induced by current stability problems with dissipator (restart not possible because of damaged cells). Module B operated for 1579 hours at ave output 17.8 kWdc. The unit was damaged by operation at excessively high fuel utilization > 91%. It was rebuilt and returned to Rokko Island. This module B2 operated for 1843 hours on PNG; shutdown was cuased by air supply failure. After a new blower and motor were installed July 1993, the system was restarted August 5, 1993 and operated continuously until November 10, 1993, when an automatic shutdown was induced as part of a MITI licensing inspection. After restart, the unit passed 6000 hours of operation on desulfurized PNG on January 25, 1994. Westinghouse`s future plans are outlined.

  18. Richland Operations Office

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

    /: -. !~t. Department of Energy Richland Operations Office P.O. Box 550 Richland, Washington 99352 Nav 0 4 ?nn~ 05-AMCP-OO46 Mr. Todd Martin, Chair Hanford Advisory Board 1933 Jadwin, Suite 135 Richland, Washington 99352 Dear Mr. Martin: HANFORD ADVISORY BOARD (HAB) ADVICE #166 -FUND U PLANT AREA REMEDIATION ACTIVITIES In response to your letter dated September 10, 2004, the U.S. Department of Energy, Richland Operations Office (RL), appreciates your recommendations contained in HAB Consensus

  19. Conduct of Operations

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

    2010-06-29

    This Order defines the requirements for establishing and implementing Conduct of Operations Programs at Department of Energy (DOE), including National Nuclear Security Administration (NNSA), facilities and projects. Cancels DOE O 5480.19. Admin Chg 1, dated 6-25-13, cancels DOE O 422.1. Certified 12-3-14.

  20. Reactor engineering support of operations at Three Mile Island nuclear station

    SciTech Connect (OSTI)

    Tropasso, R.T.

    1995-12-31

    The purpose of this paper is to detail the activities in which plant nuclear engineering personnel provide direct support to plant operations. The specific activities include steady-state, transient, and shutdown/refueling operation support as well as special project involvement. The paper is intended to describe the experiences at Three Mile Island (TMI) in which significant benefit to the success of the activity is achieved through the support of the nuclear engineers.

  1. Hazard Communication Training - Upcoming Implementation Date...

    Energy Savers [EERE]

    Hazard Communication Training - Upcoming Implementation Date for New Hazard Communication Standard Hazard Communication Training - 10 CFR 851, Worker Safety and Health Program, ...

  2. Categorical Exclusion (CX) Determinations By Date | Department...

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

    CX(s) Applied: DOEEA-1914 National Renewable Energy Laboratory (NREL) Date: 072815 Location(s): CO Office(s): Golden Field Office July 21, 2015 CX-100313...

  3. Property:GEAReportDate | Open Energy Information

    Open Energy Info (EERE)

    the project. Pages using the property "GEAReportDate" Showing 1 page using this property. L Los Humeros III Geothermal Power Plant + 19 December 2013 + Retrieved from "http:...

  4. Nuclear Speed-Dating | Department of Energy

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

    Nuclear Speed-Dating Nuclear Speed-Dating March 10, 2015 - 10:48am Addthis Photo courtesy of Idaho National Laboratory. Photo courtesy of Idaho National Laboratory. Pat Adams Pat Adams Digital Content Specialist, Office of Public Affairs Nuclear Speed-Dating The future of nuclear energy needs smart, creative thinkers. That's why more than 120 experts met up last week to "speed-date" each other's ideas. Storified by Energy Department * Tue, Mar 10 2015 15:28:50 Nuclear Wetlands * James

  5. Property:OpenEI/PublicationDate | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search Property Name OpenEIPublicationDate Property Type Date Description The date the resource was first published. Retrieved from "http:...

  6. Property:Geothermal/ProjectEndDate | Open Energy Information

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    Jump to: navigation, search Property Name GeothermalProjectEndDate Property Type Date Description Project End Date Retrieved from "http:en.openei.orgw...

  7. Property:Geothermal/ProjectStartDate | Open Energy Information

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    Jump to: navigation, search Property Name GeothermalProjectStartDate Property Type Date Description Project Start Date Retrieved from "http:en.openei.orgw...

  8. Property:Estimated End Date | Open Energy Information

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    Estimated End Date Jump to: navigation, search Property Name Estimated End Date Property Type String Pages using the property "Estimated End Date" Showing 4 pages using this...

  9. Operating experience with 100% pellet burden on Amanda blast furnace

    SciTech Connect (OSTI)

    Keaton, D.E.; Minakawa, T. . Ironmaking Dept.)

    1993-01-01

    A number of significant changes in operations at the Ashland Works of the Armco Steel Company occurred in 1992 which directly impacted the Amanda Blast Furnace operation. These changes included the shutdown of the hot strip mill which resulted in coke oven gas enrichment of the Amanda stoves and an increase of 75 C in hot blast temperature, transition to 100% continuous cast operation which resulted in increased variation of the hot metal demand, and the July idling of the sinter plant. Historically, the Amanda Blast Furnace burden was 30% fluxed sinter and 70% acid pellet. It was anticipated that the change to 100% pellet burden would require changes in charging practice and alter furnace performance. The paper gives a general furnace description and then describes the burden characteristics, operating practice with 30% sinter/70% acid pellet burden, preparations for the 100% acid pellet burden operation, the 100% acid pellet operation, and the 100% fluxed pellet burden operation.

  10. Pretreated Slurries; Issue Date: August 2010; Revision Date: July 2011 (Version 07-08-2011)

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

    Summative Mass Closure Laboratory Analytical Procedure (LAP) Review and Integration: Pretreated Slurries Issue Date: August 2010 Revision Date: July 2011 (Version 07-08-2011) J. Sluiter and A. Sluiter Technical Report NREL/TP-510-48825 Revised July 2011 Technical Report Summative Mass Closure NREL/TP-510-48825 Revised July 2011 Laboratory Analytical Procedure (LAP) Review and Integration: Pretreated Slurries Issue Date: August 2010 Revision Date: July 2011 (Version 07-08-2011) J. Sluiter and A.

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    CreationDate Jump to: navigation, search Property Name FileCreationDate Property Type Date Description Original creation date for the file. Note that this is usually not the same...

  12. Property:NEPA RevisedApplicationDate | Open Energy Information

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  14. Property:NEPA DecisionDocumentDate | Open Energy Information

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    DecisionDocumentDate Jump to: navigation, search Property Name NEPA DecisionDocumentDate Property Type Date This is a property of type Date. Subproperties This property has the...

  15. First demonstration of rapid shutdown using neon shattered pellet injection for thermal quench mitigation on DIII-D

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

    Commaux, Nicolas J. C.; Shiraki, Daisuke; Baylor, Larry R.; Hollmann, E. M.; Eidietis, N. W.; Lasnier, C. J.; Moyer, R. A.; Jernigan, T. C.; Meitner, S. J.; Combs, Stephen Kirk; et al

    2016-03-02

    Shattered pellet injection (SPI) is one of the prime candidates for the ITER disruption mitigation system because of its deeper penetration and larger particle flux than massive gas injection (MGI) (Taylor et al 1999 Phys. Plasmas 6 1872) using deuterium (Commaux et al 2010 Nucl. Fusion 50 112001, Combs et al 2010 IEEE Trans. Plasma Sci. 38 400, Baylor et al 2009 Nucl. Fusion 49 085013). The ITER disruption mitigation system will likely use mostly high Z species such as neon because of more effective thermal mitigation and pumping constraints on the maximum amount of deuterium or helium that couldmore » be injected. An upgrade of the SPI on DIII-D enables ITER relevant injection characteristics in terms of quantities and gas species. This upgraded SPI system was used on DIII-D for the first time in 2014 for a direct comparison with MGI using identical quantities of neon. This comparison enabled the measurements of density perturbations during the thermal quench (TQ) and radiated power and heat loads to the divertor. It showed that SPI using similar quantities of neon provided a faster and stronger density perturbation and neon assimilation, which resulted in a lower conducted energy to the divertor and a faster TQ onset. Radiated power data analysis shows that this was probably due to the much deeper penetration of the neon in the plasma inducing a higher core radiation than in the MGI case. This experiment shows also that the MHD activity during an SPI shutdown (especially during the TQ) is quite different compared to MGI. Furthermore, this favorable TQ energy dissipation was obtained while keeping the current quench (CQ) duration within acceptable limits when scaled to ITER.« less

  16. Company Company Code Fiscal Year Submission Date

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

    NAME: TITLE: SIGNATURE: DATE: Mail to: U.S. Department of Energy Financial Reporting System, EI-24 Attention: Robert Schmitt Forrestal Building, Room 2G-089 1000 Independence Ave., ...

  17. Home Energy Score: Analysis & Improvements to Date

    Broader source: Energy.gov [DOE]

    Home Energy Score: Analysis & Improvements to Date, a presentation from the U.S. Department of Energy, by Joan Glickman Senior Advisor/Program Manager, Home Energy Score, July 24, 2012.

  18. Categorical Exclusion (CX) Determinations By Date | Department...

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

    Air Conditioners RIN: 1904-AC82 CX(s) Applied: B5.1 EERE- Buildings Technology Program Date: 06172015 Location(s): Nationwide Office(s): Golden Field Office June 16, 2015...

  19. Date centerdTimes New Roman

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

    April 2010 DOE F 1325.8 (493) United States Government Department of Energy memorandum DATE: April 27, 2010 Audit Report Number: OAS-RA-L-10-04 REPLY TO ATTN TO: IG-32 (A10RA025)...

  20. Date centerdTimes New Roman

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

    2010 DOE F 1325.8 (08-93) United States Government Department of Energy Memorandum DATE: April 23, 2010 Audit Report Number: OAS-RA-L-10-03 REPLY TO ATTN OF: IG-34 (A09ID019)...

  1. Categorical Exclusion (CX) Determinations By Date | Department...

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

    Number: DE-EE0007137 CX(s) Applied: A9, B3.6, B3.11 Solar Energy Technologies Office Date: 09102015 Location(s): AL Office(s): Golden Field Office September 8, 2015 CX-100362...

  2. Categorical Exclusion (CX) Determinations By Date | Department...

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

    Products Award Number: DE-EE0006875 CX(s) Applied: B3.6 Bioenergy Technologies Office Date: 05152015 Location(s): CA Office(s): Golden Field Office May 15, 2015 CX-100243...

  3. Date centerdTimes New Roman

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

    Project OAS-RA-L-11-03 February 2011 DOE F 1325.8 (08-93) United States Government Department of Energy Memorandum DATE: February 9, 2011 Audit Report Number: OAS-RA-L-11-03 ...

  4. Date centerdTimes New Roman

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

    Audit of Fermi National Accelerator Laboratory's NOvA Project OAS-RA-L-10-02 April 2010 ... DATE: April 16, 2010 Audit Report Number: OAS-RA-L-10-02 REPLY TO ATTN OF: IG-32 ...

  5. DETERMINATION OF THE QUANTITY OF I-135 RELEASED FROM THE AGR-1 TEST FUELS AT THE END OF ATR OPERATING CYCLE 138B

    SciTech Connect (OSTI)

    J. K. Hartwell; D. M. Scates; J. B. Walter; M. W. Drigert

    2007-05-01

    The AGR-1 experiment is a multiple fueled-capsule irradiation experiment being conducted in the Advanced Test Reactor (ATR) in support of the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The experiment began irradiation in the ATR with a cycle that reached full power on December 26, 2006 and ended with shutdown of the reactor for a brief outage on February 10, 2007 at 0900. The AGR-1 experiment will continue cyclical irradiation for about 2.5 years. In order to allow estimation of the amount of radioiodine released during the first cycle, purge gas flow to all capsules continued for about 4 days after reactor shutdown. The FPMS data acquired during part of that shutdown flow period has been analyzed to elucidate the level of 135I released during the operating cycle.

  6. Shutdown 2013 Update

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

    in your browser. or 7 upgrade Beamline 7 has been disassembled to make way for MAESTRO (nanoARPES) and COSMIC (Coherent Scattering and Microscopy). One major part of this...

  7. Plan for Operating in the Event of a Lapse in Appropriations

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

    1998-09-04

    The order establishes the Departments plan and procedures for continuing operations using balances from prior years, if available, during a lapse in appropriations and continuing only those essential functions related to emergencies involving the safety of human life or the protection of property and initiating orderly shutdown of those activities not considered essential. Canceled by DOE O 137.1A. Cancels DOE 5500.6B.

  8. Plan for Operating in the Event of a Lapse in Appropriations

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

    1999-08-30

    The order establishes the DOE plan and procedures for continuing operations using balances from prior years, if available, during a lapse in appropriations and upon exhaustion of all available balances, continuing only those essential functions related to emergencies involving the safety of human life or the protection of property and initiating orderly shutdown of those activities not considered essential. Cancels DOE O 137.1. Canceled by DOE O 137.1B.

  9. From: Madra Fischer To: Congestion Study Comments Date:

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

    Madra Fischer To: Congestion Study Comments Date: Friday, October 03, 2014 2:38:30 PM I am writing to state my objection to the Rock Island Clean Line project. They want to cross my farm field at a diagonal angle to the mainline railroad and across TWO (2) gas pipelines which causes even more hazard and danger to me and my operators. This line has no funding in place, no wind farm to supply it and no customers on the East coast who want it. The cost to me as a landowner in Illinois is the

  10. Posting Date: 12/18/15 Posting Close Date: 1/4/16

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

    815 Posting Close Date: 1416 North American Industry Classification System (NAICS) code for the request: 336211 Estimated SubcontractPO Value: TBD Estimated Period of...

  11. Posting Date: 12/17/15 Posting Close Date: 12/24/15

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

    715 Posting Close Date: 122415 North American Industry Classification System (NAICS) code for the request: 236220 Estimated SubcontractPO Value: TBD Estimated Period of...

  12. Operating plan FY 1998

    SciTech Connect (OSTI)

    1997-10-01

    This document is the first edition of Argonne`s new Operating Plan. The Operating Plan complements the strategic planning in the Laboratory`s Institutional Plan by focusing on activities that are being pursued in the immediate fiscal year, FY 1998. It reflects planning that has been done to date, and it will serve in the future as a resource and a benchmark for understanding the Laboratory`s performance. The heart of the Institutional Plan is the set of major research initiatives that the Laboratory is proposing to implement in future years. In contrast, this Operating Plan focuses on Argonne`s ongoing R&D programs, along with cost-saving measures and other improvements being implemented in Laboratory support operations.

  13. Computational Age Dating of Special Nuclear Materials

    SciTech Connect (OSTI)

    2012-06-30

    This slide-show presented an overview of the Constrained Progressive Reversal (CPR) method for computing decays, age dating, and spoof detecting. The CPR method is: Capable of temporal profiling a SNM sample; Precise (compared with known decay code, such a ORIGEN); Easy (for computer implementation and analysis).  We have illustrated with real SNM data using CPR for age dating and spoof detection. If SNM is pure, may use CPR to derive its age. If SNM is mixed, CPR will indicate that it is mixed or spoofed.

  14. Monitoring, safety systems for LNG and LPG operators

    SciTech Connect (OSTI)

    True, W.R.

    1998-11-16

    Operators in Korea and Australia have chosen monitoring and control systems in recent contracts for LNG and LPG storage. Korea Gas Corp. (Kogas) has hired Whessoe Varec, Calais, to provide monitoring systems for four LNG storage tanks being built at Kogas` Inchon terminal. For Elgas Ltd., Port Botany, Australia, Whessoe Varec has already shipped a safety valve-shutdown system to a new LPG cavern-storage facility under construction. The paper describes the systems, terminal monitoring, dynamic approach to tank management, and meeting the growing demand for LPG.

  15. 2014 NEJC Save the Date (English) | Department of Energy

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

    NEJC Save the Date (English) 2014 NEJC Save the Date (English) 2014 National Environmental Justice Conference and Training Program Save the Date, March 26 to 28, 2014 Save the Date (English) (3.38 MB) More Documents & Publications 2017 EJ Save the Date EIS-0333: Draft Environmental Impact Statement ITP Aluminum: Technical Working Group on Inert Anode Technologies

  16. Energy Department Announces Dates and New Contests for Solar Decathlon 2017

    Energy Savers [EERE]

    in Denver, Colorado | Department of Energy Dates and New Contests for Solar Decathlon 2017 in Denver, Colorado Energy Department Announces Dates and New Contests for Solar Decathlon 2017 in Denver, Colorado August 24, 2016 - 10:58am Addthis NEWS MEDIA CONTACT (202) 586-4940 DOENews@hq.doe.gov WASHINGTON, DC -The U.S. Department of Energy Solar Decathlon 2017 student design competition, which challenges collegiate teams to design, build and operate solar-powered houses that are

  17. I HEHORANDIJH I TO{ FILE DATE SUti.lECTa I O&R(S)

    Office of Legacy Management (LM)

    HEHORANDIJH I TO{ FILE DATE SUti.lECTa I O&R(S) -------- lyaa * ------------------------ currwlt * ~e.Gd. ------------------------ Owner contacted Ja Yes 0 no; if ym, date contact=d--~~~?~~-2--- :TY+E OF OPERATION --------- - ---- Research & Development 0 Facility Type Production scale testing Pi lot Scale Bench Scale Process Theoretical Studies *i Sample & &balysis a Hanuf ??cturing a University 0 Research Organization 0 Sov~rnment Sponsored Facjlity a Other

  18. Title V Operation Permit Application Webpage | Open Energy Information

    Open Energy Info (EERE)

    to library Web Site: Title V Operation Permit Application Webpage Author Division of Air Quality Published State of Alaska, Date Not Provided DOI Not Provided Check for DOI...

  19. Property:ASHRAE 169 Start Date | Open Energy Information

    Open Energy Info (EERE)

    Start Date Jump to: navigation, search This is a property of type Date. Pages using the property "ASHRAE 169 Start Date" Showing 25 pages using this property. (previous 25) (next...

  20. Property:ASHRAE 169 End Date | Open Energy Information

    Open Energy Info (EERE)

    End Date Jump to: navigation, search This is a property of type Date. Retrieved from "http:en.openei.orgwindex.php?titleProperty:ASHRAE169EndDate&oldid21585...

  1. Adv. Nuclear Solicitation Part I Due Date | Department of Energy

    Energy Savers [EERE]

    Nuclear Solicitation Part I Due Date Adv. Nuclear Solicitation Part I Due Date July 20, 2016 12:01AM to 11:59PM EDT ADVANCED NUCLEAR ENERGY PROJECTS SOLICITATION PART I DUE DATE ...

  2. Adv. Fossil Solicitation Part I Due Date | Department of Energy

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

    Fossil Solicitation Part I Due Date Adv. Fossil Solicitation Part I Due Date January 13, 2016 12:01AM to 11:59PM EST ADVANCED FOSSIL ENERGY PROJECTS SOLICITATION PART I DUE DATE ...

  3. Adv. Nuclear Solicitation Part I Due Date | Department of Energy

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

    Nuclear Solicitation Part I Due Date Adv. Nuclear Solicitation Part I Due Date March 16, 2016 12:01AM to 11:59PM EDT ADVANCED NUCLEAR ENERGY PROJECTS SOLICITATION PART I DUE DATE ...

  4. REEE Solicitation Part I Due Date | Department of Energy

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

    I Due Date REEE Solicitation Part I Due Date November 30, 2016 1:01AM EST to December 1, 2016 12:59AM EST RENEWABLE ENERGY AND EFFICENT ENERGY PROJECTS SOLICITATION PART I DUE DATE

  5. REEE Solicitation Part II Due Date | Department of Energy

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

    II Due Date REEE Solicitation Part II Due Date November 30, 2016 1:01AM EST to December 1, 2016 12:59AM EST RENEWABLE ENERGY AND EFFICENT ENERGY PROJECTS SOLICITATION PART II DUE DATE

  6. REEE Solicitation Part I Due Date | Department of Energy

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

    I Due Date REEE Solicitation Part I Due Date March 16, 2016 12:01AM to 11:59PM EDT RENEWABLE ENERGY AND EFFICENT ENERGY PROJECTS SOLICITATION PART I DUE DATE...

  7. Adv. Fossil Solicitation Part I Due Date | Department of Energy

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

    Fossil Solicitation Part I Due Date Adv. Fossil Solicitation Part I Due Date March 16, 2016 12:01PM to 11:59PM EDT ADVANCED FOSSIL ENERGY PROJECTS SOLICITATION PART I DUE DATE...

  8. REEE Solicitation Part I Due Date | Department of Energy

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

    I Due Date REEE Solicitation Part I Due Date September 14, 2016 12:01AM to 11:59PM EDT RENEWABLE ENERGY AND EFFICENT ENERGY PROJECTS SOLICITATION PART I DUE DATE

  9. Using Process Safety Management to improve plant operability

    SciTech Connect (OSTI)

    Sutton, I.S.

    1995-12-31

    The Process Safety Management (PSM) standard, 29 CFR 1910.119, was published in draft from in July 1990 and has been in force since May 1992. The standard requires that all companies that handle hazardous materials must have in place a management program to minimize the chance of accidents, and to reduce the consequences of such accidents should they occur. The purpose of this paper is to provide some preliminary guidance as to how PSM activities can be managed so that, as the compliance part of the work is completed, the best return on the investment can be achieved. One final point should be made about safety and operability. The two are closely linked, but they are not identical. In other words, a safety improvement program will almost certainly lead to reduced economic losses, similarly a reliability improvement program will almost certainly reduce injuries, but there are some differences that need to be taken account. These include: (1) Additional safety equipment may reduce reliability. (2) A reliable plant does not undergo many shutdowns. Therefore, operators have less practice with the implementation of shutdown and startup procedures than they would otherwise. (3) Unsafe engineering practices, such as the use of temporary bypasses and jumper lines, may increase operability, but they reduce safety.

  10. Operational readiness review for the Waste Experimental Reduction Facility. Final report

    SciTech Connect (OSTI)

    Not Available

    1993-11-01

    An Operational Readiness Review (ORR) at the Idaho National Engineering Laboratory`s (INEL`s) Waste Experimental Reduction Facility (WERF) was conducted by EG&G Idaho, Inc., to verify the readiness of WERF to resume operations following a shutdown and modification period of more than two years. It is the conclusion of the ORR Team that, pending satisfactory resolution of all pre-startup findings, WERF has achieved readiness to resume unrestricted operations within the approved safety basis. ORR appraisal forms are included in this report.

  11. Report of the Task Group on operation Department of Energy tritium facilities

    SciTech Connect (OSTI)

    Not Available

    1991-10-01

    This report discusses the following topics on the operation of DOE Tritium facilities: Environment, Safety, and Health Aspects of Tritium; Management of Operations and Maintenance Functions; Safe Shutdown of Tritium Facilities; Management of the Facility Safety Envelope; Maintenance of Qualified Tritium Handling Personnel; DOE Tritium Management Strategy; Radiological Control Philosophy; Implementation of DOE Requirements; Management of Tritium Residues; Inconsistent Application of Requirements for Measurement of Tritium Effluents; Interdependence of Tritium Facilities; Technical Communication among Facilities; Incorporation of Confinement Technologies into New Facilities; Operation/Management Requirements for New Tritium Facilities; and Safety Management Issues at Department of Energy Tritium Facilities.

  12. Energy Department Announces Dates and New Contests for Solar...

    Energy Savers [EERE]

    Dates and New Contests for Solar Decathlon 2017 in Denver, Colorado Energy Department Announces Dates and New Contests for Solar Decathlon 2017 in Denver, Colorado August 24, 2016 ...

  13. Property:FERC License Issuance Date | Open Energy Information

    Open Energy Info (EERE)

    Issuance Date Jump to: navigation, search Property Name FERC License Issuance Date Property Type String Retrieved from "http:en.openei.orgwindex.php?titleProperty:FERCLicense...

  14. Property:FERC License Application Date | Open Energy Information

    Open Energy Info (EERE)

    FERC License Application Date Jump to: navigation, search Property Name FERC License Application Date Property Type String Retrieved from "http:en.openei.orgw...

  15. NEMA Lighting, CCE Overview and Update presentation, dated 05...

    Energy Savers [EERE]

    Lighting, CCE Overview and Update presentation, dated 05252011. NEMA Lighting, CCE Overview and Update presentation, dated 05252011. This document is the U.S. Department of ...

  16. Jupiter Laser Facility Target Fab Request Requester: Date Requested:

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

    / Sketches: « Jupiter Laser Facility Target Fab Request Requester: Date Requested: Phone or E-Mail: Date Required: Target Name: Reference #: Laser System: Project: Task:

  17. Memorandum from Daniel B. Poneman dated August 27, 2010, Strategic...

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

    Daniel B. Poneman dated August 27, 2010, Strategic Business Initiatives Memorandum from Daniel B. Poneman dated August 27, 2010, Strategic Business Initiatives Dep Sec Memo ...

  18. FAQ's for: ENERGY STAR Verification Testing Pilot Program dated...

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

    FAQ's for: ENERGY STAR Verification Testing Pilot Program dated December 2010 FAQ's for: ENERGY STAR Verification Testing Pilot Program dated December 2010 This document is the ...

  19. POLICY GUIDANCE MEMORANDUM #04 Setting Effective Date for New...

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

    04 Setting Effective Date for New Hires POLICY GUIDANCE MEMORANDUM 04 Setting Effective Date for New Hires The purpose of this memorandum is to establish the Department of...

  20. Contractor Fee Payments- Idaho Operations Office

    Office of Energy Efficiency and Renewable Energy (EERE)

    See the amount of fees earned on EM's major contracts for each evaluated fee period and the total contract to date at the Idaho Operations Office on these charts.

  1. Contractor Fee Payments- Oak Ridge Operations

    Office of Energy Efficiency and Renewable Energy (EERE)

    See the amount of fees earned on EM's major contracts for each evaluated fee period and the total contract to date at the Oak Ridge Operations on these charts.  

  2. Contractor Fee Payments- Richland Operations Office

    Office of Energy Efficiency and Renewable Energy (EERE)

    See the amount of fees earned on EM's major contracts for each evaluated fee period and the total contract to date at the Richland Operations Office on these charts. 

  3. Supplier Information Form Date: New Revision

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

    Supplier Information Form Date: New Revision Interested suppliers may complete and submit a Supplier Information Form to be included into LANS' vendor database. Suppliers are advised that there is no guarantee any solicitations or awards will be sent to Supplier by submitting a Supplier Information Form; however, in the event a solicitation is sent to the Supplier from an LANS Procurement Official, then a more formal quotation/offer may be required. Legal Business Name: D/B/A: (if applicable)

  4. WEATHERIZATION PROGRAM NOTICE 16-XX EFFECTIVE DATE:

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

    WEATHERIZATION PROGRAM NOTICE 16-XX EFFECTIVE DATE: SUBJECT: WEATHERIZATION OF RENTAL UNITS - Applicable to single family and multifamily dwellings PURPOSE: To provide Grantees with updated guidance on weatherizing rental units in the Weatherization Assistance Program (WAP). DOE has answered specific questions from Grantees related to the weatherization of rental units, whether single family building or multifamily dwellings, over a number of years. However, the responses to these questions have

  5. Low energy cyclotron for radiocarbon dating

    SciTech Connect (OSTI)

    Welch, J.J.

    1984-12-01

    The measurement of naturally occurring radioisotopes whose half lives are less than a few hundred million years but more than a few years provides information about the temporal behavior of geologic and climatic processes, the temporal history of meteoritic bodies as well as the production mechanisms of these radioisotopes. A new extremely sensitive technique for measuring these radioisotopes at tandem Van de Graaff and cyclotron facilities has been very successful though the high cost and limited availability have been discouraging. We have built and tested a low energy cyclotron for radiocarbon dating similar in size to a conventional mass spectrometer. These tests clearly show that with the addition of a conventional ion source, the low energy cyclotron can perform the extremely high sensitivity /sup 14/C measurements that are now done at accelerator facilities. We found that no significant background is present when the cyclotron is tuned to accelerate /sup 14/C negative ions and the transmission efficiency is adequate to perform radiocarbon dating on milligram samples of carbon. The internal ion source used did not produce sufficient current to detect /sup 14/C directly at modern concentrations. We show how a conventional carbon negative ion source, located outside the cyclotron magnet, would produce sufficient beam and provide for quick sampling to make radiocarbon dating milligram samples with a modest laboratory instrument feasible.

  6. MEMORANDUM TO: FILE, OH. 0 DATE

    Office of Legacy Management (LM)

    0 AECMED overviewed 7 operations 0 Contractor had total control 6r unknown 0 Health Physics Protection I 0 Little or None c CIEWMED responsibility D Contractof 'responsibility ...

  7. Date centerdTimes New Roman

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

    ... These problems existed because the Commission had not fully ... and continue in the event of an emergency or disaster. ... continuity of operations planning by securing a secondary ...

  8. Date centerdTimes New Roman

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

    Since the terrorist attacks of September 2001, revisions to the DBT have established significantly more stringent standards for protecting Departmental assets and operations. The ...

  9. Publication Dates | MIT-Harvard Center for Excitonics

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

    Publication Dates 9.25.2014 2016 2015 2014 2013 2012 2011 2010 2009

  10. Rich land Operations Office

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

    TG Department of Energy Rich land Operations Office P.O. Box 550 AES Richland, Washington 99352 CERTIFIED MAIL NOV~ 2 10 2009 Mr. Gerald Pollet Heart of America Northwest 1314 N.E. 5 6 th Street Suite 100 Seattle, Washington 98105 Dear Mr. Pollet: FREEDOM OF INFORMATION ACT REQUEST (FOI 2009-0054) The purpose of this letter is to inform you that we have withdrawn our response dated September 14, 2009, and have issued the following determination regarding item 8 of your request. In response to

  11. 2017 EJ Save the Date | Department of Energy

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

    7 EJ Save the Date 2017 EJ Save the Date Save the Date! March 8 through 10, 2017 2017 National Environmental Justice Conference and Training Program SAVE THE DATE for the 2017 National Environmental Justice Conference and Training Program (2.86 MB) More Documents & Publications 2014 NEJC Save the Date (English) EIS-0333: Draft Environmental Impact Statement Conference Information: 2017 National Environmental Justice Conference and Training Program

  12. Date centerdTimes New Roman

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

    Audit Services Audit Report Office of Science's Energy Frontier Research Centers OAS-RA-L-10-09 August 2010 DOE F 1325.8 (08-93) United States Government Department of Energy Memorandum DATE: August 27, 2010 Audit Report Number: OAS-RA-L-10-09 REPLY TO ATTN OF: IG-32 (A10RA003) SUBJECT: Audit Report on "Office of Science's Energy Frontier Research Centers" TO: Associate Director, Office of Basic Energy Sciences, SC-22 INTRODUCTION AND OBJECTIVE In 2008, the Department of Energy's

  13. Date Time Event Description/Participants Location

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

    Updated: 06/11/2015 Date Time Event Description/Participants Location Point of Contact 11 thru 12 All Day Meeting Todd Allen, deputy director of Science and Technology at INL, has been invited to speak at the Idaho Society of Professional Engineers (ISPE) annual meeting. Coeur d'Alene, ID Sara Prentice, 526-9591 18 9:00 AM Education Outreach Approximately 50 iSTEM students and instructors will tour various INL Idaho Falls facilities Idaho Falls, ID INL Tours Office, 526-0050 23 All Day Meeting

  14. : H. Jack Elackwell, Area Manager, LAAO DATE:

    Office of Legacy Management (LM)

    O.&E b.&AORANDti~ l > : H. Jack Elackwell, Area Manager, LAAO DATE: June 5, 1973 70~ : ~$?$Z~H-Division Leader ,WE~,T : ENVIRONMENTAL RADIOACTIVITY SURVEY OF LOS ALAMOS COMIMUNITY LAND AREAS ' MBOL : H8M-73-102 At your request an environmental radioactivity survey of four' .tracts of AEC-owned land in Los Alamos County was conducted. The monitoring and analysis of samples paralleled that described in Los Alamos Scientific Laboratory Report LA5097-MS, "Los Alamos Land Areas

  15. Categorical Exclusion Determinations: Idaho Operations Office | Department

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

    of Energy Idaho Operations Office Categorical Exclusion Determinations: Idaho Operations Office Categorical Exclusion Determinations issued by Idaho Operations Office. DOCUMENTS AVAILABLE FOR DOWNLOAD May 26, 2015 CX-013669: Categorical Exclusion Determination Advanced Test Reactor 2A Loop Chemistry Control CX(s) Applied: B3.6 Date: 05/26/2015 Location(s): Idaho Offices(s): Idaho Operations Office May 20, 2015 CX-013673: Categorical Exclusion Determination Advanced Test Reactor Complex

  16. Operational Excellence

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

    Operational Excellence Operational Excellence The Lab's mission is to develop and apply science and technology to ensure the safety, security, and reliability of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. aeiral shot of los alamos, new mexico What Los Alamos gets done as a premier national security science laboratory depends on how we do it The Laboratory's operations and business systems ensure the safe, secure, and

  17. Operations Videos

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

    Operations Research Analysts The U.S. Energy Information Administration (EIA) within the Department of Energy has forged a world-class information program that stresses quality, teamwork, and employee growth. In support of our program, we offer a variety of profes- sional positions, including the Operations Research Analyst, whose work is associated with the development and main- tenance of energy modeling systems. Responsibilities: Operations Research Analysts perform or participate in one or

  18. Laboratory Operations

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

    Laboratory Operations Laboratory Operations Latest announcements from the Lab on its operations. News Releases Science Briefs Photos Picture of the Week Publications Social Media Videos Fact Sheets The Laboratory began the Hazmat Challenge in 1996 to hone the skills of its own hazmat team members. 20th Hazmat Challenge tests skills of hazardous materials response teams Ten hazardous materials response teams from New Mexico, Missouri, Oklahoma and Nebraska test their skills in a series of graded,

  19. SECTION 124„AGENCY OPERATIONS IN THE ABSENCE OF APPROPRIATIONS

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

    SECTION 124-AGENCY OPERATIONS IN THE ABSENCE OF APPROPRIATIONS OMB Circular No. A-11 (2013) Page 1 of Section 124 SECTION 124-AGENCY OPERATIONS IN THE ABSENCE OF APPROPRIATIONS Table of Contents 124.1 What types of actions may my agency conduct during a funding hiatus? 124.2 What plans should my agency make in anticipation of a funding hiatus? 124.3 When should my agency's shutdown plans be implemented? 124.1 What types of actions may my agency conduct during a funding hiatus? (a) Background.

  20. Design and operation of a rapid thermal transient component testing sodium loop

    SciTech Connect (OSTI)

    Crandall, D.L.

    1984-04-16

    A specific problem developed during the design of an on-line sampling system for the Sodium Loop Safety Facility fast breeder reactor experiments. Rapid fluctuations in the sodium temperature, caused by reactor operation and shutdown, exposed the system components to conditions that could result in fatigue failure. A component test loop was designed and built at the Idaho National Engineering Laboratory to allow experimental qualification of component integrity. This paper outlines test system requirements, describes the design and special features, presents test procedures ad relates significant operating experience.

  1. Laboratory Operations

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

    ... Hockaday is the associate director of the Experimental Physical Sciences Directorate and Cabbil is associate director for Nuclear and High Hazard Operations. - 12513 Norris ...

  2. operations center

    National Nuclear Security Administration (NNSA)

    servers and other critical Operations Center equipment

  3. Independent air supply system filtered to protect against biological and radiological agents (99.7%).
  4. <...

  5. SPEAR Operations

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

    Interface 1113 N. Kurita J. Langton Vacuum TSP's 1120 J. Corbett A. Terebilo MATLAB Applications - Basics 1121 F. Rafael Booster Kicker Upgrade, Operation Manual 1121...

  6. Blanket Module Boil-Off Times during a Loss-of-Coolant Accident - Case 0: with Beam Shutdown only

    SciTech Connect (OSTI)

    Hamm, L.L.

    1998-10-07

    This report is one of a series of reports that document LBLOCA analyses for the Accelerator Production of Tritium primary blanket Heat Removal system. This report documents the analysis results of a LBLOCA where the accelerator beam is shut off without primary pump trips and neither the RHR nor the cavity flood systems operation.

  7. COST BREAKDOWN AWARD NO: START DATE: EXPIRATION DATE: FISCAL YEAR BREAKDOWN OF FUNDS

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

    COST BREAKDOWN AWARD NO: START DATE: EXPIRATION DATE: FISCAL YEAR BREAKDOWN OF FUNDS ELEMENTS FY FY FY FY FY TOTAL Direct Labor Overhead Materials Supplies Travel Other Direct Costs Subcontractors Total Direct Costs G&A Expense Total All Costs DOE Share* Awardee Share* Overhead Rate G&A Rate 1. The cost elements indicated are provided as an example only. Your firm should indicate the costs elements you have used on your invoices. 2. You should indicate the cost incurred for each of your

  8. CX-009065: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Installation of Sentinel Wells ASB011B/011C for A-2 Air Stripper Shutdown CX(s) Applied: B3.1 Date: 07/24/2012 Location(s): South Carolina Offices(s): Savannah River Operations Office

  9. Case history: Effectively operating an RTO with batch VOC spikes

    SciTech Connect (OSTI)

    Hohl, H.M.

    1999-07-01

    The problem at a foam packaging plant in Texas was periodic spikes of expanded foam blowing agent to atmosphere. The amount of butane blowing agent released is a function of the thickness of the packaging foam desired. As the facility changed products on the multiple extrusion lines, volatile organic compound (VOC) emissions varied widely. The Texas Natural Resource Conservation Commission (TNRCC) requires abatement of the blowing agent. If the abatement device was not designed for the wide variation in VOCs, the abatement device could shut down under high temperature conditions. With the abatement device shutdown, the manufacturing operation must also be shut down. Two methods were used in the past to address the widely varied operating conditions. One was to operate an abatement device with a less thermally efficient recuperative style oxidizer. These units had thermal efficiencies in the range of 50 to 70%. The second method of dealing with the different operating conditions was to oversize the abatement device for the maximum VOC concentration. In this case a very large regenerative thermal oxidizer (RTO) was used to minimize operating costs. This paper will provide case history information on an innovative way to deal with effective operation in dealing with VOC spikes in an expanded foam packaging application. A hot gas bypass system was designed and installed to address the VOC spikes. As a result the system operates with lower overall operating costs than previous systems. The design, operation, and environmental performance for this unit will be reviewed during this presentation.

  10. Adv. Fossil Solicitation Part I Due Date | Department of Energy

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

    I Due Date Adv. Fossil Solicitation Part I Due Date November 30, 2016 1:01AM EST to December 1, 2016 12:59AM EST ADVANCED FOSSIL ENERGY PROJECTS SOLICITATION PART I

  11. Adv. Fossil Solicitation Part II Due Date | Department of Energy

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

    II Due Date Adv. Fossil Solicitation Part II Due Date November 30, 2016 1:01AM AST to December 1, 2016 12:59AM AST ADVANCED FOSSIL ENERGY PROJECTS SOLICITATION PART II

  12. REEE Solicitation Part II Due Date | Department of Energy

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

    REEE Solicitation Part II Due Date REEE Solicitation Part II Due Date April 13, 2016 12:01AM to 11:59PM EDT RENEWABLE ENERGY AND EFFICENT ENERGY PROJECTS SOLICITATION PART II DUE...

  13. REEE Solicitation Part II Due Date | Department of Energy

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

    REEE Solicitation Part II Due Date REEE Solicitation Part II Due Date June 15, 2016 12:01AM to 11:59PM EDT RENEWABLE ENERGY AND EFFICENT ENERGY PROJECTS SOLICITATION PART II DUE...

  14. Adv. Nuclear Solicitation Part II Due Date | Department of Energy

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

    Adv. Nuclear Solicitation Part II Due Date Adv. Nuclear Solicitation Part II Due Date April 13, 2016 12:01AM to 11:59PM EDT ADVANCED NUCLEAR ENERGY PROJECTS SOLICITATION PART II ...

  15. Pressurized reactor system and a method of operating the same

    DOE Patents [OSTI]

    Isaksson, J.M.

    1996-06-18

    A method and apparatus are provided for operating a pressurized reactor system in order to precisely control the temperature within a pressure vessel in order to minimize condensation of corrosive materials from gases on the surfaces of the pressure vessel or contained circulating fluidized bed reactor, and to prevent the temperature of the components from reaching a detrimentally high level, while at the same time allowing quick heating of the pressure vessel interior volume during start-up. Super-atmospheric pressure gas is introduced from the first conduit into the fluidized bed reactor and heat derived reactions such as combustion and gasification are maintained in the reactor. Gas is exhausted from the reactor and pressure vessel through a second conduit. Gas is circulated from one part of the inside volume to another to control the temperature of the inside volume, such as by passing the gas through an exterior conduit which has a heat exchanger, control valve, blower and compressor associated therewith, or by causing natural convection flow of circulating gas within one or more generally vertically extending gas passages entirely within the pressure vessel (and containing heat exchangers, flow rate control valves, or the like therein). Preferably, inert gas is provided as a circulating gas, and the inert gas may also be used in emergency shut-down situations. In emergency shut-down reaction gas being supplied to the reactor is cut off, while inert gas from the interior gas volume of the pressure vessel is introduced into the reactor. 2 figs.

  16. Pressurized reactor system and a method of operating the same

    DOE Patents [OSTI]

    Isaksson, Juhani M. (Karhula, FI)

    1996-01-01

    A method and apparatus are provided for operating a pressurized reactor system in order to precisely control the temperature within a pressure vessel in order to minimize condensation of corrosive materials from gases on the surfaces of the pressure vessel or contained circulating fluidized bed reactor, and to prevent the temperature of the components from reaching a detrimentally high level, while at the same time allowing quick heating of the pressure vessel interior volume during start-up. Superatmospheric pressure gas is introduced from the first conduit into the fluidized bed reactor and heat derived reactions such as combustion and gassification are maintained in the reactor. Gas is exhausted from the reactor and pressure vessel through a second conduit. Gas is circulated from one part of the inside volume to another to control the temperature of the inside volume, such as by passing the gas through an exterior conduit which has a heat exchanger, control valve, blower and compressor associated therewith, or by causing natural convection flow of circulating gas within one or more generally vertically extending gas passages entirely within the pressure vessel (and containing heat exchangers, flow rate control valves, or the like therein). Preferably, inert gas is provided as a circulating gas, and the inert gas may also be used in emergency shut-down situations. In emergency shut-down reaction gas being supplied to the reactor is cut off, while inert gas from the interior gas volume of the pressure vessel is introduced into the reactor.

  17. Key Dates | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    Key Dates DOE Office of Science Graduate Student Research (SCGSR) Program SCGSR Home Eligibility Benefits Participant Obligations How to Apply Information for Laboratory Scientists and Thesis Advisors Key Dates Frequently Asked Questions Contact WDTS Home Key Dates Print Text Size: A A A FeedbackShare Page The SCGSR Program Key Dates are noted below. At the submission deadline (shown in red), the online application system will close after which no additional materials will be accepted. The

  18. Appliance Standards Program Schedule - CCE Overview and Update, dated

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

    October 26, 2011 | Department of Energy dated October 26, 2011 Appliance Standards Program Schedule - CCE Overview and Update, dated October 26, 2011 This document is Appliance Standards Program Schedule & CCE Overview and Update presentation, dated 10/26/2011, presented to Energy-Efficiency Advocacy Groups doe_eeag_present2011.pdf (446.59 KB) More Documents & Publications Appliance Standards Program Schedule - CCE Overview and Update, presented at AHRI 2011 Annual Meeting, dated

  19. Key Dates | U.S. DOE Office of Science (SC)

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

    Key Dates Albert Einstein Distinguished Educator Fellowship (AEF) Program Einstein Fellowship Home Eligibility Benefits Obligations How to Apply Key Dates Frequently Asked Questions Fellows Central Contact WDTS Home Key Dates Print Text Size: A A A FeedbackShare Page Key Dates for the 2017-2018 AEF Program Application process. On-line Application Opens August 17, 2016 Application Deadline 8:00pm EST November 17, 2016 Application Review 8 - 9 weeks Notification to Semi-Finalists [Travel

  20. Key Dates | U.S. DOE Office of Science (SC)

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

    Key Dates DOE Office of Science Graduate Student Research (SCGSR) Program SCGSR Home Eligibility Benefits Participant Obligations How to Apply Information for Laboratory Scientists and Thesis Advisors Key Dates Frequently Asked Questions Contact WDTS Home Key Dates Print Text Size: A A A FeedbackShare Page The SCGSR Program Key Dates are noted below. At the submission deadline (shown in red), the online application system will close after which no additional materials will be accepted. The

  21. Operating Costs

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

    1997-03-28

    This chapter is focused on capital costs for conventional construction and environmental restoration and waste management projects and examines operating cost estimates to verify that all elements of the project have been considered and properly estimated.

  22. Determination of Protein Content in Biomass: Laboratory Analytical Procedure (LAP); Issue Date 05/23/2008

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

    Protein Content in Biomass Laboratory Analytical Procedure (LAP) Issue Date: 05/23/2008 B. Hames, C. Scarlata, and A. Sluiter Technical Report NREL/TP-510-42625 Revised May 2008 NREL is operated by Midwest Research Institute ● Battelle Contract No. DE-AC36-99-GO10337 Determination of Protein Content in Biomass Laboratory Analytical Procedure (LAP) Issue Date: 05/23/2008 B. Hames, C. Scarlata, and A. Sluiter Technical Report NREL/TP-510-42625 Revised May 2008 National Renewable Energy

  1. Preparation of Samples for Compositional Analysis: Laboratory Analytical Procedure (LAP); Issue Date 08/08/2008

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

    Preparation of Samples for Compositional Analysis Laboratory Analytical Procedure (LAP) Issue Date: 8/06/2008 B. Hames, R. Ruiz, C. Scarlata, A. Sluiter, J. Sluiter, and D. Templeton Technical Report NREL/TP-510-42620 Revised August 2008 NREL is operated by Midwest Research Institute ● Battelle Contract No. DE-AC36-99-GO10337 Preparation of Samples for Compositional Analysis Laboratory Analytical Procedure (LAP) Issue Date: 8/06/2008 B. Hames, R. Ruiz, C. Scarlata, A. Sluiter, J. Sluiter, and

  2. Adv. Fossil Solicitation Part I Due Date | Department of Energy

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

    Fossil Solicitation Part I Due Date Adv. Fossil Solicitation Part I Due Date September 14, 2016 12:01AM to 11:59PM EDT ADVANCED FOSSIL ENERGY PROJECTS SOLICITATION PART I DUE DATE Learn more about the Advanced Fossil

  3. Adv. Nuclear Solicitation Part II Due Date | Department of Energy

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

    Nuclear Solicitation Part II Due Date Adv. Nuclear Solicitation Part II Due Date November 23, 2016 12:01AM to 11:59PM EST ADVANCED NUCLEAR ENERGY PROJECTS SOLICITATION PART II DUE DATE Learn more about the Advanced Nuclear

  4. Adv. Nuclear Solicitation Part II Due Date | Department of Energy

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

    Nuclear Solicitation Part II Due Date Adv. Nuclear Solicitation Part II Due Date October 19, 2016 12:01AM to 11:59PM EDT ADVANCED NUCLEAR ENERGY PROJECTS SOLICITATION PART II DUE DATE Learn more about the Advanced Nuclear

  5. Hazard Communication Training - Upcoming Implementation Date for New Hazard

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

    Communication Standard | Department of Energy Hazard Communication Training - Upcoming Implementation Date for New Hazard Communication Standard Hazard Communication Training - Upcoming Implementation Date for New Hazard Communication Standard Hazard Communication Training - 10 CFR 851, Worker Safety and Health Program, requires all DOE Federal and contractor employees with hazardous chemicals in their workplaces to complete new Hazard Communication Training. Upcoming Implementation Date for

  6. Computerized Operator Support System – Phase II Development

    SciTech Connect (OSTI)

    Ulrich, Thomas A.; Boring, Ronald L.; Lew, Roger T.; Thomas, Kenneth D.

    2015-02-01

    A computerized operator support system (COSS) prototype for nuclear control room process control is proposed and discussed. The COSS aids operators in addressing rapid plant upsets that would otherwise result in the shutdown of the power plant and interrupt electrical power generation, representing significant costs to the owning utility. In its current stage of development the prototype demonstrates four advanced functions operators can use to more efficiently monitor and control the plant. These advanced functions consist of: (1) a synthesized and intuitive high level overview display of system components and interrelations, (2) an enthalpy-based mathematical chemical and volume control system (CVCS) model to detect and diagnose component failures, (3) recommended strategies to mitigate component failure effects and return the plant back to pre-fault status, and (4) computer-based procedures to walk the operator through the recommended mitigation actions. The COSS was demonstrated to a group of operators and their feedback was collected. The operators responded positively to the COSS capabilities and features and indicated the system would be an effective operator aid. The operators also suggested several additional features and capabilities for the next iteration of development. Future versions of the COSS prototype will include additional plant systems, flexible computer-based procedure presentation formats, and support for simultaneous component fault diagnosis and dual fault synergistic mitigation action strategies to more efficiently arrest any plant upsets.

  7. Operating Strategies

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

    Operating Strategies and Design Recommendations for Mitigating Local Damage Effects in Offshore Turbine Blades Phillip W. Richards phillip@gatech.edu Graduate Research Assistant Daniel Guggenheim School of Aerospace Engineering Atlanta, Georgia, USA D. Todd Griffith dgriffi@sandia.gov Principal Member of the Technical Staff Sandia National Laboratories Albuquerque, New Mexico, USA Dewey H. Hodges dhodges@gatech.edu Professor Daniel Guggenheim School of Aerospace Engineering Atlanta, Georgia, USA

  8. Refinery Capacity Report

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

    Operable Date of Last Operation Date Shutdown Table 11. New, Shutdown and Reactivated Refineries During 2015 a b NEW PAD District III 71,250 Buckeye Texas Processing LLC Corpus Christi, TX 46,250 11/15 Petromax Refining Co LLC Houston, TX 25,000 07/15 SHUTDOWN PAD District III 0 12,000 Pelican Refining Company LLC Lake Charles, LA 0 12,000 12/14 01/15 a b bbl/cd=Barrels per calendar day. bbl/sd=Barrels per stream day. Sources: Energy Information Administration (EIA) Form EIA-810, "Monthly

  9. NEMA Distribution Transformers, CCE Overview and Update presentation, dated

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

    05/24/2011 | Department of Energy Distribution Transformers, CCE Overview and Update presentation, dated 05/24/2011 NEMA Distribution Transformers, CCE Overview and Update presentation, dated 05/24/2011 This document is the U.S. Department of Energys presentation titled NEMA Distribution Transformers, CCE Overview and UpdateŽ, date - May 24, 2011 nema_distributiontransformers_presentation.pdf (215.16 KB) More Documents & Publications Energy Conservation Program for Consumer Products

  10. Key Dates | U.S. DOE Office of Science (SC)

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

    Key Dates Visiting Faculty Program (VFP) VFP Home Eligibility Benefits Participant Obligations How to Apply Key Dates Frequently Asked Questions Contact WDTS Home Key Dates Print Text Size: A A A FeedbackShare Page At the submission deadline (shown in red) the application system will close, and no materials will be accepted after the submission deadline has passed. The Application System closes at 5:00 PM Eastern Time. VFP Term: Summer 2015 On-line Application Opens October 15, 2015 Applications

  11. Low Solids Enzymatic Saccharification of Lignocellulosic Biomass: Laboratory Analytical Procedure (LAP), Issue Date: February 4, 2015

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

    Low Solids Enzymatic Saccharification of Lignocellulosic Biomass Laboratory Analytical Procedure (LAP) Issue Date: February 4, 2015 M. G. Resch, J. O. Baker, and S. R. Decker Technical Report NREL/TP-5100-63351 February 2015 NREL is a national laboratory of the U.S. Department of Energy Office of Energy Efficiency & Renewable Energy Operated by the Alliance for Sustainable Energy, LLC This report is available at no cost from the National Renewable Energy Laboratory (NREL) at

  12. Microsoft Word - 2014 BUDGET WORKSHOP - SAVE THE DATE Final.docx

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

    SAVE THE DATE Thursday, March 15, 2012 2014 Hanford Budget and Cleanup Priorities Public Meeting The U.S. Department of Energy (DOE) Richland Operations Office, DOE Office of River Protection, U.S. Environmental Protection Agency (EPA) and the Washington State Department of Ecology (Ecology) would like to invite you to participate in a public meeting on Hanford cleanup priorities. When: Thursday, March 15, 2012 Where: Richland Public Library - Gallery Room 955 Northgate Drive Richland, WA 99352

  13. Detection and Analysis of Threatsto the Energy Sector (DATES...

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

    Detection and Analysis of Threatsto the Energy Sector (DATES) May 2008 DOEOE National SCADA Test Bed Fiscal Year 2009 Work Plan "Supervisory Control and Data Acquisition (SCADA) ...

  14. 2014 NEJC Save the Date (Spanish) | Department of Energy

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

    More Documents & Publications 2013 National Environmental Justice Conference and Training Program 2014 NEJC Save the Date (English) 2015 National Environmental Justice Conference ...

  15. Memorandum from Paul Bosco dated May, 20, 2012, Utlization of...

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

    Purchase Agreements Memorandum from Paul Bosco dated May, 20, 2012, Utlization of the General Services Administration's Federal Strategic Sourcing Initiative Blanket Purchase ...

  16. Date Set for Closure of Russian Nuclear Weapons Plant - NNSA...

    National Nuclear Security Administration (NNSA)

    Date Set for Closure of Russian Nuclear Weapons Plant - NNSA Is Helping Make It Happen | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission ...

  17. Microsoft Word - EIA-914 Instructions_Expiration Date 09202012...

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

    ENERGY INFORMATION ADMINISTRATION OMB No. 1905-0205 Washington, DC 20585 Expiration Date: 09202012 INSTRUCTIONS for FORM EIA-914 MONTHLY NATURAL GAS PRODUCTION REPORT PURPOSE...

  18. Property:Incentive/StartDateString | Open Energy Information

    Open Energy Info (EERE)

    Pages using the property "IncentiveStartDateString" Showing 25 pages using this property. (previous 25) (next 25) 3 30% Business Tax Credit for Solar (Vermont) +...

  19. STATEMENT OF COMPLIANCE PAYROLL NUILBER PAYROLL PAYMENT DATE...

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

    COMPLIANCE PAYROLL NUILBER PAYROLL PAYMENT DATE CONTRACT NUMBER 382246 1 411712014 ... (Tile) (1) That I pay or supervise the payment of the persons employed by Intermach, ...

  20. Dating of major normal fault systems using thermochronology-...

    Open Energy Info (EERE)

    Dating of major normal fault systems using thermochronology- An example from the Raft River detachment, Basin and Range, western United States Jump to: navigation, search OpenEI...

  1. "Title","Creator/Author","Publication Date","OSTI Identifier...

    Office of Scientific and Technical Information (OSTI)

    Date: 31-DEC-64","Maryland. Univ., College Park, MD (United States)","US Atomic Energy Commission (AEC)","PHYSICS; ANGULAR DISTRIBUTION; DEUTERON BEAMS; ELASTIC SCATTERING;...

  2. POLICY GUIDANCE MEMORANDUM #04 Setting Effective Date for New...

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

    of Energy's (DOE) policy for setting effective dates for newly hired employees and to ensure uniform application among DOE Headquarters, Elements and Field Human Resources Offices. ...

  3. DOE Guidance-Setting Effective Date for New Hires

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

    MEMORANDUM FOR HUMAN RESOURCES DIRECTORS FROM: SARA I. BONIL HUMAN CAPITAL OFFICER GUIDANCE MEMORANDUM4: SETTING EFFECTIVE DATE FOR NEW HIRES The purpose of this memorandum is to ...

  4. Operating data to In-Tank Solidification (ITS)-2 for January 1 to October 10, 1974

    SciTech Connect (OSTI)

    Reich, F.R., Westinghouse Hanford

    1996-08-02

    Data sheets containing date, time, feet above bottom,temperature, comments. Operating data to In-Tank Solidification (ITS)-2 for January 1 to October 10, 1974.

  5. Operations Office

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

    (~ii~,Richland Operations Office ~Z4TESO~Richland, Washington 99352 SEP 2 2009 CERTIFIED MAIL Ms. Sarah Washburn Heart of America Northwest 1314 N.E. 5 6 th Street Suite 100 Seattle, Washington 98105 Dear Ms. Washburn: FREEDOM OF INFORMATION ACT REQUEST (FOI 2009-0067) You requested, pursuant to the Freedom of Information Act (FOJA), the following documents relating to: 1 . "The authorization, decision to use, and actual use of any and all pesticides and herbicides anywhere within the

  6. Determination of Ash in Biomass: Laboratory Analytical Procedure (LAP); Issue Date: 7/17/2005

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

    Ash in Biomass Laboratory Analytical Procedure (LAP) Issue Date: 7/17/2005 A. Sluiter, B. Hames, R. Ruiz, C. Scarlata, J. Sluiter, and D. Templeton Technical Report NREL/TP-510-42622 January 2008 NREL is operated by Midwest Research Institute ● Battelle Contract No. DE-AC36-99-GO10337 National Renewable Energy Laboratory 1617 Cole Boulevard, Golden, Colorado 80401-3393 303-275-3000 * www.nrel.gov Operated for the U.S. Department of Energy Office of Energy Efficiency and Renewable Energy by

  7. Determination of Extractives in Biomass: Laboratory Analytical Procedure (LAP); Issue Date 7/17/2005

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

    Extractives in Biomass Laboratory Analytical Procedure (LAP) Issue Date: 7/17/2005 A. Sluiter, R. Ruiz, C. Scarlata, J. Sluiter, and D. Templeton Technical Report NREL/TP-510-42619 January 2008 NREL is operated by Midwest Research Institute ● Battelle Contract No. DE-AC36-99-GO10337 National Renewable Energy Laboratory 1617 Cole Boulevard, Golden, Colorado 80401-3393 303-275-3000 * www.nrel.gov Operated for the U.S. Department of Energy Office of Energy Efficiency and Renewable Energy by

  8. DOE - NNSA/NFO -- Photo Library OPERATION DOORSTEP

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

    Operation Doorstep NNSA/NFO Language Options U.S. DOE/NNSA - Nevada Field Office Photo Library - Operation Doorstep Operation Doorstep and Operation Cue. This video shows Federal Civil Defense Administration film footage. In the Operation Doorstep portion, footage shows blast and thermal effects on mannequins, automobiles, and wooden frame houses. [ Full Text ] Instructions: Click the photograph THUMBNAIL to view the photograph details Click the Category, Number, or Date table header links to

  9. ARM Operations Quarterly Report July 1 - September 30 2013 (Program...

    Office of Scientific and Technical Information (OSTI)

    Title: ARM Operations Quarterly Report July 1 - September 30 2013 This reports on the fourth quarter facility statistics. Authors: Voyles, Jimmy W Publication Date: 2013-10-14 OSTI ...

  10. Environmental Protection, Safety, and Health Protection Program for DOE Operations

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

    1980-05-05

    This order establishes the Environmental Protection, Safety, and Health Protection Program for Department of Energy (DOE) operations. Cancels Interim Management Directive No. 5001, Safety, Health And Environmental Protection dated 9-29-77.

  11. Environmental Protection, Safety, and Health Protection Program for DOE Operations

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

    1981-08-13

    This Order establishes the Environmental Protection, Safety. and Health Protection Program for Department of Energy (DOE) operations. Cancels DOE 5480.1, dated 5-5-1980, its chapters are not canceled. Canceled by DOE O 5480.1B

  12. Planning and Preparedness for Operational Emergencies

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

    1991-04-30

    To establish requirements for planning and prepardness for Operational Emergencies involving the Department of Energy (DOE) or requiring DOE assistance. Cancels DOE O 5500.3. Chg 1 dated Change 1 2-27-92. canceled by DOE O 151.1 of 9-25-1995.

  13. Calutron Operations | Y-12 National Security Complex

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

    Operations Calutron Operations

  14. Fermilab | Tevatron | 2011 Shutdown Event

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

    the Tevatron, which will take place from 3-5 p.m. in Wilson Hall and the surrounding area. ... and west entrances) via C-Road, then to Wilson Hall Horseshoe. 15 minutes 3 1315-1730 ...

  15. Franklin retirement date is set: 04/30/2012

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

    Announcements » Franklin retirement date is set: 04/30/2012 Franklin retirement date is set: 04/30/2012 March 6, 2012 by Helen He The Franklin (and its external login node Freedom) retirement date has been set to April 30, 2012. Below are the related schedules: Effective immediately: Software frozen except for critical updates Mon Apr 2: No new accounts will be created Thurs Apr 26, 23:59: Batch system is drained, batch queues are stopped (no jobs will be running at this point) Mon Apr 30: Last

  16. 2017 Solar Decathlon Announces Dates | Department of Energy

    Energy Savers [EERE]

    7 Solar Decathlon Announces Dates 2017 Solar Decathlon Announces Dates Addthis Description Below is the text version for the "2017 Solar Decathlon Announces Dates" video. Eric Escudero, EERE Digital Team: Hi everybody, I'm Eric Escudero with the EERE digital team. We're in Denver, Colorado, near the new commuter line that connects the airport to downtown. The video shows a shot of the Denver light rail system In just over a year from now, this place will be packed with people and

  17. Categorical Exclusion (CX) Determinations By Date | Department of Energy

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

    Date Categorical Exclusion (CX) Determinations By Date July 28, 2016 CX-100668 Categorical Exclusion Determination A New Remote Communications Link to Reduce Residential PV Solar Costs Award Number: DE-EE0007592 CX(s) Applied: A9, B5.15 Solar Energy Technology Office Date: 7/26/2016 Location(s): CA Office(s): Golden Field Office July 20, 2016 CX-100667 Categorical Exclusion Determination Notice of Final Rulemaking Regarding Energy Conservation Standards for Ceiling Fans RIN 1904-AD28 CX(s)

  18. REEE Solicitation Part II Due Date | Department of Energy

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

    12:01AM to 11:59PM EST RENEWABLE ENERGY AND EFFICENT ENERGY PROJECTS SOLICITATION PART II DUE DATE Learn more about the Renewable Energy and Efficent Energy Projects Solicitation...

  19. Adv. Fossil Solicitation Part II Due Date | Department of Energy

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

    January 29, 2016 12:01AM to 11:59PM EST ADVANCED FOSSIL ENERGY PROJECTS SOLICITATION PART II DUE DATE Learn more about the Advanced Fossil Energy Projects Solicitation...

  20. REEE Solicitation Part II Due Date | Department of Energy

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

    12:01AM to 11:59PM EDT RENEWABLE ENERGY AND EFFICENT ENERGY PROJECTS SOLICITATION PART II DUE DATE Learn more about the Renewable Energy and Efficent Energy Projects...

  1. PLEASE NOTE THURSDAY DATE - COLLOQUIUM: Professor Ralph Roskies...

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

    May 23, 2013, 4:15pm to 5:30pm Colloquia MBG Auditorium PLEASE NOTE THURSDAY DATE - COLLOQUIUM: Professor Ralph Roskies - "Big Data at the Pittsburgh Supercomputing Center" ...

  2. United States Government Department of Energy Memorandum DATE...

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

    Memorandum DATE: AliNOF: SUBJECT: DEC 2 o 2010 NE-32 Delegation of Acquisition Executive (AE) Authority for the Material Security and Consolidation Project (08-D-702) ro: Richard...

  3. Property:Project Start Date | Open Energy Information

    Open Energy Info (EERE)

    Date" Showing 25 pages using this property. (previous 25) (next 25) M MHK Projects40MW Lewis project + 112012 + MHK ProjectsADM 3 + 112010 + MHK ProjectsADM 4 + 112010 +...

  4. From: MCKEOWN D To: Congestion Study Comments Date:

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

    MCKEOWN D To: Congestion Study Comments Date: Friday, September 19, 2014 2:18:11 AM I am ... Energy Transmission Corridors. Thank you, Mary McKeown 3502 Highway M Moberly, MO 65270

  5. Home Energy Score: Analysis & Improvements to Date | Department...

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

    Home Energy Score: Analysis & Improvements to Date, a presentation from the U.S. Department of Energy, by Joan Glickman Senior AdvisorProgram Manager, Home Energy Score, July 24, ...

  6. NTSF Spring 2013 Save The Date | Department of Energy

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

    Services » Waste Management » Packaging and Transportation » National Transportation Stakeholders Forum » National Transportation Stakeholders Forum (NTSF) Charter » NTSF Spring 2013 Save The Date NTSF Spring 2013 Save The Date Please mark your calendar to attend the next meeting of the U.S. Department of Energy (DOE) National Transportation Stakeholders Forum (NTSF) scheduled for May 14-16, 2013. This annual event will be held at the Hyatt Regency Hotel, located near the downtown business

  7. Operational results of shaft repair by installing stave type cooler at Kimitsu Nos. 3 and 4 blast furnaces

    SciTech Connect (OSTI)

    Oda, Hiroshi; Amano, Shigeru; Sakamoto, Aiichiro; Anzai, Osamu; Nakagome, Michiru; Kuze, Toshisuke; Imuta, Akira

    1997-12-31

    Nos. 3 and 4 blast furnaces in Nippon Steel Corporation Kimitsu Works were both initially fitted with cooling plate systems. With the aging of each furnace, the damage to their respective inner-shaft profiles had become serious. Thus, in order to prevent operational change and prolong the furnace life, the inner-shaft profile of each furnace was repaired by replacing the former cooling plate system with the stave type cooler during the two-week-shutdowns. With this repair, stability of burden descent and gas flow near the wall part of the furnace have been achieved. Thus the prolongation of the furnace life is naturally expected.

  8. HEl'lORANDUtl TO: FILE DATE& ALTERNATE Ya NAnE~---

    Office of Legacy Management (LM)

    ^I ,, ".. , ,' a . . _- HEl'lORANDUtl TO: FILE DATE& ALTERNATE Ya NAnE~--- Owner ccntacted TYPE OF OPERATION ----------_--____ 0 Research 81 Development 0 Production scale testing Cl Pilot Scale 0 Bench Scale Process 0 Theoretical Studies 0 Sample 81 Analysis -'* x Production 0 Disposal/Storage Ivp_E~EJx!!IEecI 0 Prim0 0 Subcontract& )rq Purchase Oider J4 .~ Facility Type M Manuiacturi 0 University 0 Research Or 0 Government 0 Other ----- cl Other informat + fixed fer, u f b%wm!s

  9. Operation and performance of the Supercritical Fluids Reactor (SFR)

    SciTech Connect (OSTI)

    Hanush, R.G.; Rice, S.F.; Hunter, T.B.; Aiken, J.D.

    1995-11-01

    The Supercritical Fluids Reactor (SFR) at Sandia National Laboratories, CA has been developed to examine and solve engineering, process, and fundamental chemistry issues regarding the development of supercritical water oxidation (SCWO). This report details the experimental apparatus, procedures, analytical methods used in these experiments, and performance characteristics of the reactor. The apparatus consists of pressurization, feed, preheat, reactor, cool down, and separation subsystems with ancillary control and data acquisition hardware and software. Its operating range is from 375 - 650{degrees} at 3250 - 6300 psi with resident times from 0.09 to 250 seconds. Procedures required for experimental operations are described. They include maintenance procedures conducted between experiments, optical alignment for acquisition of spectroscopic data, setup of the experiment, reactor start up, experimental operations, and shutdown of apparatus. Analytical methods used are Total Organic Carbon analysis, Gas Chromatography, ion probes, pH probes, turbidity measurements and in situ Raman spectroscopy. Experiments conducted that verify the accuracy of measurement and sampling methods are described.

  10. ARM - AMF2 Operations

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

    and Contacts Management and Operations Operations Overview ARM Links BCR | ECR ECO, EWO Extraview PIF, CAR, DQR & DQPR Operations Status System i.arm.gov AMF2 Deployment...

  11. Line Equipment Operator

    Broader source: Energy.gov [DOE]

    There are several Line Equipment Operator positions located in Washington and Oregon. A successful candidate in this position will perform Line Equipment Operator work operating trucks and all...

  12. Sandia/EPRI PV Symposium - Save the Date!

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

    Sandia/EPRI PV Symposium - Save the Date! Save the Date! Sandia/EPRI 2014 PV Systems Symposium (May 5-7, 2014) May 5-6 at the Biltmore Hotel in Santa Clara, CA May 7 at EPRI Headquarters in Palo Alto, CA Sandia National Laboratories and the Electric Power Research Institute (EPRI) are delighted to host this symposium on technical issues related to PV systems and technologies. Core areas of focus will include PV performance modeling, distribution hosting capacity and screening methods, component

  13. RADIOCARBON DATING, MEMORIES AND HOPES W.F, Libby

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

    RADIOCARBON DATING, MEMORIES AND HOPES W.F, Libby Department of Chemistry* and Institute of Geophysics and Planetary Physics, Uni^sjersity of California Los Angeles --(tm)- HISTORY The cosmic ray production of radiocarbon in matter is the basis of radiocarbon dating. It is made from the most abundant atom in air^nitrogen of mass fourteen. Radiocarbon-- carbon-l4 or C-- lasts 83OO years on the average (see note on radioactive decay for explanation on "half life" and "average

  14. Impact of Distributed Wind on Bulk Power System Operations in ISO-NE: Preprint

    SciTech Connect (OSTI)

    Brancucci Martinez-Anido, C.; Hodge, B. M.; Palchak, D.; Miettinen, J.

    2014-09-01

    The work presented in this paper aims to study the impact of a range of penetration levels of distributed wind on the operation of the electric power system at the transmission level. This paper presents a case study on the power system in Independent System Operator New England. It is analyzed using PLEXOS, a commercial power system simulation tool. The results show that increasing the integration of distributed wind reduces total variable electricity generation costs, coal- and gas-fired electricity generation, electricity imports, and CO2 emissions, and increases wind curtailment. The variability and uncertainty of wind power also increases the start-up and shutdown costs and ramping of most conventional power plants.

  15. Operating Experience Committee Charter

    Broader source: Energy.gov [DOE]

    The Operating Experience Committee (OEC) charter provides a description of the OEC's purpose, background, membership, functions, and operations.

  16. 07\pDcmn:N Actionee: Dorothy Riehie QDocument Date: 07/21/2009 Due Date: NO ACTION

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

    \pDcmn:N Actionee: Dorothy Riehie QDocument Date: 07/21/2009 Due Date: NO ACTION 4 Author: MORETZ 41 Addressee: RIEHLE DC TA2ES 01 Title: Sallee vs. Crown Cork & Seal Company, Inc., et al. DIR DIV NAME DIR DIV NAME MGR AMRC DEP AMSE AMA EMD FMD OOD HRM SED PRO 0CC AMCP OCE Riehie, Dorothy (Actionee) AMMS ORP ISI PNSO PIC RLCI SES Comments: ORIGINAL TO DC RIEHLE Records Schedule Information: Need to separate granted and denied requests. Scan?: Yes Sensitive?: Yes Sensitive Attachments IDMS

  17. Document: 1095-0005 Actionee: Dorothy Riehie * Document Date: 10/21/2009 Due Date: NO ACTION

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

    v~il T op Document: 1095-0005 Actionee: Dorothy Riehie * Document Date: 10/21/2009 Due Date: NO ACTION i 1 4Author: EVENSON BG 9b Addressee: RIEHLE DC ATE S O' Title: FOIA Request for Print of May, 1943 Aerial Photographs L26-12 and L26-3 DIR DIV NAME DIR DIV NAME MGR AMRC DEP AMSE AMA EMD FMD OOD HRM SED PRO 0CC AMCP OCE Riehie, Dorothy (Actionee) AMMS ORP ISI PNSO PIC RLCI SES Comments: Original given to Dorothy Riehie. Records Schedule Information: ADM-1 .28.1 Scan?: Yes Sensitive?: No

  18. Upcoming Implementation Date for New Hazard Communication Standard

    Broader source: Energy.gov [DOE]

    The upcoming implementation date for the new Hazard Communication Standard requires all Federal and Contractor employees with hazardous chemicals in their workplace must be in compliance with all modified revisions of this final rule, except: The distributors shall not ship containers labeled by the chemical manufacturer or importer unless it has been modified to comply with paragraph (f)(1) of the Hazard Communication Standard.

  19. Microsoft Word - Port of Call Dates.docx

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

    - 3 1 Sep 1 2---14 Sep 2 6 - 2 8 Oct 1 0---12 ( Last P ort C all) Tentative Honolulu in port dates: May 1 5---16 May 2 9 --- 30 Jun 1 2---13 Jun 2 6 - 2 7 Jul 1 0 ---11 Jul 2...

  20. Save the Date: Office of Indian Energy Program Review

    Broader source: Energy.gov [DOE]

    Save the date for the Office of Indian Energy Program Review! The annual Program Review provides tribes with an opportunity to meet and learn from other tribes that are pursuing energy sufficiency and reduced carbon pollution through energy efficiency and/or renewable energy development, and to share in each other's successes.

  1. DATE: REPLY TO Al-l' N OF: SUBJECT: TO:

    Office of Legacy Management (LM)

    oy& IL4 2%?5- EFG (07.90) ' Uni,ted bates Government memorandum Department of Energy Em 7:3 (5 2L-e DATE: REPLY TO Al-l' N OF: SUBJECT: TO: - MAR 1 1 1991 EM-421 Authority ...

  2. and Operations | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    and Operations

  3. Property:OpenEI/UtilityRate/EndDate | Open Energy Information

    Open Energy Info (EERE)

    EndDate Jump to: navigation, search This is a property of type Date. Name: End Date Retrieved from "http:en.openei.orgwindex.php?titleProperty:OpenEIUtilityRate...

  4. Property:OpenEI/UtilityRate/StartDate | Open Energy Information

    Open Energy Info (EERE)

    StartDate Jump to: navigation, search This is a property of type Date. Name: Start Date Retrieved from "http:en.openei.orgwindex.php?titleProperty:OpenEIUtilityRate...

  5. Human Behavior, Standards and Tools to Improve Design & Operation

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

    Human Behavior, Standards and Tools to Improve Design & Operation 2014 Building Technologies Office Peer Review Tianzhen Hong, thong@lbl.gov Lawrence Berkeley National Laboratory Project Summary Timeline: Start date: 10/1/2012 planned, 1/1/2013 actual Planned end date: 9/30/2015 Key Milestones 1. Behavior data mining and models; 6/28/2013 2. Behavior framework; 12/20/2013 3. IEA EBC Annex 66 launched; 11/14/2013 Budget: Total DOE $ to date: $380K (FY13 + FY14) Total future DOE $: $220K, FY15

  6. "Title","Creator/Author","Publication Date","OSTI Identifier...

    Office of Scientific and Technical Information (OSTI)

    DRAFT COOLING TOWERS; PERFORMANCE; SIMULATION; COST; DESIGN; HEAT TRANSFER; OPERATION; WATER REQUIREMENTS; COOLING TOWERS; ENERGY TRANSFER; MECHANICAL STRUCTURES; TOWERS...

  7. DOE - NNSA/NFO -- Photo Library OPERATION TEAPOT

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

    Operation Teapot NNSA/NFO Language Options U.S. DOE/NNSA - Nevada Field Office Photo Library - Operation Teapot Operation Teapot consisted of 14 nuclear tests. The goal of the series was to test nuclear devices for possible inclusion in the nuclear weapons stockpile; improve military tactics, equipment and training; and study civil defense requirements. [ Full Text ] Instructions: Click the photograph THUMBNAIL to view the photograph details Click the Category, Number, or Date table header links

  8. Memorandum A. J. Rizzo, Chief TO : Operational Safety Branch

    Office of Legacy Management (LM)

    j Memorandum A. J. Rizzo, Chief TO / : Operational Safety Branch Harold Glauberman, ?a FROM : Operational Safety Branch ' I DATE: September 30, 1966 REMOVAL OF CONTAMINATED EQUlPMEHT AT THE CANEL FACILITY SUBJECT: MI DDLETOWN, CONNECT I CUT' INTRODUCTION The decision to terminate AEC contract activities at the CANEL facility introduced the need to dispose of radioactively contaminated equipment and materials so as to permit release of the facilities. As a result, -' . the Operational Safety

  9. Earned Value Management System (EVMS) Corrective Action Standard Operating Procedure

    Office of Environmental Management (EM)

    Corrective Action Standard Operating Procedure (ECASOP) Issued by Office of Project Management, Oversight, and Assessments (PMOA) PM-1 September 21, 2015 DEPARTMENT OF ENERGY EVMS CORRECTIVE ACTION SOP SEPTEMBER 21, 2015 ii Earned Value Management System (EVMS) Corrective Action (CA) Standard Operating Procedure (ECASOP) OPR: PM-30 Issue Date: September 21, 2015 1. PURPOSE. This EVMS Corrective Action Standard Operating Procedure (ECASOP) serves as a primary reference for PMOA PM-1 for

  10. Property:NEPA TMP/EISFederalRegisterDate | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search This is a property of type Date. Retrieved from "http:en.openei.orgwindex.php?titleProperty:NEPATMPEISFederalRegisterDate&oldid637471...

  11. Property:NEPA TMP/PreApplicationMeetingDate | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search This is a property of type Date. Retrieved from "http:en.openei.orgwindex.php?titleProperty:NEPATMPPreApplicationMeetingDate&oldid637468...

  12. Monitored Geologic Repository Operations Monitoring and Control System Description Document

    SciTech Connect (OSTI)

    E.F. Loros

    2000-06-29

    The Monitored Geologic Repository Operations Monitoring and Control System provides supervisory control, monitoring, and selected remote control of primary and secondary repository operations. Primary repository operations consist of both surface and subsurface activities relating to high-level waste receipt, preparation, and emplacement. Secondary repository operations consist of support operations for waste handling and treatment, utilities, subsurface construction, and other selected ancillary activities. Remote control of the subsurface emplacement operations, as well as, repository performance confirmation operations are the direct responsibility of the system. In addition, the system monitors parameters such as radiological data, air quality data, fire detection status, meteorological conditions, unauthorized access, and abnormal operating conditions, to ensure a safe workplace for personnel. Parameters are displayed in a real-time manner to human operators regarding surface and subsurface conditions. The system performs supervisory monitoring and control for both important to safety and non-safety systems. The system provides repository operational information, alarm capability, and human operator response messages during emergency response situations. The system also includes logic control to place equipment, systems, and utilities in a safe operational mode or complete shutdown during emergency response situations. The system initiates alarms and provides operational data to enable appropriate actions at the local level in support of emergency response, radiological protection response, evacuation, and underground rescue. The system provides data communications, data processing, managerial reports, data storage, and data analysis. This system's primary surface and subsurface operator consoles, for both supervisory and remote control activities, will be located in a Central Control Center (CCC) inside one of the surface facility buildings. The system

  13. Age Dating of Mixed SNM--Preliminary Investigations

    SciTech Connect (OSTI)

    Yuan, D., Guss, P. P., Yfantis, E., Klingensmith, A., Emer, D.

    2011-12-01

    Recently we investigated the nuclear forensics problem of age determination for mixed special nuclear material (SNM). Through limited computational mixing experiments and interactive age analysis, it was observed that age dating results are generally affected by the mixing of samples with different assays or even by small radioactive material contamination. The mixing and contamination can be detected through interactive age analysis, a function provided by the Decay Interaction, Visualization and Analysis (DIVA) software developed by NSTec. It is observed that for mixed SNM with two components, the age estimators typically fall into two distinct clusters on the time axis. This suggests that averaging or other simple statistical methods may not always be suitable for age dating SNM mixtures. Instead, an interactive age analysis would be more suitable for age determination of material components of such SNM mixtures. This work was supported by the National Center for Nuclear Security (NCNS).

  14. WEATHERIZATION PROGRAM NOTICE 16-XX EFFECTIVE DATE: SUBJECT: MULTIFAMILY WEATHERIZATION

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

    6-XX EFFECTIVE DATE: SUBJECT: MULTIFAMILY WEATHERIZATION PURPOSE: To provide Grantees with consolidated guidance on previously issued Weatherization Program Notices (WPNs) on weatherizing multifamily buildings in the Weatherization Assistance Program (WAP). This supersedes WPN 10-7 and WPN 11-9 SCOPE: The provisions of this guidance apply to Grantees applying for financial assistance under the Department of Energy (DOE) WAP. LEGAL AUTHORITY: Title IV, Energy Conservation and Production Act, as

  15. Home Energy Score: Analysis & Improvements to Date

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

    Home Energy Score: � Analysis & Improvements to Date � Joan Glickman Senior Advisor/Program Manager U.S. Department of Energy July 24, 2012 1 eere.energy.gov Presentation Overview 1) Background 2) Program Improvements 3) Analysis: Efficacy of Tool & Program - Asset Perturbations - Behavior Perturbations - Estimated Energy Use vs. Actual Energy Use (from utility bills) - Time Required for Assessment and Scoring - Blower Door Test Analysis 4) Next Steps & Ongoing Analysis 2

  16. Richland Operations Office - Hanford Site

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

    Richland Operations Office Richland Operations Office Richland Operations Office River Corridor Central Plateau Groundwater Mission Support Newsroom Richland Operations Office...

  17. Increasing the reliability of the shutdown of 500 - 750-kV overhead lines equipped with shunt reactors in an unsuccessful three-phase automatic repeated closure cycle

    SciTech Connect (OSTI)

    Kuz'micheva, K. I.; Merzlyakov, A. S.; Fokin, G. G.

    2013-05-15

    The reasons for circuit-breaker failures during repeated disconnection of 500 - 750 kV overhead lines with shunt reactors in a cycle of unsuccessful three-phase automatic reconnection (TARC) are analyzed. Recommendations are made for increasing the operating reliability of power transmission lines with shunt reactors when there is unsuccessful reconnection.

  18. Massachusetts Natural Gas Underground Storage Net Withdrawals All Operators

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

    (Million Cubic Feet) Net Withdrawals All Operators (Million Cubic Feet) Massachusetts Natural Gas Underground Storage Net Withdrawals All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's -174 -102 253 1970's -200 -96 -1,074 2,468 1,707 -2,185 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring

  19. Alaska Natural Gas Underground Storage Injections All Operators (Million

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

    Cubic Feet) Underground Storage Injections All Operators (Million Cubic Feet) Alaska Natural Gas Underground Storage Injections All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 16,327 13,253 15,555 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring Pages: Injections of Natural Gas into

  20. Alaska Natural Gas Underground Storage Net Withdrawals All Operators

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

    (Million Cubic Feet) Net Withdrawals All Operators (Million Cubic Feet) Alaska Natural Gas Underground Storage Net Withdrawals All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's -16,327 -13,253 -15,555 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring Pages: Net Withdrawals of Natural Gas

  1. Connecticut Natural Gas Underground Storage Injections All Operators

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

    (Million Cubic Feet) Underground Storage Injections All Operators (Million Cubic Feet) Connecticut Natural Gas Underground Storage Injections All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 683 740 746 1990's 0 0 0 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring Pages: Injections of

  2. Connecticut Natural Gas Underground Storage Net Withdrawals All Operators

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

    (Million Cubic Feet) Net Withdrawals All Operators (Million Cubic Feet) Connecticut Natural Gas Underground Storage Net Withdrawals All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's -242 501 1,271 1990's 0 0 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring Pages: Net Withdrawals of

  3. Delaware Natural Gas Underground Storage Injections All Operators (Million

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

    Cubic Feet) Underground Storage Injections All Operators (Million Cubic Feet) Delaware Natural Gas Underground Storage Injections All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's 1,274 1,500 179 1970's 391 189 255 2,012 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring Pages: Injections

  4. Delaware Natural Gas Underground Storage Net Withdrawals All Operators

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

    (Million Cubic Feet) Net Withdrawals All Operators (Million Cubic Feet) Delaware Natural Gas Underground Storage Net Withdrawals All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's -294 -245 699 1970's 211 -189 -255 -549 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring Pages: Net

  5. Georgia Natural Gas Underground Storage Injections All Operators (Million

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

    Cubic Feet) Underground Storage Injections All Operators (Million Cubic Feet) Georgia Natural Gas Underground Storage Injections All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 123 366 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring Pages: Injections of Natural Gas into Underground

  6. Georgia Natural Gas Underground Storage Net Withdrawals All Operators

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

    (Million Cubic Feet) Net Withdrawals All Operators (Million Cubic Feet) Georgia Natural Gas Underground Storage Net Withdrawals All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's -90 -339 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring Pages: Net Withdrawals of Natural Gas from

  7. Idaho Natural Gas Underground Storage Injections All Operators (Million

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

    Cubic Feet) Underground Storage Injections All Operators (Million Cubic Feet) Idaho Natural Gas Underground Storage Injections All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 112 395 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring Pages: Injections of Natural Gas into Underground

  8. Idaho Natural Gas Underground Storage Net Withdrawals All Operators

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

    (Million Cubic Feet) Net Withdrawals All Operators (Million Cubic Feet) Idaho Natural Gas Underground Storage Net Withdrawals All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's -112 -395 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring Pages: Net Withdrawals of Natural Gas from Underground

  9. Rhode Island Natural Gas Underground Storage Injections All Operators

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

    (Million Cubic Feet) Underground Storage Injections All Operators (Million Cubic Feet) Rhode Island Natural Gas Underground Storage Injections All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 97 243 137 1990's 0 0 0 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring Pages: Injections of

  10. Rhode Island Natural Gas Underground Storage Net Withdrawals All Operators

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

    (Million Cubic Feet) Net Withdrawals All Operators (Million Cubic Feet) Rhode Island Natural Gas Underground Storage Net Withdrawals All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's -6 411 541 1990's 0 0 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring Pages: Net Withdrawals of Natural

  11. South Carolina Natural Gas Underground Storage Injections All Operators

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

    (Million Cubic Feet) Underground Storage Injections All Operators (Million Cubic Feet) South Carolina Natural Gas Underground Storage Injections All Operators (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 48 80 70 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/31/2016 Next Release Date: 9/30/2016 Referring Pages: Injections of Natural Gas

  12. "Title","Creator/Author","Publication Date","OSTI Identifier...

    Office of Scientific and Technical Information (OSTI)

    reduction associated with co-locating this type of operation at a municipal wastewater treatment plant (WWTP); '' To develop a business case or model for...

  13. "Title","Creator/Author","Publication Date","OSTI Identifier...

    Office of Scientific and Technical Information (OSTI)

    76DP00789",,"Conference",,,"Conference: 3. annual systems simulation, economic analysissolar heating and cooling operational results conference, Reno, NV, USA, 27 Apr...

  14. "Title","Creator/Author","Publication Date","OSTI Identifier...

    Office of Scientific and Technical Information (OSTI)

    clustering is generally considered as an efficient and scalable way to facilitate the management and operation of such large-scale networks and minimize the total energy...

  15. "Title","Creator/Author","Publication Date","OSTI Identifier...

    Office of Scientific and Technical Information (OSTI)

    Matrix multiplication operations with data pre-conditioning in a high performance computing architecture","Eichenberger, Alexandre E; Gschwind, Michael K; Gunnels, John...

  16. Uranium Marketing Annual Report - Release Date: May 31, 2011

    Gasoline and Diesel Fuel Update (EIA)

    1. Unfilled uranium market requirements of owners and operators of U.S. civilian nuclear ... Source: U.S. Energy Information Administration, Form EIA-858 "Uranium Marketing Annual ...

  17. OP-PR-0003-001.PDF

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

    OP-PR-0003-001.doc Lights Out (w/o Wiggler) Date: 2000/12/08 1. In the Operations Room, (room 202), the workstation to the right, as you enter the room, is set up to accept the shutdown (Lights Out) process. 2. If the workstation is dark, press the "space" key. This action will awaken the screen. 3. The screen will have a window named "SHUTDOWN PAGE". It will contain red and possibly a few green buttons. At the bottom there will be one button marked "SHUTDOWN". 4.

  18. ENERGY STAR Appliance Verification Testing- Pilot Program Summary Report dated February 3, 2012

    Broader source: Energy.gov [DOE]

    This document is ENERGY STAR Appliance Verification Testing - Pilot Program Summary Report dated February 3, 2012

  19. FAQ's for: ENERGY STAR Verification Testing Pilot Program dated December 2010

    Office of Energy Efficiency and Renewable Energy (EERE)

    This document is the FAQ's for the ENERGY STAR Verification Testing Pilot Program dated December 2010

  20. Facility design, construction, and operation

    SciTech Connect (OSTI)

    1995-04-01

    France has been disposing of low-level radioactive waste (LLW) at the Centre de Stockage de la Manche (CSM) since 1969 and now at the Centre de Stockage de l`Aube (CSA) since 1992. In France, several agencies and companies are involved in the development and implementation of LLW technology. The Commissariat a l`Energie Atomic (CEA), is responsible for research and development of new technologies. The Agence National pour la Gestion des Dechets Radioactifs is the agency responsible for the construction and operation of disposal facilities and for wastes acceptance for these facilities. Compagnie Generale des Matieres Nucleaires provides fuel services, including uranium enrichment, fuel fabrication, and fuel reprocessing, and is thus one generator of LLW. Societe pour les Techniques Nouvelles is an engineering company responsible for commercializing CEA waste management technology and for engineering and design support for the facilities. Numatec, Inc. is a US company representing these French companies and agencies in the US. In Task 1.1 of Numatec`s contract with Martin Marietta Energy Systems, Numatec provides details on the design, construction and operation of the LLW disposal facilities at CSM and CSA. Lessons learned from operation of CSM and incorporated into the design, construction and operating procedures at CSA are identified and discussed. The process used by the French for identification, selection, and evaluation of disposal technologies is provided. Specifically, the decisionmaking process resulting in the change in disposal facility design for the CSA versus the CSM is discussed. This report provides` all of the basic information in these areas and reflects actual experience to date.