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Sample records for mohawk pwr corp

  1. PP-190 Niagara Mohawk Power Corporation | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    190 Niagara Mohawk Power Corporation PP-190 Niagara Mohawk Power Corporation Presidential permit authorizing Niagara Mohawk Power Corporation to construct, operate, and maintain electric transmission facilitates at the U.S-Canadian border. PP-190 Niagara Mohawk Power Corporation (21.94 KB) More Documents & Publications PP-230-2 International Transmission Company Proposed Open Access Requirement for International Electric Transmission Facilities and Delegation to the Federal Energy Regulatory

  2. Brookfield Renewable Power Corp formerly Brascan Power Corp ...

    OpenEI (Open Energy Information) [EERE & EIA]

    Brookfield Renewable Power Corp formerly Brascan Power Corp Jump to: navigation, search Name: Brookfield Renewable Power Corp (formerly Brascan Power Corp) Place: Toronto, Ontario,...

  3. St. Regis Mohawk Tribe Paves the Way to a Sustainable Future; Kicks Off

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Community Solar Initiative | Department of Energy St. Regis Mohawk Tribe Paves the Way to a Sustainable Future; Kicks Off Community Solar Initiative St. Regis Mohawk Tribe Paves the Way to a Sustainable Future; Kicks Off Community Solar Initiative June 12, 2015 - 1:51pm Addthis Six photovoltaic arrays generate 32 kilowatts of energy to power 20 units at the Akwesasne Housing Authority’s (AHA) Sunrise Acres housing complex on the St. Regis Mohawk Reservation. Pictured from left to right

  4. Review of integrated resource bidding at Niagara Mohawk

    SciTech Connect

    Goldman, C.A.; Busch, J.F.; Kahn, E.P.; Stoft, S.S.; Cohen, S.

    1992-05-01

    In June 1988, the New York Public Service Commission (PSC) ordered the state's investor-owned utilities to develop competitive bidding programs that included both supply and demandside resource options. The New York State Energy Research Development Authority (NYSERDA), the New York Department of Public Service, and the Department of Energy's Integrated Resource Planning program asked Lawrence Berkeley Laboratory (LBL) to review the integrated bidding processes of two New York utilities, Niagara Mohawk and Consolidated Edison. This interim report focuses on Niagara Mohawk (NMPC). In terms of overall approach, our analysis is intended as a critical review of a large-scale experiment in competitive resource acquisition implemented by New York utilities at the direction of their state regulators. The study is not a formal impact or process evaluation. Based on priorities established jointly with project sponsors, the report focuses on selected topics: analysis of the two-stage scoring system used by NMPC, ways that the scoring system can be improved, an in-depth review of the DSM bidding component of the solicitation including surveys of DSM bidders, relationship between DSM bidding and other utility-sponsored DSM programs, and major policy issues that arise in the design and implementation of competitive resource procurements. The major findings of this report are: NMPC's solicitation elicited an impressive response from private power developers and energy service companies. In the initial ranking of bids, DSM projects were awarded significantly more points on price and environmental factors compared to supply-side bids. NMPC's scoring system gave approximately twice as much weight nominally to price as to non-price factors (850 vs. 460 points).

  5. Review of integrated resource bidding at Niagara Mohawk

    SciTech Connect

    Goldman, C.A.; Busch, J.F.; Kahn, E.P.; Stoft, S.S.; Cohen, S.

    1992-05-01

    In June 1988, the New York Public Service Commission (PSC) ordered the state`s investor-owned utilities to develop competitive bidding programs that included both supply and demandside resource options. The New York State Energy Research & Development Authority (NYSERDA), the New York Department of Public Service, and the Department of Energy`s Integrated Resource Planning program asked Lawrence Berkeley Laboratory (LBL) to review the integrated bidding processes of two New York utilities, Niagara Mohawk and Consolidated Edison. This interim report focuses on Niagara Mohawk (NMPC). In terms of overall approach, our analysis is intended as a critical review of a large-scale experiment in competitive resource acquisition implemented by New York utilities at the direction of their state regulators. The study is not a formal impact or process evaluation. Based on priorities established jointly with project sponsors, the report focuses on selected topics: analysis of the two-stage scoring system used by NMPC, ways that the scoring system can be improved, an in-depth review of the DSM bidding component of the solicitation including surveys of DSM bidders, relationship between DSM bidding and other utility-sponsored DSM programs, and major policy issues that arise in the design and implementation of competitive resource procurements. The major findings of this report are: NMPC`s solicitation elicited an impressive response from private power developers and energy service companies. In the initial ranking of bids, DSM projects were awarded significantly more points on price and environmental factors compared to supply-side bids. NMPC`s scoring system gave approximately twice as much weight nominally to price as to non-price factors (850 vs. 460 points).

  6. AmeriCorps National Civilian Community Corps Webinar

    Energy.gov [DOE]

    AmeriCorps National Civilian Community Corps Webinar, from the U.S. Department of Energy's Better Buildings Neighborhood Program.

  7. Vermont Yankee Nucl Pwr Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Utility Location Yes Ownership I NERC Location NPCC NERC NPCC Yes ISO NE Yes Activity Wholesale Marketing Yes This article is a stub. You can help OpenEI by expanding it. Utility...

  8. Keosauqua Municipal Light & Pwr | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Keosauqua Municipal Light & Pwr Jump to: navigation, search Name: Keosauqua Municipal Light & Pwr Place: Iowa Phone Number: 319-293-3406 Website: villagesofvanburen.comdirecto...

  9. Zephyr Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: Zephyr Corp Place: Tokyo, Tokyo, Japan Zip: 151-0061 Sector: Solar, Wind energy Product: Zephyr Corp is a small micro wind and solar power...

  10. Hohsen Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Hohsen Corp Jump to: navigation, search Name: Hohsen Corp Place: Osaka, Osaka, Japan Zip: 542-0081 Sector: Solar Product: Testing and maufacturing equipment maker for batteries,...

  11. Kyocera Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: Kyocera Corp Place: Kyoto, Kyoto, Japan Zip: 612-8501 Product: Japanese manufacturer of fine ceramic and electric components; vertically...

  12. Shimadzu Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Shimadzu Corp Jump to: navigation, search Name: Shimadzu Corp Place: Kyoto, Kyoto, Japan Zip: 654-8511 Sector: Solar Product: Japanese manufacturer measuring, medical and...

  13. Kyosemi Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Kyosemi Corp Jump to: navigation, search Name: Kyosemi Corp Place: Kyoto, Kyoto, Japan Zip: 612 8201 Sector: Solar Product: Japanese Kyocera's arm that manufactures...

  14. Ferrotec Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Ferrotec Corp Jump to: navigation, search Name: Ferrotec Corp Place: Tokyo, Tokyo, Japan Zip: 104 0031 Sector: Solar Product: Japanese manufacturer of precision systems for solar...

  15. Meidensha Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Meidensha Corp Jump to: navigation, search Name: Meidensha Corp Place: Tokyo, Tokyo, Japan Zip: 141-6029 Product: Japanese manufacturer of mainly power generating system,...

  16. TKX Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    TKX Corp Jump to: navigation, search Name: TKX Corp Place: Osaka, Japan Zip: 543 0011 Product: Japanese manufacturer of abrasive products such as grinding wheels; manufactures...

  17. Toshiba Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Toshiba Corp Jump to: navigation, search Name: Toshiba Corp Place: Tokyo, Tokyo, Japan Zip: 105-8001 Product: Japan-based, worldwide electronic and electrical products giant, plays...

  18. Ebara Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Ebara Corp Jump to: navigation, search Name: Ebara Corp Place: Tokyo, Tokyo, Japan Zip: 144-8510 Product: Japan-based manufacturer of fluid systems, precision machineries and...

  19. Mascoma Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Mascoma Corp Jump to: navigation, search Name: Mascoma Corp Place: Cambridge, Massachusetts Zip: 2142 Product: Bioethanol start-up company making ethanol from corn stover on a...

  20. GEMZ Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Name: GEMZ Corp Place: Spring Valley, New York Zip: 10977 Sector: Carbon, Hydro, Hydrogen Product: Holding company for International Nanotechnology Corp, which is developing...

  1. Kebaili Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search Name: Kebaili Corp Place: Irvine, California Zip: CA 92612- Sector: Hydro, Hydrogen Product: Kebaili Corp is a Southern-California based high technology company...

  2. MicroPlanet Technology Corp formerly HF Capital Corp | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Technology Corp formerly HF Capital Corp Jump to: navigation, search Name: MicroPlanet Technology Corp (formerly HF Capital Corp) Place: Seattle, Washington Zip: 98104 Sector:...

  3. Lab-Corps

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    in the Clean Energy Trust Challenge w over 1M of investment awards. 4 * Using Lab-Corps methods as part of T2M in my proposals * New relationships within Argonne * New ...

  4. Preliminary study on direct recycling of spent PWR fuel in PWR...

    Office of Scientific and Technical Information (OSTI)

    Preliminary study on direct recycling of spent PWR fuel in PWR system Citation Details ... conference on advances in nuclear science and engineering, Bali (Indonesia), 14-17 ...

  5. Capstone Turbine Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Turbine Corp Jump to: navigation, search Name: Capstone Turbine Corp Place: Chatsworth, California Zip: 91311 Product: Capstone Turbine Corp produces low-emission microturbine...

  6. Biofuels Power Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Power Corp Jump to: navigation, search Name: Biofuels Power Corp Place: The Woodlands, Texas Zip: 77380 Sector: Biofuels, Renewable Energy Product: Biofuels Power Corp produces and...

  7. Magnet Motor Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Magnet Motor Corp Jump to: navigation, search Name: Magnet Motor Corp. Place: Starnberg, Germany Zip: 82319 Sector: Vehicles Product: Magnet motor Corp has been developing and...

  8. Radiological Survey Results for the Niagara Mohawk Right-of-Way, Tonawanda, New York (TNY004)

    SciTech Connect

    McKenzie, S.P.; Uziel, M.S.

    1998-11-01

    At the request of the U.S. Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey of a small portion of the Niagara Mohawk Power Corporation right-of-way in Tonawanda, New York. The purpose of the survey was to determine if radioactive residuals had migrated from or been redistributed onto the Niagara Mohawk right-of-way from the former Linde property to the west. The Linde Air Products Division of Union Carbide Corporation, Tonawanda New York, had used radioactive materials at that location for work performed under government contract from 1942 through 1948. The survey was performed in May 1996 in response to Formerly Utilized Sites Remedial Action Program (FUSRAP) requirements. These requirements dictate that the radiological status of certain vicinity properties shall be assessed and documented according to prescribed procedures prior to certification of the property for release for unrestricted use. Such release can only be granted if the property is found to be within current applicable authorized limits. The survey included a gamma scan of accessible areas and the collection and radionuclide analysis of soil samples from the portion of right-of-way located east of the former Linde plant site and north of the railway spur entrance gate. Results of the survey indicate that radioactive material probably originating from the Linde plant is located on the Niagara Mohawk right-of-way in the area surveyed. Surface gamma exposure rates were elevated above typical background levels. Four scattered surface soil samples exceeded DOE guideline values for {sup 238}U, and 8 of 13 surface soil samples exceeded DOE guideline values for {sup 226}Ra. The radionuclide distribution in these samples was similar to that found in materials resulting from former processing activities at the Linde site. It is recommended that the property be designated for remedial action by DOE.

  9. MSK Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    MSK Corp Jump to: navigation, search Name: MSK Corp Place: Tokyo, Tokyo, Japan Zip: 160-0023 Product: Japanese manufacturer of mono, multi-crystalline, and amorphous thin-film PV...

  10. Noritz Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Noritz Corp Jump to: navigation, search Name: Noritz Corp Place: Kobe, Hyogo, Japan Zip: 650-0033 Sector: Solar Product: Japan-based manufacturer of gas water heaters. It also...

  11. Intel Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Intel Corp Jump to: navigation, search Name: Intel Corp Place: Santa Clara, California Zip: 95052-8119 Product: Intel is a large semiconductor maker best known for its Pentium and...

  12. Semiconductor Manufacturing International Corp SMIC | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Manufacturing International Corp SMIC Jump to: navigation, search Name: Semiconductor Manufacturing International Corp (SMIC) Place: Shanghai, Shanghai Municipality, China Zip:...

  13. PWR AXIAL BURNUP PROFILE ANALYSIS

    SciTech Connect

    J.M. Acaglione

    2003-09-17

    The purpose of this activity is to develop a representative ''limiting'' axial burnup profile for pressurized water reactors (PWRs), which would encompass the isotopic axial variations caused by different assembly irradiation histories, and produce conservative isotopics with respect to criticality. The effect that the low burnup regions near the ends of spent fuel have on system reactivity is termed the ''end-effect''. This calculation will quantify the end-effects associated with Pressurized Water Reactor (PWR) fuel assemblies emplaced in a hypothetical 21 PWR waste package. The scope of this calculation covers an initial enrichment range of 3.0 through 5.0 wt% U-235 and a burnup range of 10 through 50 GWd/MTU. This activity supports the validation of the process for ensuring conservative generation of spent fuel isotopics with respect to criticality safety applications, and the use of burnup credit for commercial spent nuclear fuel. The intended use of these results will be in the development of PWR waste package loading curves, and applications involving burnup credit. Limitations of this evaluation are that the limiting profiles are only confirmed for use with the B&W 15 x 15 fuel assembly design. However, this assembly design is considered bounding of all other typical commercial PWR fuel assembly designs. This calculation is subject to the Quality Assurance Requirements and Description (QARD) because this activity supports investigations of items or barriers on the Q-list (YMP 2001).

  14. Sharp Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Sharp Corp Place: Osaka, Osaka, Japan Zip: 545-8522 Product: Japanese manufacturer of electric appliances and one of the biggest PV cell manufacturers in the world. Coordinates:...

  15. Korchip Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Manangu, Korea (Republic) Product: Korchip producers a range of ultracapacitors, batteries, and for various applications. References: Korchip Corp.1 This article is a stub....

  16. Zomeworks Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Place: Albuquerque, New Mexico Zip: 87125 Product: Developer and manufacturer of passive energy products. Coordinates: 35.08418, -106.648639 Show Map Loading map......

  17. Acumentrics Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Place: Westwood,, Massachusetts Zip: 02090-1548 Product: A manufacturer of direct natural gas and propane fueled Solid Oxide Fuel Cells. Coordinates: 40.991995,...

  18. EPS Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Sector: Services Product: California-based, developer and implementor of a suite of performance monitoring and "energy intelligence" services. References: EPS Corp1 This article...

  19. Solexant Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    firmdeveloping nanostructured PV cells to harvest photons across the spectrum from UV to IR, in order to manufacture cells and supply them to OEMs. References: Solexant Corp1...

  20. Ambient Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Product: Ambient develops open standards-based technologies for creating smart grid communication platforms and technologies. References: Ambient Corp1 This article is a stub....

  1. Ember Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Place: Boston, Massachusetts Zip: 2210 Product: US-based manufacturer of Zigbee communication chips, software and development tools for energy management applications....

  2. VERA Core Simulator Methodology for PWR Cycle Depletion (Conference...

    Office of Scientific and Technical Information (OSTI)

    VERA Core Simulator Methodology for PWR Cycle Depletion Citation Details In-Document Search Title: VERA Core Simulator Methodology for PWR Cycle Depletion Authors: Kochunas, ...

  3. Suzlon Wind Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Wind Energy Corp Jump to: navigation, search Name: Suzlon Wind Energy Corp Place: Chicago, Illinois Zip: 60631 Product: Regional office of turbine manufacturer, Suzlon Energy....

  4. Sphere Renewable Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Sphere Renewable Energy Corp Jump to: navigation, search Name: Sphere Renewable Energy Corp Place: California Product: California-based polysilicon technology company which has...

  5. First Electric Coop Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: First Electric Coop Corp Place: Arkansas Phone Number: 888-827-3322 Website: www.firstelectric.coop Twitter: https:twitter.com...

  6. Polymer Technology Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Polymer Technology Corp Jump to: navigation, search Name: Polymer Technology Corp Place: Menomonie, Wisconsin Zip: 54751 Sector: Services Product: A provider of contract...

  7. Hanwha Chemical Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Chemical Corp Jump to: navigation, search Name: Hanwha Chemical Corp Place: Seoul, Seoul, Korea (Republic) Zip: 100-797 Product: Korea-based manufacturer of synthetic resins and...

  8. Silicon Chemical Corp SCC | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp SCC Jump to: navigation, search Name: Silicon Chemical Corp (SCC) Place: Vancouver, Washington State Zip: 98687 Product: US manufacturer of polysilicon and silicon chemical...

  9. Rainbow Energy Marketing Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Energy Marketing Corp Jump to: navigation, search Name: Rainbow Energy Marketing Corp Place: North Dakota Phone Number: (701) 222-2290 Website: www.rainbowenergy.com Facebook:...

  10. Gulf Ethanol Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Gulf Ethanol Corp Jump to: navigation, search Name: Gulf Ethanol Corp Place: Houston, Texas Zip: 77055 Sector: Biomass Product: Focused on developing biomass preprocessing...

  11. JFE Steel Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: JFE Steel Corp Place: Tokyo, Tokyo, Japan Zip: 100-0011 Product: Japanese steel manufacturer; manufactures metallurgical silicon and plans to...

  12. Mitsubishi Materials Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: Mitsubishi Materials Corp Place: Tokyo, Tokyo, Japan Zip: 100-8117 Product: A metal and nonferrous metal manufacturer for industrial...

  13. Clean Venture 21 Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    21 Corp Jump to: navigation, search Name: Clean Venture 21 Corp Place: Kyoto, Kyoto, Japan Zip: 601 8121 Product: Japan-based company that researches, manufactures, and retails...

  14. Mitsubishi Electric Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: Mitsubishi Electric Corp Place: Tokyo, Tokyo, Japan Zip: 100-8310 Sector: Services, Solar Product: Japan-based manufacturer of electrical...

  15. Inter Action Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Action Corp Jump to: navigation, search Name: Inter Action Corp Place: Kanagawa, Japan Zip: 236-0004 Product: Semiconductor equipment and testing devices maker building a PV...

  16. Mitsubishi Polysilicon America Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    America Corp Jump to: navigation, search Name: Mitsubishi Polysilicon America Corp Place: Theodore, Alabama Zip: 36582 Product: US-based polysilicon manufacturer. Coordinates:...

  17. Universal Display Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Jump to: navigation, search Name: Universal Display Corp. Place: New Jersey Product: OLED (Organic Light Emitting Device) Developer References: Universal Display Corp.1 This...

  18. Irwin Electric Membership Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Electric Membership Corp Jump to: navigation, search Name: Irwin Electric Membership Corp Place: Georgia Website: www.irwinemc.com Twitter: @IrwinEMC Facebook: https:...

  19. Blue Sphere Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Sphere Corp Jump to: navigation, search Name: Blue Sphere Corp Place: London, United Kingdom Product: London-based emission reduction project integrator. References: Blue Sphere...

  20. Distributed Energy Systems Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Distributed Energy Systems Corp Jump to: navigation, search Name: Distributed Energy Systems Corp Place: Wallingford, Connecticut Zip: CT 06492 Product: The former holding company...

  1. Renovar Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Renovar Energy Corp Jump to: navigation, search Name: Renovar Energy Corp Place: Midland, Texas Zip: 79705 Product: Texas-based landfill gas project developer. References: Renovar...

  2. Yunnan Dehong Power Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Dehong Power Corp Jump to: navigation, search Name: Yunnan Dehong Power Corp Place: Yunnan Province, China Sector: Hydro Product: Dehongzhou-based small hydro project developer....

  3. Windblade Power Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Windblade Power Corp Jump to: navigation, search Name: Windblade Power Corp Place: Nevada Sector: Biomass, Hydro, Wind energy Product: Nevada-based project developer; focused on...

  4. Tippecanoe Valley School Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Wind Facility Status In Service Owner Tippecanoe Valley School Corp Developer Performance Services Energy Purchaser Tippecanoe Valley School Corp Location Akron IN...

  5. Jackson Energy Coop Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Energy Coop Corp Jump to: navigation, search Name: Jackson Energy Coop Corp Place: Kentucky Phone Number: (800)262-7480 Website: www.jacksonenergy.com Twitter: @jacksonenergy...

  6. American Lithium Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Lithium Energy Corp Jump to: navigation, search Name: American Lithium Energy Corp Place: San Marcos, California Zip: 92069 Product: California-based developer of lithium ion...

  7. Essential Innovations Technology Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Technology Corp Jump to: navigation, search Name: Essential Innovations Technology Corp Place: Bellingham,, Washington State Zip: 98225 Sector: Geothermal energy, Services Product:...

  8. Zenith Materials Technology Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Materials Technology Corp Jump to: navigation, search Name: Zenith Materials Technology Corp. Place: Hsinchu, Taiwan Sector: Solar Product: Taiwan-based manufacturer of solar ingot...

  9. Industrial Solar Technology Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Solar Technology Corp Jump to: navigation, search Name: Industrial Solar Technology Corp Place: Golden, Colorado Zip: CO 80403-1 Product: IST designs, manufactures, installs and...

  10. Kinsus Interconnect Technology Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Kinsus Interconnect Technology Corp Jump to: navigation, search Name: Kinsus Interconnect Technology Corp Place: Taiwan Sector: Solar Product: Engaged in the manufacture of chip...

  11. Sinonar Solar Sinonar Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Sinonar Solar Sinonar Corp Jump to: navigation, search Name: Sinonar Solar (Sinonar Corp) Place: Miaoli, Taiwan Product: Sinonar corporation is an amorphous silicon cell...

  12. Amereco Biofuels Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Amereco Biofuels Corp Jump to: navigation, search Name: Amereco Biofuels Corp Place: Phoenix, Arizona Zip: 85028 Sector: Biofuels Product: Amereco pursues technologies that...

  13. New Energy Capital Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Capital Corp Jump to: navigation, search Name: New Energy Capital Corp. Place: Hanover, New Hampshire Zip: 3755 Sector: Renewable Energy Product: Private equity fund focused on...

  14. Silescent Lighting Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Lighting Corp Place: Fort Lauderdale, Florida Zip: 33315 Product: Florida-based LED lighting fixtures maker. References: Silescent Lighting Corp1 This article is a stub....

  15. Pataula Electric Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Pataula Electric Member Corp Jump to: navigation, search Name: Pataula Electric Member Corp Place: Georgia Website: www.cobbemc.com Twitter: @cobbemc Facebook: https:...

  16. Sunrise Solar Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Solar Corp Jump to: navigation, search Name: Sunrise Solar Corp Place: San Antonio, Texas Zip: 78249 Sector: Solar Product: Sunrise Solar intends to commercialise and distribute...

  17. CECO Environmental Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Place: Cincinnati, Ohio Zip: 45209 Sector: Services Product: Provider of air pollution control products and services. References: CECO Environmental Corp1 This...

  18. NF Energy Saving Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    NF Energy Saving Corp Jump to: navigation, search Name: NF Energy Saving Corp Place: Shenyang, Liaoning Province, China Sector: Services Product: China-based company provides...

  19. Boston Carbon Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Carbon Corp Jump to: navigation, search Name: Boston Carbon Corp Place: Carlisle, Massachusetts Zip: 1741 Sector: Carbon Product: Boston Carbon Corporation helps develop clean...

  20. Sky Train Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Train Corp Jump to: navigation, search Name: Sky Train Corp. Place: Palm Harbor, Florida Zip: 34684 Sector: Services Product: Sky Train Corporation is a consultant company...

  1. GC China Turbine Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    GC China Turbine Corp Jump to: navigation, search Name: GC China Turbine Corp Place: Wuhan, Hubei Province, China Sector: Wind energy Product: China-base wind turbine manufacturer....

  2. China Hydroelectric Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: China Hydroelectric Corp Place: Beijing, Beijing Municipality, China Zip: 100010 Sector: Hydro Product: Engaged in the acquisition of small...

  3. EPCOR Power Development Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Development Corp Jump to: navigation, search Name: EPCOR Power Development Corp Place: Canada Sector: Wind energy Product: Develops, constructs and operates non-regulated power...

  4. Longi Silicon Materials Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Longi Silicon Materials Corp Jump to: navigation, search Name: Longi Silicon Materials Corp Place: Xi'an, Shaanxi Province, China Zip: 710065 Product: A monocrystalline silicon...

  5. Guardian Industries Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Industries Corp Jump to: navigation, search Name: Guardian Industries Corp Place: Auburn Hills, Michigan Zip: 48326-1714 Sector: Solar Product: Michigan-based firm that...

  6. Yu Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: Yu Energy Corp Region: United States Sector: Marine and Hydrokinetic Website: http: This company is listed in the Marine and Hydrokinetic...

  7. Environmental Power Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Power Corp Jump to: navigation, search Name: Environmental Power Corp Place: Portsmouth, New Hampshire Zip: 3801 Product: Holding company focused on energy production from waste...

  8. Sintek Photronic Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    to: navigation, search Name: Sintek Photronic Corp Place: Taiwan Product: Taiwanese TFT-LCD panel color filter producer. References: Sintek Photronic Corp1 This article is a...

  9. DOE's Lab-Corps Fact Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Fact Sheet DOE's Lab-Corps Fact Sheet DOE's Lab-Corps Fact Sheet.pdf (626.52 KB) More Documents & Publications Lab-Corps Fact Sheet Lab-Corps Documents Lab-Corps

  10. Lab-Corps Fact Sheet

    Energy.gov [DOE]

    This fact sheet provides an overview of the Lab-Corps program, which is a specialized training curriculum aimed at accelerating the transfer of clean energy technologies from national laboratories into the commercial marketplace.

  11. GIGASTORAGE Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp. Place: Hsinchu,, Taiwan Sector: Solar Product: A Taiwan-based Optical Storage Media manufacture, who also produces AlAg or Al+Ag paste for solar cells....

  12. Auria Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    between E-Ton Solar Tech and Lite-On Technology that will manufacture amorphous silicon thin-film modules. References: Auria Corp1 This article is a stub. You can help OpenEI...

  13. Diatom Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Beach, California Zip: 92651 Sector: Carbon Product: Focused on carbon credit trading business. References: Diatom Corp1 This article is a stub. You can help OpenEI by expanding...

  14. Catelectric Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    the type and number of catalytic sites in a fuel cell or other system, through nanotechnology. References: Catelectric Corp1 This article is a stub. You can help OpenEI by...

  15. EA-376 Societe Generale Energy Corp | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    6 Societe Generale Energy Corp EA-376 Societe Generale Energy Corp Order authorizing Societe Generale Energy Corp to export electric energy to Canada EA-376 Societe Generale Energy Corp (3.53 MB) More Documents & Publications Application to Export Electric Energy OE Docket No. EA-376 Societe Generale Energy Corp. EA-171-D Powerex Corp. EA-145-E Powerex Corp.

  16. Marine Corps Base Quantico Achieves 85% Savings in Parking Lighting...

    Office of Environmental Management (EM)

    Quantico Achieves 85% Savings in Parking Lighting Marine Corps Base Quantico Achieves 85% Savings in Parking Lighting Marine Corps Base Quantico (MCBQ) in Virginia Marine Corps ...

  17. EA-145-E Powerex Corp. | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    E Powerex Corp. EA-145-E Powerex Corp. Order authorizing Powerex Corp to export electric energy to Mexico. PDF icon EA-145-E Powerex Corp.pdf More Documents & Publications ...

  18. Liberty Power Corp. (Delaware) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp. Place: Delaware Phone Number: 1-866-769-3799 Website: www.libertypowercorp.com Twitter: https:twitter.comlibertypower Facebook: http:www.facebook.comLibertyPowerCorp...

  19. Sunner Solar Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Name: Sunner Solar Corp. Place: Taoyuan, Taiwan Product: A Taiwan-based thin-film PV cell manufacturer References: Sunner Solar Corp.1 This article is a stub. You can help...

  20. Formosun Solar Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp. Place: Hsinchu County, Taiwan Zip: 303-51 Sector: Solar Product: Thin-film solar cell producer based in Taiwan. References: Formosun Solar Corp.1 This article is a stub....

  1. Hitachi High Technologies Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: Hitachi High-Technologies Corp Place: Tokyo, Japan Zip: 105-8717 Sector: Solar Product: Japan-based technology firm that is member of the...

  2. Tanaka Chemical Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: Tanaka Chemical Corp Place: Fukui-shi, Fukui, Japan Zip: 910-3131 Product: Japanese chemical manufactuerer with a focus on materials for...

  3. JM Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    JM Energy Corp Place: Hokuto, Yamanashi, Japan Product: Manufacturer of high-capacity lithium-ion capacitors (LICs) References: JM Energy Corp1 This article is a stub. You can...

  4. GS Yuasa Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: GS Yuasa Corp Place: Minato-Ku, Kyoto, Japan Zip: 601-8520 Sector: Solar Product: Kyoto-based company involved in battery manufacturing and...

  5. Washington Elec Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Washington Elec Member Corp Jump to: navigation, search Name: Washington Elec Member Corp Place: Georgia Phone Number: 478-552-2577; 1-800-552-2577 Website: washingtonemc.com...

  6. Power Tree Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Tree Corp Place: Boca Raton, Florida Zip: 33487 Product: Florida-based flywheel power storage systems maker. References: Power Tree Corp1 This article is a stub. You can help...

  7. Georgia Transmission Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: Georgia Transmission Corp Place: Georgia References: EIA Form EIA-861 Final Data File for 2010 - File1a1 EIA Form 861 Data Utility Id 7197...

  8. Green Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: Green Energy Corp Region: United States Sector: Marine and Hydrokinetic Website: www.gweconline.com This company is listed in the Marine and...

  9. ZBB Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Energy Corp Place: Wisconsin Zip: 53051 Product: Focused on development of advanced battery systems. References: ZBB Energy Corp1 This article is a stub. You can help OpenEI...

  10. Upstate NY Power Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    NY Power Corp Jump to: navigation, search Name: Upstate NY Power Corp Place: West Seneca, New York Zip: 14224-3454 Sector: Wind energy Product: Developer of clean energy projects...

  11. GEXA Corp. (Connecticut) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    GEXA Corp. (Connecticut) Jump to: navigation, search Name: GEXA Corp. Place: Connecticut Phone Number: 866-961-9399 Website: www.gexaenergy.com Outage Hotline: 866-961-9399...

  12. Brunswick Electric Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Brunswick Electric Member Corp Jump to: navigation, search Name: Brunswick Electric Member Corp Place: North Carolina Phone Number: 1-800-682-5309 Website: www.bemc.org Outage...

  13. Pearl River Valley El Pwr Assn | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Valley El Pwr Assn Jump to: navigation, search Name: Pearl River Valley El Pwr Assn Place: Mississippi Phone Number: Columbia: 601-736-2666 -- Hattiesburg: 601-264-2458 -- Purvis:...

  14. Northeast Missouri El Pwr Coop | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Pwr Coop Jump to: navigation, search Name: Northeast Missouri El Pwr Coop Place: Missouri Phone Number: 573-769-2107 Website: www.northeast-power.coop Outage Hotline: 573-769-2107...

  15. Polk County Rural Pub Pwr Dist | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Polk County Rural Pub Pwr Dist Jump to: navigation, search Name: Polk County Rural Pub Pwr Dist Place: Nebraska Phone Number: (888) 242-5265 Website: www.pcrppd.com Outage...

  16. Sam Rayburn Municipal Pwr Agny | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Municipal Pwr Agny Jump to: navigation, search Name: Sam Rayburn Municipal Pwr Agny Place: Texas Phone Number: 936-336-3684 or 936-336-5666 Website: www.cityofliberty.orgGOVERNME...

  17. Red River Valley Coop Pwr Assn | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Red River Valley Coop Pwr Assn Jump to: navigation, search Name: Red River Valley Coop Pwr Assn Place: Minnesota Website: www.rrvcoop.com Facebook: https:www.facebook.comRRVCPA...

  18. Central Montana E Pwr Coop Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    E Pwr Coop Inc Jump to: navigation, search Name: Central Montana E Pwr Coop Inc Place: Montana Phone Number: 406-268-1211 Website: www.cmepc.org Outage Hotline: 406-268-1211...

  19. Lab-Corps Documents | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Lab-Corps Documents Lab-Corps Documents These documents are related the Tech-to-Market Lab-Corps Pilot. Lab-Corps Pilot Summary The Lab-Corps pilot program has $2.3 million in available funding aimed at accelerating the transfer of innovative clean energy technologies from the Energy Department's national laboratories into the commercial marketplace. To accomplish this, the program has selected a "node" for its national network-the National Renewable Energy Laboratory-to develop a

  20. Lab-Corps | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Lab Impact » Lab-Corps Lab-Corps DOE's Lab-Corps program is a specialized training curriculum aimed at accelerating the transfer of clean energy technologies from national laboratories into the commercial marketplace. The training provides an entrepreneurial education to national laboratory researchers and connects them to potential customers and industry partners, helping to close the knowledge gap between researchers and the marketplace. As part of Technology-to-Market's Lab Impact portfolio,

  1. Everphoton Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Place: Taipei, Taiwan Zip: 11493 Product: Taiwanese HCPV (high concentration photovoltaic) key components manufacturer and HCPV system solution provider. Coordinates:...

  2. GEXA Corp. (Rhode Island) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    GEXA Corp. Place: Rhode Island Website: www.gexaenergy.com Twitter: @nationalgridus Facebook: https:www.facebook.comnationalgrid Outage Hotline: 1-800-465-1212 Outage Map:...

  3. Walton Electric Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Electric Member Corp Place: Georgia Website: www.waltonemc.com Twitter: @waltonemc Facebook: https:www.facebook.comwaltonemc Outage Hotline: 770-267-2505 Outage Map:...

  4. Beijing Soltech Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Place: Beijing, Beijing Municipality, China Zip: 100176 Product: Chinese thin-film PV cell manufacturer References: Beijing Soltech Corp1 This article is a stub. You can help...

  5. Legend Investment Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    to: navigation, search Name: Legend Investment Corp Place: Michigan Zip: 48105 Sector: Solar Product: Investment company, which acquired the PV business of GiraSolar in early 2006...

  6. Connected Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Energy Corp Place: Rochester, New York Zip: 14614 Product: Developer of the Central Operation Management System (COMSYS). Coordinates: 43.1555, -77.616033 Show Map...

  7. Vorbeck Materials Corp. | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Vorbeck Materials Corp. America's Next Top Energy Innovator Challenge 45458 likes Vorbeck ... The liquid desiccant design allows for the utilization of solar or waste heat ...

  8. Portside Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Name: Portside Energy Corp Place: Indiana ParentHolding Organization: Primary Energy Recycling Corporation Website: primaryenergy.comprojectspor References: EIA Form EIA-861...

  9. Nano Tune Technologies Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Product: Nano Tune use sol-gel processing technology to develop a high energy density & power storage devices. References: Nano Tune Technologies Corp.1 This article is...

  10. Green Mountain Power Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    from Town of Readsboro, Vermont (Utility Company)) Jump to: navigation, search Name: Green Mountain Power Corp Place: Vermont Service Territory: Vermont Phone Number:...

  11. PermaCity Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search Name: PermaCity Corp Place: Commerce, California Zip: 90040 Sector: Buildings Product: US-based provider of turnkey PV and passive system installation for...

  12. Integrated Power Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search Name: Integrated Power Corp. Place: Novato, California Zip: 94947 Sector: Buildings, Services, Solar Product: Provides services in making buildings more reliant on...

  13. Liberty Power Corp. (Maryland) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Phone Number: 1-866-769-3799 Website: www.libertypowercorp.comresid Twitter: https:twitter.comlibertypower Facebook: https:www.facebook.comLibertyPowerCorp Outage...

  14. GEXA Corp. (Delaware) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Name: GEXA Corp. Place: Delaware Phone Number: 866.961.9399 Website: www.gexaenergy.com Twitter: @gexavoice Facebook: https:www.facebook.comGexaEnergy Outage Hotline:...

  15. Avista Corp (Idaho) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Avista Corp Place: Idaho Phone Number: (800) 227-9187 Website: www.avistautilities.com Twitter: @avistautilities Facebook: https:www.facebook.comAvistaUtilities Outage...

  16. SunPower Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    to: navigation, search Name: SunPower Corp Place: San Jose, California Zip: 95134 Sector: Solar Product: Leading manufacturer of monocrystalline silicon cells, modules, system...

  17. Krystal Planet Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Planet Corp Place: Lenexa, Kansas Zip: 66214 Product: Retailer of clean power and energy-saving products. Coordinates: 38.960971, -94.740565 Show Map Loading map......

  18. Taiwan Glass Industry Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Taiwan Glass Industry Corp Place: Taipei, Taiwan Zip: 10566 Product: Engaged in the manufacturing, processing and selling of various types of glass. References: Taiwan Glass...

  19. Contrel Technology Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Taiwan Zip: 744 Sector: Solar Product: Taiwan-based LCD and thin-film solar PV manufacturing and testing equipment maker. References: Contrel Technology Corp1 This article...

  20. Highlight Tech Corp HTC | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp (HTC) Place: Tainan, Taiwan Zip: 709 Product: Taiwan-based vacuum pump and LCD manufacturing equipment maker developing thin-film PV manufacturing equipment. Coordinates:...

  1. Moteck Electric Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Name: Moteck Electric Corp Place: Taipei Hsien, Taiwan Zip: 22101 Product: Taipei-based firm focusing on motorized systems. The firm also produces PV junction boxes. References:...

  2. Sapphire Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Sector: Biofuels Product: California-based venture capital backed company developing algae-based biofuels. References: Sapphire Energy Corp1 This article is a stub. You can...

  3. US Hybrid Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Jump to: navigation, search Name: US Hybrid Corp Place: California Sector: Renewable Energy, Vehicles Product: US Hybrid Corporation is a California-based company specializing in...

  4. Solaris Nanosciences Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    nanoscale materials for large applications including the solar energy, display and vision markets. References: Solaris Nanosciences Corp1 This article is a stub. You can help...

  5. Liberty Power Corp. (Connecticut) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Connecticut) Jump to: navigation, search Name: Liberty Power Corp. Place: Connecticut Phone Number: 1-866-769-3799 Website: www.libertypowercorp.comresid Outage Hotline:...

  6. Wisconsin Public Service Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Wisconsin Public Service Corp Place: Wisconsin Phone Number: 800-450-7260 Website: www.wisconsinpublicservice.com Twitter: @WPSStorm Outage Hotline: 800-450-7240 Outage Map:...

  7. Constellation Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Jump to: navigation, search Name: Constellation Energy Corp. Place: Toronto, Ontario, Canada Sector: Renewable Energy Product: A Toronto-based subsidiary of EnerAsia Renewable...

  8. United Technologies Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    United Technologies Corp Place: Hartford, Connecticut Zip: CT 06101 Sector: Hydro, Hydrogen Product: UTC is a global technology corporation with activities in aerospace,...

  9. Lab-Corps | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    in September 2015, ORNL's new crowdsourcing initiative ... and ORNL to provide in-kind technical support and cash ... Lab-Corps, which builds on the National Science Foundation's ...

  10. Lab-Corps Teams | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    For information about the commercialization of Lab-Corps technologies or to find contact information for a specific DOE laboratory, visit the DOE Energy Innovation Portal. For ...

  11. Cobb Electric Membership Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Electric Membership Corporation) Jump to: navigation, search Name: Cobb Electric Membership Corp Place: Marietta, Georgia References: EIA Form EIA-861 Final Data File for 2010 -...

  12. Cobb Electric Membership Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Jump to: navigation, search Name: Cobb Electric Membership Corp Place: Marietta, Georgia References: EIA Form EIA-861 Final Data File for 2010 - File1a1 Energy Information...

  13. Celunol Corp formerly BCI | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    and other value added products from cellulosic waste derived from pulp and paper, wood, agriculture and various other waste streams. References: Celunol Corp (formerly...

  14. Tailored Materials Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Zip: 85706 Sector: Carbon, Solar Product: String representation "Tailored Materi ... ng solar cells." is too long. References: Tailored Materials Corp1 This article is a stub....

  15. Terranova Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Terranova Energy Corp Place: Barcelona, Spain Zip: 8034 Sector: Wind energy Product: Spanish wind developer with projects in Asturia,Catalunya and Galicia. Coordinates:...

  16. Nuclear Power Corp L T JV | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp L T JV Jump to: navigation, search Name: Nuclear Power Corp-L&T JV Place: Mumbai, Maharashtra, India Zip: 400094 Product: JV between Nuclear Power Corp. and L&T. Coordinates:...

  17. U.S. Marine Corp Logistics Base | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Marine Corp Logistics Base Jump to: navigation, search Name U.S. Marine Corp Logistics Base Facility U.S. Marine Corp Logistics Base Sector Wind energy Facility Type Community Wind...

  18. U.S. Army Corps of Engineers | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    U.S. Army Corps of Engineers Jump to: navigation, search Logo: U.S. Army Corps of Engineers Name: U.S. Army Corps of Engineers Place: Michigan Phone Number: 1-888-694-8313 Website:...

  19. EA-149 PacifiCorp | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    EA-149 PacifiCorp Order authorizing PacifiCorp to export electric energy to Mexico. EA-149 PacifiCorp (MX).pdf (424.52 KB) More Documents & Publications EA-247-D Constellation ...

  20. AmeriCorps State and National Grants

    Office of Energy Efficiency and Renewable Energy (EERE)

    The AmeriCorps grants are awarded to eligible organizations proposing to engage AmeriCorps members in evidence-based or evidence-informed interventions to strengthen communities. The focus areas include disaster services, economic opportunity, education, environmental stewardship, healthy futures, and veteran and military families.

  1. Arima Photovoltaic And Optical Corp Arima PV | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Photovoltaic And Optical Corp Arima PV Jump to: navigation, search Name: Arima Photovoltaic And Optical Corp (Arima PV) Place: Taipei, Taiwan Product: Once a maker of computers,...

  2. BioFuel Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Energy Corp Jump to: navigation, search Name: BioFuel Energy Corp Place: Denver, Colorado Zip: 80202 Product: Develops, owns and operates ethanol facilities. References: BioFuel...

  3. Xunlight Corp previously MWOE Solar Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Xunlight Corp previously MWOE Solar Inc Jump to: navigation, search Name: Xunlight Corp (previously MWOE Solar Inc) Place: Toledo, Ohio Zip: 43607 Product: US-based developer of...

  4. Lab-Corps Program Trains Scientists in Commercialization | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Lab-Corps Program Trains Scientists in Commercialization Lab-Corps Program Trains Scientists in Commercialization Addthis Description This video features an introduction to the ...

  5. Pacific Fuel Cell Corp PFCE | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Fuel Cell Corp PFCE Jump to: navigation, search Name: Pacific Fuel Cell Corp (PFCE) Place: Tustin, California Zip: 92780 Sector: Carbon Product: Owns a license for a proprietary...

  6. Datang Sino Japan Chifeng Renewable Power Corp | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Japan Chifeng Renewable Power Corp Jump to: navigation, search Name: Datang Sino-Japan (Chifeng) Renewable Power Corp Place: Inner Mongolia Autonomous Region, China Product:...

  7. Bihar State Hydroelectric Power Corp BSHPC | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Hydroelectric Power Corp BSHPC Jump to: navigation, search Name: Bihar State Hydroelectric Power Corp (BSHPC) Place: Patna, Bihar, India Sector: Hydro Product: Patna-based nodal...

  8. Solar Environmental Technologies Tianjin Corp aka SETC Cenicom...

    OpenEI (Open Energy Information) [EERE & EIA]

    Environmental Technologies Tianjin Corp aka SETC Cenicom Solar Etc Jump to: navigation, search Name: Solar & Environmental Technologies (Tianjin) Corp (aka SETC, Cenicom, Solar...

  9. United Solar Systems Corp USSC aka Bekaert ECD Solar Systems...

    OpenEI (Open Energy Information) [EERE & EIA]

    Systems Corp USSC aka Bekaert ECD Solar Systems LLC Jump to: navigation, search Name: United Solar Systems Corp (USSC) (aka Bekaert ECD Solar Systems LLC) Place: Middletown...

  10. Ecosystem Solar Electric Corp aka Solar MW Energy Inc | Open...

    OpenEI (Open Energy Information) [EERE & EIA]

    Solar Electric Corp aka Solar MW Energy Inc Jump to: navigation, search Name: Ecosystem Solar Electric Corp, aka Solar MW Energy Inc Place: Ontario, California Zip: 91761 Product:...

  11. Applied Solar LLC formerly Open Energy Corp and Barnabus Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Open Energy Corp and Barnabus Energy Inc Jump to: navigation, search Name: Applied Solar LLC (formerly Open Energy Corp and Barnabus Energy Inc) Place: San Diego, California...

  12. Quantum Materials Corporation formerly Hague Corp | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Corporation formerly Hague Corp Jump to: navigation, search Name: Quantum Materials Corporation (formerly Hague Corp) Sector: Renewable Energy Product: Through their wholly owned...

  13. DOE - Office of Legacy Management -- Bendix Aviation Corp Pioneer...

    Office of Legacy Management (LM)

    Corp Pioneer Div - IA 05 FUSRAP Considered Sites Site: BENDIX AVIATION CORP., PIONEER DIV. (IA.05 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated...

  14. DOE - Office of Legacy Management -- Sharples Corp - PA 29

    Office of Legacy Management (LM)

    FUSRAP Also see Documents Related to SHARPLES CORP. PA.29-1 - MemorandumChecklist; D. Levine to the File; Subject: Elimination Recommendation (Sharples Corp.); December 30, 1986...

  15. Farmers Rural Electric Coop Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Rural Electric Coop Corp Jump to: navigation, search Name: Farmers Rural Electric Coop Corp Place: Kentucky Website: farmersrecc.com Facebook: https:www.facebook.comFarmersRECC...

  16. Green Wave Energy Corp GWEC | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Wave Energy Corp GWEC Jump to: navigation, search Name: Green Wave Energy Corp GWEC Region: United States Sector: Marine and Hydrokinetic Website: http: This company is listed in...

  17. Hall's Warehouse Corp Solar Project | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp. Solar Project" Retrieved from "http:en.openei.orgwindex.php?titleHall%27sWarehouseCorpSolarProject&oldid397541" Feedback Contact needs updating Image...

  18. GreenFuel Technologies Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: GreenFuel Technologies Corp Place: Cambridge, Massachusetts Product: Manufacturer of biodiesel grown on the CO2 emissions from...

  19. DOE - Office of Legacy Management -- United Nuclear Corp - MO...

    Office of Legacy Management (LM)

    Nuclear Corp - MO 0-03 FUSRAP Considered Sites Site: UNITED NUCLEAR CORP. (MO.0-03) Eliminated from further consideration under FUSRAP Designated Name: Not Designated Alternate ...

  20. Korea Rural Community Corp KRC | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search Name: Korea Rural Community Corp (KRC) Place: Korea (Republic) Product: South Korea-based rural development company. References: Korea Rural Community Corp...

  1. Voluntary Protection Program Onsite Review, Parsons Corp., Salt...

    Office of Environmental Management (EM)

    Corp., Salt Waste Processing Facility Construction Project - May 2014 Voluntary Protection Program Onsite Review, Parsons Corp., Salt Waste Processing Facility Construction Project...

  2. China Recycling Energy Corp CREG | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Recycling Energy Corp CREG Jump to: navigation, search Name: China Recycling Energy Corp (CREG) Place: Reno, Nevada Zip: 89511 Product: A US-incorporated company that develops...

  3. China South Industries Group Corp CSG | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Industries Group Corp CSG Jump to: navigation, search Name: China South Industries Group Corp (CSG) Place: Beijing, Beijing Municipality, China Zip: 100821 Product: Beijing-based...

  4. Shandong Linuo New Material Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    New Material Corp Jump to: navigation, search Name: Shandong Linuo New Material Corp. Place: Jinan, Shandong Province, China Zip: 251600 Sector: Solar Product: Manufacturer of...

  5. C & L Electric Coop Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    C & L Electric Coop Corp Jump to: navigation, search Name: C & L Electric Coop Corp Place: Arkansas Service Territory: Arkansas Phone Number: 870.628.4676 Website:...

  6. Sempra Energy Trading Corp (Washington) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Sempra Energy Trading Corp (Washington) Jump to: navigation, search Name: Sempra Energy Trading Corp Place: Washington Phone Number: (877) SEMPRA1 Website: www.sempra.com Twitter:...

  7. Digital Ultracap Corp formerly Digital Ultracap LLC | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Ultracap Corp formerly Digital Ultracap LLC Jump to: navigation, search Name: Digital Ultracap Corp (formerly Digital Ultracap LLC) Place: Netherlands Product: Partnership between...

  8. International Business Machines Corp IBM | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Business Machines Corp IBM Jump to: navigation, search Name: International Business Machines Corp (IBM) Place: Armonk, New York Zip: 10504 Sector: Services Product: IBM is a...

  9. HydroGen Corporation formerly Chiste Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    HydroGen Corporation formerly Chiste Corp Jump to: navigation, search Name: HydroGen Corporation (formerly Chiste Corp) Place: Jefferson Hills, Pennsylvania Zip: 15025 Sector:...

  10. First Energy Solutions Corp. (New Jersey) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Solutions Corp. Name: First Energy Solutions Corp. Abbreviation: FES Address: 341 White Pond Dr., Building B3 Place: Akron, Ohio Country: United States Zip: 44320 Service...

  11. PPM Atlantic Renewable Formerly Atlantic Renewable Energy Corp...

    OpenEI (Open Energy Information) [EERE & EIA]

    PPM Atlantic Renewable Formerly Atlantic Renewable Energy Corp Jump to: navigation, search Name: PPM Atlantic Renewable (Formerly Atlantic Renewable Energy Corp) Place: Virginia...

  12. Vision Industries dba Vision Motor Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Industries dba Vision Motor Corp Jump to: navigation, search Name: Vision Industries (dba Vision Motor Corp) Place: Santa Monica, California Zip: 90405 Product: Santa Monica-based...

  13. Lab-Corps Program | Argonne National Laboratory

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Videos Lab-Corps Program Info. Session - April 15, 2016 Lab-Corps Program Symposium - Feb. 18, 2016 Lab-Corps program In support of the U.S. Department of Energy's (DOE's) mission to secure U.S. leadership in clean energy technology, the Office of Energy Efficiency and Renewable Energy (EERE) is committed to improving the DOE national laboratories' commercial impact on clean energy industries. As a part of this effort, EERE's Technology-to-Market team within the Office of Strategic Programs has

  14. Calpine Corp-Agnews | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp-Agnews Place: California Phone Number: 916.443.2500 Website: www.calpine.com Twitter: @Calpine Outage Hotline: 1 713-830-2000 References: EIA Form EIA-861 Final Data File...

  15. Beacon Power Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    1879 Sector: Solar Product: US-based developer of solar PV inverters and flywheel-based energy storage systems. References: Beacon Power Corp1 This article is a stub. You can...

  16. Liberty Power Corp. (Illinois) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Number: 1-866-769-3799 Website: www.libertypowercorp.comresid Twitter: @libertypower Facebook: https:www.facebook.comLibertyPowerCorp Outage Hotline: 1-866-769-3799 References:...

  17. Liberty Power Corp. (Pennsylvania) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Number: 1-866-769-3799 Website: www.libertypowercorp.comresid Twitter: @libertypower Facebook: https:www.facebook.comLibertyPowerCorp Outage Hotline: 1-866-769-3799 References:...

  18. Liberty Power Corp. (California) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Number: 1-866-769-3799 Website: www.libertypowercorp.com Twitter: @libertypower Facebook: https:www.facebook.comLibertyPowerCorp References: EIA Form EIA-861 Final Data...

  19. Quietside Corp: Order (2010-CE-1710)

    Energy.gov [DOE]

    DOE ordered Quietside Corporation to pay a $5,000 civil penalty after finding Quietside Corp. had failed to certify that certain models of water heaters comply with the applicable energy conservation standards.

  20. Mitchell Electric Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Mitchell Electric Member Corp Place: Georgia Phone Number: Camilla, GA: 229-336-5221; Albany, GA: 229-436-0070, Sylvester, GA: 229-776-3386 Website: mitchellemc.com Facebook:...

  1. State Grid Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    State Grid Corp Jump to: navigation, search 2011-2015 Plans for 1000kV transmission lines (UHV) 1 http:www.chinadaily.com.cnbusiness2010-0813content11148692.htm...

  2. Liberty Power Corp. (Massachusetts) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Phone Number: (1-866-769-3799) Website: www.libertypowercorp.com Twitter: @libertypower Facebook: https:www.facebook.comLibertyPowerCorp Outage Hotline: (1-866-769-3799)...

  3. Upson Elec Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Name: Upson Elec Member Corp Place: Georgia Website: www.upsonemc.comUpson%20EMC%2 Facebook: https:www.facebook.comupson.emc Outage Hotline: 706-647-5475 References: EIA...

  4. Jackson Electric Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Jackson Electric Member Corp Place: Georgia Phone Number: 1-800-462-3691 Website: www.jacksonemc.com Twitter: @JacksonEMC Facebook: https:www.facebook.comJacksonEMC Outage...

  5. PacifiCorp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    abou References: Energy Information Administration.1 EIA Form 861 Data Utility Id 14354 This article is a stub. You can help OpenEI by expanding it. PacifiCorp consists of...

  6. SolarCity Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Place: Foster City, California Zip: 94404 Sector: Solar Product: US-based designer and installer of solar systems for domestic and commercial use. References: SolarCity Corp1...

  7. Excelsior Electric Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Member Corp Place: Georgia Phone Number: 912-685-2115 Website: www.excelsioremc.com Outage Map: outage.excelsioremc.com:8181 References: EIA Form EIA-861 Final Data File for...

  8. Farmers Electric Coop Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Coop Corp Place: Arkansas Phone Number: 903-455-1715 Website: www.fecelectric.com Outage Hotline: 903-455-1715 Outage Map: s-webserv.fecelectric.comfarm References: EIA Form...

  9. Haywood Electric Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Member Corp Place: North Carolina Phone Number: 828-452-2281 or 828-966-4215 or toll free at 1-800-951-6088 Website: www.haywoodemc.com Facebook: https:www.facebook.com...

  10. DOE Participates in EDF Climate Corps Training

    Energy.gov [DOE]

    The Energy Department (DOE) was pleased to help Better Buildings Alliance affiliate Environmental Defense Fund prepare a new class of Climate Corps fellows during their training this past week in...

  11. Arise Technologies Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Jump to: navigation, search Name: Arise Technologies Corp Place: Kitchener, Ontario, Canada Zip: N2E 3B3 Product: Canada-based manufacturer of proprietary "thin-film on silicon...

  12. Improving fuel-rod performance. [PWR; BWR

    SciTech Connect

    Ocken, H.; Knott, S.

    1981-03-01

    To reduce the risk of fuel-rod failures, utilities operate their nuclear reactors within conservative limits on power increases proposed by nuclear-fuel vendors. Of particular concern to US utilities is that adopting these limits results in an industrywide average plant capacity loss of 3% in BWR designs and 0.3% in PWR designs. To replace lost BWR capacity by other generating means currently costs the utilities $150 million annually, and losses for PWRs are about $20 million. Efforts are therefore being made to identify the factors responsible for Zircaloy degradation under PCI condition and to improve nuclear-fuel-rod design and reactor operation.

  13. South Mississippi El Pwr Assn | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    South Mississippi El Pwr Assn Place: Mississippi Phone Number: 601.268.2083 Website: www.smepa.coop Outage Hotline: 601.268.2083 References: EIA Form EIA-861 Final Data File for...

  14. East Mississippi Elec Pwr Assn | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search Name: East Mississippi Elec Pwr Assn Place: Mississippi Phone Number: Meridian Office: 601-581-8600 -- Quitman Office: 601-776-6271 -- DeKalb Office: 601-743-2641 --...

  15. Effects of Multiple Drying Cycles on HBU PWR Cladding Alloys

    Office of Energy Efficiency and Renewable Energy (EERE)

    The purpose of this research effort is to determine the effects of canister/cask vacuum drying and storage on radial hydride precipitation in high‐burnup (HBU) pressurized water reactor (PWR)...

  16. Grand Valley Rrl Pwr Line, Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Valley Rrl Pwr Line, Inc Place: Colorado Website: www.gvp.org Twitter: @GVRuralPower Outage Hotline: 970-242-0040 Outage Map: www.gvp.orgcontentoutage-map References: EIA Form...

  17. Impact of High Burnup on PWR Spent Fuel Characteristics (Journal...

    Office of Scientific and Technical Information (OSTI)

    Reducing the burden of management of spent nuclear fuel is important to the future of nuclear energy. The impact of higher pressurized water reactor (PWR) fuel burnup is examined ...

  18. Ex parte submission of SANYO North America Corp. and SANYO E...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    parte submission of SANYO North America Corp. and SANYO E&E Corp. Ex parte submission of SANYO North America Corp. and SANYO E&E Corp. On November 2, 2010, Nobuko Horii of SANYO ...

  19. South River Elec Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    River Elec Member Corp Jump to: navigation, search Name: South River Elec Member Corp Place: North Carolina Phone Number: (910) 892-8071 Website: www.sremc.com Twitter: https:...

  20. FirstEnergy Generation Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search Name: FirstEnergy Generation Corp Place: Ohio Twitter: @FirstEnergyCorp Facebook: https:www.facebook.comFirstEnergyCareers Outage Hotline: 1-888-544-4877 Outage...

  1. New England Hydro-Trans Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Hydro-Trans Corp Jump to: navigation, search Name: New England Hydro-Trans Corp Place: New Hampshire Phone Number: 1.800.661.3805 Website: www.transcanada.comindex.html Twitter:...

  2. New England Elec Transm'n Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Transm'n Corp Jump to: navigation, search Name: New England Elec Transm'n Corp Place: New Hampshire References: EIA Form EIA-861 Final Data File for 2010 - File1a1 EIA Form 861...

  3. Central Hudson Gas & Elec Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Gas & Elec Corp Jump to: navigation, search Name: Central Hudson Gas & Elec Corp Place: New York Phone Number: 845-452-2700 or 1-800-527-2714 Website: www.centralhudson.com...

  4. Carteret-Craven El Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Carteret-Craven El Member Corp Jump to: navigation, search Name: Carteret-Craven El Member Corp Place: North Carolina Phone Number: 252.247.3107 or 1.800.682.2217 Website:...

  5. Snapping Shoals El Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Snapping Shoals El Member Corp Jump to: navigation, search Name: Snapping Shoals El Member Corp Place: Georgia Phone Number: 770-786-3484 Website: www.ssemc.com Twitter:...

  6. Niobrara Valley El Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Member Corp Jump to: navigation, search Name: Niobrara Valley El Member Corp Place: Nebraska Phone Number: 402.336.2803 Website: nvemc.org Outage Hotline: (402) 336-2803 or (800)...

  7. Little Ocmulgee El Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Ocmulgee El Member Corp Jump to: navigation, search Name: Little Ocmulgee El Member Corp Place: Georgia Phone Number: 1-800-342-1290; 912-568-7171; 1-800-342-1290 Website:...

  8. Baldwin County El Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    El Member Corp Jump to: navigation, search Name: Baldwin County El Member Corp Place: Alabama Phone Number: (251) 989-6247 or (800) 837-3374 Website: www.baldwinemc.com Outage...

  9. Alaska District US Army Corps of Engineers | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Not Provided DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for Alaska District US Army Corps of Engineers Citation US Army Corps of...

  10. Just Energy New York Corp. (New York) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Energy New York Corp. (New York) Jump to: navigation, search Name: Just Energy New York Corp. Place: New York Phone Number: 1-877-846-0301 Website: newyork.justenergy.com Twitter:...

  11. Clay County Electric Coop Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: Clay County Electric Coop Corp Place: Arkansas Service Territory: Arkansas, Missouri Phone Number: 870.857.3521 or 870.892.5251 or...

  12. Blue Grass Energy Coop Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Grass Energy Coop Corp Jump to: navigation, search Name: Blue Grass Energy Coop Corp Place: Kentucky Phone Number: 888-546-4243 Website: www.bgenergy.com Twitter: @BlueGrassEnergy...

  13. Tri-State Electric Member Corp (Tennessee) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Tri-State Electric Member Corp (Tennessee) Jump to: navigation, search Name: Tri-State Electric Member Corp Place: Tennessee Phone Number: 706-492-3251 Website: www.tsemc.net...

  14. China National Nuclear Corp CNNC | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Nuclear Corp CNNC Jump to: navigation, search Name: China National Nuclear Corp (CNNC) Place: Beijing, China Zip: 100822 Product: The goal of CNNC is to achieve self-reliance in...

  15. Salt River Electric Coop Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    River Electric Coop Corp Jump to: navigation, search Name: Salt River Electric Coop Corp Place: Kentucky References: EIA Form EIA-861 Final Data File for 2010 - File1a1 EIA Form...

  16. Petit Jean Electric Coop Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Petit Jean Electric Coop Corp Jump to: navigation, search Name: Petit Jean Electric Coop Corp Place: Arkansas Phone Number: 501-745-2493 (Clinton) or 870-448-3477 (Marshall)...

  17. Safe Harbor Water Power Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Harbor Water Power Corp Jump to: navigation, search Name: Safe Harbor Water Power Corp Place: Pennsylvania Phone Number: 1-800-692-6328 Website: www.shwpc.com Outage Hotline:...

  18. Joe Wheeler Elec Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Joe Wheeler Elec Member Corp Jump to: navigation, search Name: Joe Wheeler Elec Member Corp Place: Alabama Phone Number: (256) 552-2300 Website: www.jwemc.org Twitter: @jwemc...

  19. Liberty Power Corp. (New York) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp. Place: New York Phone Number: 1-866-769-3799 Website: www.libertypowercorp.com Twitter: @libertypower Facebook: https:www.facebook.comLibertyPowerCorp Outage Hotline:...

  20. US BioEnergy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp Jump to: navigation, search Name: US BioEnergy Corp Place: South Dakota Zip: 57006 Product: Focused on biofuel production. Merged with VeraSun as of 1 April 2008. References:...

  1. US Energy Biogas Corp prev ZAPCO | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp prev ZAPCO Jump to: navigation, search Name: US Energy Biogas Corp (prev ZAPCO) Place: Connecticut Zip: 6001 Product: Owns and operates 26 landfill gas-to-energy (LFG)...

  2. Lab-Corps: Training National Lab Entrepreneurs to Take Clean...

    Office of Environmental Management (EM)

    Lab-Corps: Training National Lab Entrepreneurs to Take Clean Energy to Market Lab-Corps: Training National Lab Entrepreneurs to Take Clean Energy to Market March 18, 2016 - 8:54am ...

  3. Sky WindPower Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    WindPower Corp Jump to: navigation, search Name: Sky WindPower Corp Place: Ramona, California Zip: 92065 Sector: Wind energy Product: Sky WindPower is working on turbines that...

  4. Stream Fund High Tech Group Corp Ltd | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Group Corp Ltd Place: Hong Kong Product: Hong Kong-based investment company engaged in thin-film PV products and automobiles. References: Stream Fund High-Tech Group Corp Ltd1...

  5. Westwind-PacifiCorp Wind Farm | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    In Service Owner PacifiCorp Developer SeaWest Energy Purchaser Southern California EdisonPacifiCorp Location San Gorgonio CA Coordinates 33.9095, -116.734 Show Map Loading...

  6. US Army Corps of Engineers Website | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    of Engineers Website Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: US Army Corps of Engineers Website Abstract Website of the US Army Corps of...

  7. Silicon Genesis Corp SiGen | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp SiGen Jump to: navigation, search Name: Silicon Genesis Corp (SiGen) Place: San Jose, California Zip: 95134 Product: US-based manufacturer of proton-shooting wafer slicing...

  8. Marine Corps Base Quantico Achieves 85% Savings in Parking Lighting |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Quantico Achieves 85% Savings in Parking Lighting Marine Corps Base Quantico Achieves 85% Savings in Parking Lighting Marine Corps Base Quantico (MCBQ) in Virginia Marine Corps Base Quantico (MCBQ) in Virginia Document provides an overview of how the Marine Corps Base Quantico (MCBQ) achieved 85% energy savings in parking lighting at one of its parking lots as part of a major overhaul of its outdoor lighting (replacing 2,000 fixtures with light-emitting diode lights),

  9. Fuel Assembly Shaker Test for Determining Loads on a PWR Assembly...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Assembly Shaker Test for Determining Loads on a PWR Assembly under Surrogate Normal Conditions of Truck Transport R0.1 Fuel Assembly Shaker Test for Determining Loads on a PWR...

  10. PWR representative behavior during a LOCA

    SciTech Connect

    Allison, C.M.

    1981-01-01

    To date, there has been substantial analytical and experimental effort to define the margins between design basis loss-of-coolant accident (LOCA) behavior and regulatory limits on maximum fuel rod cladding temperature and deformation. As a result, there is extensive documentation on the modeling of fuel rod behavior in test reactors and design basis LOCA's. However, modeling of that behavior using representative, non-conservative, operating histories is not nearly as well documented in the public literature. Therefore, the objective of this paper is (a) to present calculations of LOCA induced behavior for Pressurized Water Reactor (PWR) core representative fuel rods, and (b) to discuss the variability in those calculations given the variability in fuel rod condition at the initiation of the LOCA. This analysis was limited to the study of changes in fuel rod behavior due to different power operating histories. The other two important parameters which affect that behavior, initial fuel rod design and LOCA coolant conditions were held invarient for all of the representative rods analyzed.

  11. Quality Assurance Review of ISOTOPE and ORIGEN Decay Masses for PWR Fuel (51 GWd/MTU)

    SciTech Connect

    Gastelum, Jason A.

    2011-03-28

    This memorandum documents the comparison of ISOTOPE decay mass calculations for PWR 51GW fuel with analogous calculations in ORIGEN.

  12. A Combined Nonfertile and UO{sub 2} PWR Fuel Assembly for Actinide...

    Office of Scientific and Technical Information (OSTI)

    the CONFU assembly exhibits negative reactivity feedback coefficients comparable in ... NUCLEAR FUELS; PWR TYPE REACTORS; REACTIVITY COEFFICIENTS; REPROCESSING; SIMULATION; ...

  13. Swing-Down of 21-PWR Waste Package

    SciTech Connect

    A.K. Scheider

    2001-05-04

    The objective of this calculation is to determine the structural response of the waste package (WP) swinging down from a horizontally suspended height. The WP used for that purpose is the 21-Pressurized Water Reactor (PWR) WP. The scope of this document is limited to reporting the calculation results in terms of stress intensities. This calculation is associated with the WP design and was performed by the Waste Package Design group in accordance with the ''Technical Work Plan for: Waste Package Design Description for LA'' (Ref. 13). AP-3.12Q, ''Calculations'' (Ref. 18) is used to perform the calculation and develop the document. The information provided by the sketches attached to this calculation is that of the potential design of the type of 21-PWR WP design considered in this calculation and provides the potential dimensions and materials for the 21-PWR WP design.

  14. Leak before break application in French PWR plants under operation

    SciTech Connect

    Faidy, C.

    1997-04-01

    Practical applications of the leak-before break concept are presently limited in French Pressurized Water Reactors (PWR) compared to Fast Breeder Reactors. Neithertheless, different fracture mechanic demonstrations have been done on different primary, auxiliary and secondary PWR piping systems based on similar requirements that the American NUREG 1061 specifications. The consequences of the success in different demonstrations are still in discussion to be included in the global safety assessment of the plants, such as the consequences on in-service inspections, leak detection systems, support optimization,.... A large research and development program, realized in different co-operative agreements, completes the general approach.

  15. Marine Corps Base Camp Pendleton | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Camp Pendleton Marine Corps Base Camp Pendleton Fact sheet describes the Energy savings Performance Contract (ESPC) Success Story on how a comprehensive effort cuts energy use by 44% at Marine Corps Base Camp Pendleton in Camp Pendleton, California. Download the Marine Corps Base Camp Pendleton fact sheet. (162.82 KB) More Documents & Publications 2013 Federal Energy and Water Management Award Winner Jeff Allen Camp Pendleton Saves 91% in Parking Lot Lighting Energy Savings Performance

  16. Lab-Corps Cohort 4 Teams | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Cohort 4 Teams Lab-Corps Cohort 4 Teams October 18 - December 8, 2016 Golden, CO Information about the Lab-Corps cohort 4 teams, their technologies, and how Lab-Corps is helping the teams fine-tune their commercialization approaches are highlighted here. Idaho National Laboratory - CellSage Idaho National Laboratory - Detection Systems Idaho National Laboratory - Dry Cask Vital Signs Idaho National Laboratory - E-RECOV Idaho National Laboratory - Optiblend Lawrence Livermore National Laboratory

  17. Kyungdong Photovoltaic Energy Corp KPE formerly Photon Semiconductor...

    OpenEI (Open Energy Information) [EERE & EIA]

    formerly Photon Semiconductor Energy Jump to: navigation, search Name: Kyungdong Photovoltaic Energy Corp (KPE) (formerly Photon Semiconductor & Energy) Place: Changwon, South...

  18. Associated Media Holdings Inc formerly EL Tigre Development Corp...

    OpenEI (Open Energy Information) [EERE & EIA]

    Tigre Development Corp) Place: San Diego, California Zip: 92150-2548 Product: Engaged in research, development and commercialization of technologies for the production of...

  19. Liberty Power Corp. (Rhode Island) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Place: Rhode Island Website: www.libertypowercorp.combusin Twitter: @libertypower Facebook: https:www.facebook.comLibertyPowerCorp Outage Hotline: 1-800-465-1212 Outage Map:...

  20. Nippon Coke and Engineering Sumitomo Corp JV | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    navigation, search Name: Nippon Coke and Engineering & Sumitomo Corp JV Place: Tokyo, Japan Zip: 135-6007 Product: Japan-based natural graphite base anode materials joint...

  1. Sumitomo Mitsubishi Silicon Corp SUMCO | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    navigation, search Name: Sumitomo Mitsubishi Silicon Corp (SUMCO) Place: Tokyo, Tokyo, Japan Zip: 105 8634 Product: Holding company; Japanese manufacturer of monocrystalline...

  2. 1,"Kingdom Community Wind","Wind","Green Mountain Power Corp...

    Energy Information Administration (EIA) (indexed site)

    Vermont" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Kingdom Community Wind","Wind","Green Mountain Power Corp",65 2,"J C ...

  3. US Energy Initiatives Corp formerly Hybrid Fuel Systems Inc ...

    OpenEI (Open Energy Information) [EERE & EIA]

    Fuel Systems Inc) Place: Tampa, Florida Zip: 33637 Product: Holds patented natural gasdiesel dual fuel technology. References: US Energy Initiatives Corp (formerly Hybrid...

  4. DOE - Office of Legacy Management -- Oliver Corp - MI 11

    Office of Legacy Management (LM)

    OLIVER CORP. (MI.11 ) Eliminated from further consideration under FUSRAP - Referred to NRC Designated Name: Not Designated Alternate Name: Behnke Warehousing Incorporated MI.11-1...

  5. DOE - Office of Legacy Management -- American Bearing Corp -...

    Office of Legacy Management (LM)

    Bearing Corp. (IN.09 ) Eliminated from further consideration under FUSRAP - Referred to NRC Designated Name: Not Designated Alternate Name: None Location: 429 South Harding Street...

  6. Choice FuelCorp Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Pennsylvania Zip: 17702 Product: Pennsylvania-based biodiesel producer, from its plant in Williamsport. References: Choice FuelCorp, Inc.1 This article is a stub. You...

  7. Tipmont Rural Elec Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search Name: Tipmont Rural Elec Member Corp Abbreviation: Tipmont REMC Address: 403 S Main St Place: Linden, Indiana Zip: 47955 Phone Number: 800-726-3953 Website:...

  8. First Energy Solutions Corp. (Illinois) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Illinois) Jump to: navigation, search Name: First Energy Solutions Corp. Place: Illinois Phone Number: 1-888-254-6359 Website: www.fes.comcontentfeshomer Twitter:...

  9. Imara Corp formerly Lion Cells | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Cells) Place: Menlo Park, California Zip: 94025 Product: California-based developer of lithium-ion battery technologies formerly known as Lion Cells. References: Imara Corp...

  10. Wuhan Lixun Power Corp Ltd LISUN | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Name: Wuhan Lixun Power Corp Ltd (LISUN) Place: China Product: China-based maker of Lithium-ion secondary batteries, primary batteries and battery test equipment. References:...

  11. ICeL Systems Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search Name: iCeL Systems Corp Sector: Renewable Energy Product: Focused on Lithium based energy storage and management systems for the renewable energy market....

  12. Li ion Motors Corp formerly EV Innovations Inc | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Vegas, Nevada Zip: 89110 Sector: Vehicles Product: Las Vegas - based manufacturer of lithium-powered plug-in vehicles. References: Li-ion Motors Corp (formerly EV Innovations...

  13. Unitech Printed Circuit Board Corp UPCB | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Sector: Solar Product: Taiwan-based printed-circuit board maker with intent to enter into solar cell manufacturing industry. References: Unitech Printed Circuit Board Corp....

  14. South Kentucky Rural Electric Coop Corp (Tennessee) | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Electric Coop Corp Place: Tennessee Phone Number: 800-772-4636 Website: www.skrecc.com Twitter: @skrecc Facebook: https:www.facebook.compagesSouth-Kentucky-RECC...

  15. DOE - Office of Legacy Management -- Beryllium Corp - PA 39

    Office of Legacy Management (LM)

    FUSRAP Also see Documents Related to BERYLLIUM CORP. PA.39-1 - MemorandumChecklist; D. Levine to the File; Subject: Elimination Recommendation (Beryllium Corporation); June 17...

  16. DOE - Office of Legacy Management -- Fansteel Metallurgical Corp...

    Office of Legacy Management (LM)

    Daley; Subject: Fansteel Metallurgical Corp. Information; January 13, 1995 IL.16-3 - MemorandumChecklist; Young to the File; Subject: Elimination Recommendation; October 28, 1987...

  17. Army Corps of Engineers - Regulatory Guidance Letters | Open...

    OpenEI (Open Energy Information) [EERE & EIA]

    Guidance Letters Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Army Corps of Engineers - Regulatory Guidance Letters Abstract This webpage...

  18. Advanced Energy Products Corp AEP | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp. (AEP) Place: Davis, California Zip: 95619 Product: Created to commercialise energy saving products developed by Davis Energy Group. Coordinates: 39.12868, -79.465714...

  19. DOE - Office of Legacy Management -- Nuclear Development Corp...

    Office of Legacy Management (LM)

    Development Corp of America - NY 32 FUSRAP Considered Sites Site: NUCLEAR DEVELOPMENT ... - Facility was licensed to handle nuclear materials NY.32-2 NY.32-3 Radioactive ...

  20. DOE - Office of Legacy Management -- Pasadena Chemical Corp Pilot...

    Office of Legacy Management (LM)

    Designated Name: Not Designated Alternate Name: Olin Mathieson Chemical Corp. Mobil Mining ... TX.01-1 - DOE Report; FUSRAP Elimination Report for Mobil Mining and Minerals Company (The ...

  1. KL Energy Corp Formerly KL Process Design Group | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    provider of engineering, procurement, and contracting. Operates both greenfield and brownfield projects. References: KL Energy Corp. (Formerly KL Process Design Group)1 This...

  2. Solar Applied Materials Technology Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Name: Solar Applied Materials Technology Corp Place: Tainan, Taiwan Product: Taiwan's material process specialists with over 20 years experience and in the areas of sputtering...

  3. Vision Machine & Fabrication Corp. Named Top Small Business Subcontrac...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Vision Machine & Fabrication Corp. Named Top Small Business Subcontractor at Jefferson Lab for FY 2014 NEWPORT NEWS, VA, Sept. 10, 2015 - Jefferson Science Associates, the...

  4. DOE - Office of Legacy Management -- New York Shipbuilding Corp...

    Office of Legacy Management (LM)

    Site: NEW YORK SHIPBUILDING CORP. (NJ.34) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: South Yard, New York ...

  5. Lab-Corps Pilot Trains Scientists in Commercialization

    Energy.gov [DOE]

    The Biolyst Renewables team has a new perspective on bringing new technologies to commercialization thanks to the Office of Energy Efficiency and Renewable Energy's Lab-Corps pilot.

  6. USACE Engineer Regulation 1110-2-1454 Corps Responsibilities...

    OpenEI (Open Energy Information) [EERE & EIA]

    USACE Engineer Regulation 1110-2-1454 Corps Responsibilities for Non-Federal Hydroelectric Power Development under the Federal Power Act Jump to: navigation, search OpenEI...

  7. U S Army Corps of Engineers | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Contact Twitter: @detroitdistrict Facebook: https:www.facebook.compagesDetroit-District-US-Army-Corps-of-Engineers144354390916 References: EIA Form EIA-861 Final...

  8. United States Army Corp of Engineers (ERDC) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Engineers (ERDC) Jump to: navigation, search Hydro | Hydrodynamic Testing Facilities Name United States Army Corp of Engineers (ERDC) Address Coastal & Hydraulics Laboratory, 3909...

  9. Memorandum of Understanding Between United States Army Corps...

    OpenEI (Open Energy Information) [EERE & EIA]

    Between United States Army Corps of Engineers and the Federal Energy Regulatory Commission on Non-Federal Hydropower Projects Jump to: navigation, search OpenEI Reference...

  10. Targeting Net Zero Energy at Marine Corps Air Station Miramar...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Targeting Net Zero Energy at Marine Corps Air Station Miramar: Assessment and ... laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable ...

  11. Analysis of PWR RCS Injection Strategy During Severe Accident

    SciTech Connect

    Wang, S.-J. [Institute of Nuclear Energy Research, Taiwan (China); Chiang, K.-S. [Institute of Nuclear Energy Research, Taiwan (China); Chiang, S.-C. [Taiwan Power Company, Taiwan (China)

    2004-05-15

    Reactor coolant system (RCS) injection is an important strategy for severe accident management of a pressurized water reactor (PWR) system. Maanshan is a typical Westinghouse PWR nuclear power plant (NPP) with large, dry containment. The severe accident management guideline (SAMG) of Maanshan NPP is developed based on the Westinghouse Owners Group (WOG) SAMG.The purpose of this work is to analyze the RCS injection strategy of PWR system in an overheated core condition. Power is assumed recovered as the vessel water level drops to the bottom of active fuel. The Modular Accident Analysis Program version 4.0.4 (MAAP4) code is chosen as a tool for analysis. A postulated station blackout sequence for Maanshan NPP is cited as a reference case for this analysis. The hot leg creep rupture occurs during the mitigation action with immediate injection after power recovery according to WOG SAMG, which is not desired. This phenomenon is not considered while developing the WOG SAMG. Two other RCS injection methods are analyzed by using MAAP4. The RCS injection strategy is modified in the Maanshan SAMG. These results can be applied for typical PWR NPPs.

  12. St Lawrence Energy Corp formerly known as UroMed Corporation...

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp. (OTC: SLAW) is a Delaware company focused on the energy sector, including renewable energy and chemical transportation. References: St. Lawrence Energy Corp (formerly known...

  13. HydroChina ZhongNan Engineering Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    ZhongNan Engineering Corp Jump to: navigation, search Name: HydroChina ZhongNan Engineering Corp Place: Hunan Province, China Sector: Hydro, Wind energy Product: Hunan...

  14. Jiangxi Solar PV Corp JSPV aka Solar PV Corporation | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Solar PV Corp JSPV aka Solar PV Corporation Jump to: navigation, search Name: Jiangxi Solar PV Corp (JSPV, aka Solar PV Corporation ) Place: Xinyu, Jiangxi Province, China Zip:...

  15. Microsoft PowerPoint - 2015-06-18 Corps Columbia Riverkeeper...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Federal Columbia River Power System Generation & Transmission - System Map The FCRPS 31 dams 21 Corps ... at Corps of Engineer labs and the Hydroelectric Design Center. ...

  16. Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment and Recommendations Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment...

  17. DOE - Office of Legacy Management -- U S Radium Corp - NJ 09

    Office of Legacy Management (LM)

    Radium Corp - NJ 09 FUSRAP Considered Sites Site: U S Radium Corp (NJ.09) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive...

  18. Robotic inspection of PWR coolant pump casing welds

    SciTech Connect

    Pratt, W.R.; Alford, J.W.; Davis, J.B.

    1997-12-01

    As of January 1, 1995, the Swedish Nuclear Inspectorate began requiring more thorough inspections of cast stainless-steel components in nuclear power plants, including pressurized water reactor (PWR) reactor coolant pump (RCP) casings. The examination requirements are established by fracture mechanics analyses of component weldments and demonstrated test system detection capabilities. This may include full volumetric inspection or some portion thereof. Ringhals station is a four-unit nuclear power plant, owned and operated by the Swedish State Power Board, Vattenfall. Unit 1 is a boiling water reactor. Units 2, 3, and 4 are Westinghouse-designed PWRs, ranging in size from 795 to 925 MW. The RCP casings at the PWR units are made of cast stainless steel and contain four circumferential welds that require inspection. Due to the thickness of the casings at the weld locations and configuration and surface conditions on the outside diameter of the casings, remote inspection from the inside diameter of the pump casing was mandated.

  19. Chemical behavior of fission products in the ORNL fission product release program. Supplement. [PWR; BWR

    SciTech Connect

    Collins, J.L.; Osborne, M.F.; Lorenz, R.A.

    1983-01-01

    Tests data are presented for BWR and PWR rods in test HI-4 and test HI-5. Operating conditions fission product release data are included.

  20. Design study of long-life PWR using thorium cycle

    SciTech Connect

    Subkhi, Moh. Nurul; Su'ud, Zaki; Waris, Abdul

    2012-06-06

    Design study of long-life Pressurized Water Reactor (PWR) using thorium cycle has been performed. Thorium cycle in general has higher conversion ratio in the thermal spectrum domain than uranium cycle. Cell calculation, Burn-up and multigroup diffusion calculation was performed by PIJ-CITATION-SRAC code using libraries based on JENDL 3.2. The neutronic analysis result of infinite cell calculation shows that {sup 231}Pa better than {sup 237}Np as burnable poisons in thorium fuel system. Thorium oxide system with 8%{sup 233}U enrichment and 7.6{approx} 8%{sup 231}Pa is the most suitable fuel for small-long life PWR core because it gives reactivity swing less than 1%{Delta}k/k and longer burn up period (more than 20 year). By using this result, small long-life PWR core can be designed for long time operation with reduced excess reactivity as low as 0.53%{Delta}k/k and reduced power peaking during its operation.

  1. VeraSun Energy Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    VeraSun Energy Corp Place: Aurora, South Dakota Zip: 57002 Product: VeraSun uses biotechnology to convert corn to fuel-grade ethanol, which is blended with gasoline and results...

  2. Middle Georgia El Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    El Member Corp Place: Georgia Phone Number: 1-800-342-0144 Website: www.mgemc.com Facebook: https:www.facebook.comMiddleGeorgiaEMC Outage Hotline: 229-268-2671; 800-342-0144...

  3. Indiana-Kentucky Electric Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search Name: Indiana-Kentucky Electric Corp Place: Ohio Website: www.ovec.comindex.php Outage Hotline: (740) 289-7200 References: EIA Form EIA-861 Final Data File for 2010 -...

  4. First Energy Solutions Corp. (Michigan) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Corp. Place: Michigan Phone Number: 1-888-254-4769 Website: www.fes.comcontentfeshome.h Outage Hotline: Contact Local Utility Company References: EIA Form EIA-861 Final Data...

  5. Okefenoke Rural El Member Corp (Florida) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Florida) Jump to: navigation, search Name: Okefenoke Rural El Member Corp Place: Florida Phone Number: 1-800-432-4770 Website: www.oremc.com Outage Hotline: 1.800.262.5131 Outage...

  6. Okefenoke Rural El Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Okefenoke Rural El Member Corp Place: Georgia Phone Number: 1-800-262-5131 Website: www.oremc.com Outage Hotline: 1-800-262-5131 References: EIA Form EIA-861 Final Data File for...

  7. Central Georgia El Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Central Georgia El Member Corp Place: Georgia Phone Number: 770-775-7857 Website: www.cgemc.com Twitter: @CentralGAEMC Outage Hotline: 770-775-7857 References: EIA Form EIA-861...

  8. Blue Ridge Elec Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Blue Ridge Elec Member Corp Place: North Carolina Phone Number: 1-800-448-2383 Website: www.blueridgeemc.com Twitter: @blueridgeemc Facebook: https:www.facebook.comBlueRidgeEMC...

  9. Tri-State Electric Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Tri-State Electric Member Corp Place: McCaysville, Georgia References: EIA Form EIA-861 Final Data File for 2010 - File1a1 SGIC2 EIA Form 861 Data Utility Id 19154 Utility...

  10. French Broad Elec Member Corp (Tennessee) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    French Broad Elec Member Corp Place: Tennessee Phone Number: (828)649-2051 or (828)688-4815 or (800)222-6190 or (828)682-6121 Website: www.frenchbroademc.com Twitter:...

  11. French Broad Elec Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    French Broad Elec Member Corp Place: North Carolina Phone Number: (828)649-2051 or (828)688-4815 or (800)222-6190 or (828)682-6121 Website: www.frenchbroademc.com Twitter:...

  12. First Energy Solutions Corp. (Pennsylvania) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Pennsylvania) Jump to: navigation, search Name: First Energy Solutions Corp. Place: Pennsylvania Phone Number: 1-888-254-6359 or 1-888-254-4769 Website: www.fes.comcontentfes...

  13. First Energy Solutions Corp. (Maryland) | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Maryland) Jump to: navigation, search Name: First Energy Solutions Corp. Place: Maryland Phone Number: 1-888-254-4769 or 1-888-254-6359 Website: www.firstenergycorp.comconten...

  14. Arima EcoEnergy Technologies Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    33547 Product: CPV systems integrator and module maker which also makes trackers and inverters. References: Arima EcoEnergy Technologies Corp1 This article is a stub. You can...

  15. DOE - Office of Legacy Management -- Metals Selling Corp - CT...

    Office of Legacy Management (LM)

    under FUSRAP Also see Documents Related to METALS SELLING CORP. CT.0-01-1 - DOE MemorandumChecklist D. Levine to File; Subject - Elimination Recommendation; December 19, 198...

  16. DOE - Office of Legacy Management -- Bakelite Corp - NJ 35

    Office of Legacy Management (LM)

    under FUSRAP Also see Documents Related to Bakelite Corp NJ.35-1 - DOE ChecklistMemorandum; D.Levine to the File; Subject: Elimination Recommendation; December 19, 198...

  17. North Georgia Elec Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    navigation, search Name: North Georgia Elec Member Corp Place: Georgia Phone Number: Dalton: (706) 259-9441; Fort Oglethorpe: (706) 866-2231; Calhoun: (706) 629-3160; Trion:...

  18. DOE - Office of Legacy Management -- Amex Specialty Metal Corp...

    Office of Legacy Management (LM)

    see Documents Related to Amex Specialty Metal Corp MI.0-01-1 - MemorandumChecklist; C.Young to the File; Subject: Elimination Recommendation; November 5, 1987 MI.0-01-2 - DOE...

  19. CORPES 11: International Workshop on Strong Correlations and...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    you to Joy Kono, Jill Stark, Mayra Rivas, Grace Covarrubias, Cynthia Perez, and Adriana Reza for their invaluable administrative support. We look forward to CORPES13, which will be...

  20. DOE - Office of Legacy Management -- Allegheny-Ludlum Steel Corp...

    Office of Legacy Management (LM)

    Site: ALLEGHENY-LUDLUM STEEL CORP. (NY.0-02 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: Al-Tech Specialty Steel NY.0-02-1 Location: ...

  1. Lawrence Livermore National Laboratory's Lab-Corps Cohort Returns

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Invigorated | Department of Energy Lawrence Livermore National Laboratory's Lab-Corps Cohort Returns Invigorated Lawrence Livermore National Laboratory's Lab-Corps Cohort Returns Invigorated May 31, 2016 - 1:54pm Addthis Researchers examine a "homemade" rare earth purification column packed with alginate beads with bioengineered microbes embedded in them. This LLNL-led effort holds promise for the development of an innovative, cost-effective, “green” bio-adsorption

  2. Marine Corps Base Quantico Achieves 85% Savings in Parking Lighting

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Marine Corps Base Quantico Achieves 85% Savings in Parking Lighting LED Parking Lighting in Federal Facilities FEDERAL ENERGY MANAGEMENT PROGRAM With technical assistance from the Federal Energy Management Program (FEMP), the Marine Corps Base Quantico (MCBQ) recently undertook a major overhaul of its outdoor lighting, boosting safety and security throughout the site, while cutting energy costs and earning a national award in the process. The MCBQ replaced nearly 2,000 old and ineffcient street

  3. DOE's Lab-Corps Syllabus Sample | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Syllabus Sample DOE's Lab-Corps Syllabus Sample DOE's Lab-Corps Syllabus Sample (1.04 MB) More Documents & Publications Microsoft Word - T4_VEIC_TO2_ Sub3_Residential Retrofit Program Design Guide Play Book_TEAM 4 FINAL.docx Before the House Energy and Commerce Subcommittee on Energy and Power Proceedings of the Computational Needs for the Next Generation Electric Grid Workshop, April 19-20, 2011

  4. ACHILLES: Heat Transfer in PWR Core During LOCA Reflood Phase

    SciTech Connect

    2013-11-01

    1. NAME AND TITLE OF DATA LIBRARY ACHILLES -Heat Transfer in PWR Core During LOCA Reflood Phase. 2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS N/A 3. CONTRIBUTOR AEA Technology, Winfrith Technology Centre, Dorchester DT2 8DH United Kingdom through the OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France. 4. DESCRIPTION OF TEST FACILITY The most important features of the Achilles rig were the shroud vessel, which contained the test section, and the downcomer. These may be thought of as representing the core barrel and the annular downcomer in the reactor pressure vessel. The test section comprises a cluster of 69 rods in a square array within a circular shroud vessel. The rod diameter and pitch (9.5 mm and 12.6 mm) were typical of PWR dimensions. The internal diameter of the shroud vessel was 128 mm. Each rod was electrically heated over a length of 3.66 m, which is typical of the nuclear heated length in a PWR fuel rod, and each contained 6 internal thermocouples. These were arranged in one of 8 groupings which concentrated the thermocouples in different axial zones. The spacer grids were at prototypic PWR locations. Each grid had two thermocouples attached to its trailing edge at radial locations. The axial power profile along the rods was an 11 step approximation to a "chopped cosine". The shroud vessel had 5 heating zones whose power could be independently controlled. 5. DESCRIPTION OF TESTS The Achilles experiments investigated the heat transfer in the core of a Pressurized Water Reactor during the re-flood phase of a postulated large break loss of coolant accident. The results provided data to validate codes and to improve modeling. Different types of experiments were carried out which included single phase cooling, re-flood under low flow conditions, level swell and re-flood under high flow conditions. Three series of experiments were performed. The first and the third used the same test section but the second used another test section, similar in

  5. ACHILLES: Heat Transfer in PWR Core During LOCA Reflood Phase

    Energy Science and Technology Software Center

    2013-11-01

    1. NAME AND TITLE OF DATA LIBRARY ACHILLES -Heat Transfer in PWR Core During LOCA Reflood Phase. 2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS N/A 3. CONTRIBUTOR AEA Technology, Winfrith Technology Centre, Dorchester DT2 8DH United Kingdom through the OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France. 4. DESCRIPTION OF TEST FACILITY The most important features of the Achilles rig were the shroud vessel, which contained the test section, and the downcomer. These maymore » be thought of as representing the core barrel and the annular downcomer in the reactor pressure vessel. The test section comprises a cluster of 69 rods in a square array within a circular shroud vessel. The rod diameter and pitch (9.5 mm and 12.6 mm) were typical of PWR dimensions. The internal diameter of the shroud vessel was 128 mm. Each rod was electrically heated over a length of 3.66 m, which is typical of the nuclear heated length in a PWR fuel rod, and each contained 6 internal thermocouples. These were arranged in one of 8 groupings which concentrated the thermocouples in different axial zones. The spacer grids were at prototypic PWR locations. Each grid had two thermocouples attached to its trailing edge at radial locations. The axial power profile along the rods was an 11 step approximation to a "chopped cosine". The shroud vessel had 5 heating zones whose power could be independently controlled. 5. DESCRIPTION OF TESTS The Achilles experiments investigated the heat transfer in the core of a Pressurized Water Reactor during the re-flood phase of a postulated large break loss of coolant accident. The results provided data to validate codes and to improve modeling. Different types of experiments were carried out which included single phase cooling, re-flood under low flow conditions, level swell and re-flood under high flow conditions. Three series of experiments were performed. The first and the third used the same test section but the second used another test section

  6. 21-PWR WASTE PACKAGE WITH ABSORBER PLATES LOADING CURVE EVALUATION

    SciTech Connect

    J.M. Scaglione

    2004-12-17

    The objective of this calculation is to evaluate the required minimum burnup as a function of initial pressurized water reactor (PWR) assembly enrichment that would permit loading of spent nuclear fuel into the 21 PWR waste package with absorber plates design as provided in Attachment IV. This calculation is an example of the application of the methodology presented in the ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003). The scope of this calculation covers a range of enrichments from 0 through 5.0 weight percent U-235, and a burnup range of 0 through 45 GWd/MTU. Higher burnups were not necessary because 45 GWd/MTU was high enough for the loading curve determination. This activity supports the validation of the use of burnup credit for commercial spent nuclear fuel applications. The intended use of these results will be in establishing PWR waste package configuration loading specifications. Limitations of this evaluation are as follows: (1) The results are based on burnup credit for actinides and selected fission products as proposed in YMP (2003, Table 3-1) and referred to as the ''Principal Isotopes''. Any change to the isotope listing will have a direct impact on the results of this report. (2) The results are based on 1.5 wt% Gd in the Ni-Gd Alloy material and having no tuff inside the waste package. If the Gd loading is reduced or a process to introduce tuff inside the waste package is defined, then this report would need to be reevaluated based on the alternative materials. This calculation is subject to the ''Quality Assurance Requirements and Description'' (QARD) (DOE 2004) because it concerns engineered barriers that are included in the ''Q-List'' (BSC 2004k, Appendix A) as items important to safety and waste isolation.

  7. Comparison of PWR-IMF and FR fuel cycles

    SciTech Connect

    Darilek, Petr; Zajac, Radoslav; Breza, Juraj |; Necas, Vladimir

    2007-07-01

    The paper gives a comparison of PWR (Russia origin VVER-440) cycle with improved micro-heterogeneous inert matrix fuel assemblies and FR cycle. Micro-heterogeneous combined assembly contains transmutation pins with Pu and MAs from burned uranium reprocessing and standard uranium pins. Cycle analyses were performed by HELIOS spectral code and SCALE code system. Comparison is based on fuel cycle indicators, used in the project RED-IMPACT - part of EU FP6. Advantages of both closed cycles are pointed out. (authors)

  8. CASL - PWR Reactor Vessel Multi-Physics CFD Model

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    PWR Reactor Vessel Multi-Physics CFD Model Jin Yan*1, Yiban Xu1, Andrew Petrarca1, Zeses Karoutas1, Emre Tatli1, Emilio Baglietto2, Jess Gehin3 1Westinghouse Electric Company LLC 2Massachusetts Institute of Technology 3Oak Ridge National Lab *Correspondence to: yan3j@westinghouse.com A complete 3D SolidWorks CAD model of Watts Bar Unit 1 was constructed based on drawings. A single fuel assembly CAD model including all geometrical details was created based on the Westinghouse V5H 17x17 fuel

  9. Waterside corrosion of Zircaloy fuel rods. Final report. [PWR

    SciTech Connect

    Garzarolli, F.; Jung, W.; Schoenfeld, H.; Garde, A.M.; Parry, G.W.; Smerd, P.G.

    1982-12-01

    There is an economic incentive to extend average fuel-rod-discharge burnup to about 50 GWd/t. For these higher burnups it is necessary to know if increased waterside corrosion of the cladding will influence fuel-rod performance. For this reason, EPRI sponsored a joint program with C-E and KWU with the objective of investigating PWR waterside corrosion. This final report presents and discusses the results of various subtasks that comprised this project. In the review of corrosion data and models in the literature it was concluded that the PWR environment enhances the corrosion rate by about three times that expected from ex-reactor tests. A large number of fuel rods were characterized in both spent-fuel-pool and hot-cell campaigns. Chemical, physical and microstructural attributes of irradiated and unirradiated oxide films were measured. These included determinations of chemical composition, crystal structure, microstructure, density, specific heat, thermal conductivity, and post-irradiation autoclave corrosion behavior. Procedures used to calculate the fuel-rod surface temperature were reviewed. A model has been developed to predict in-reactor corrosion behavior.

  10. Westinghouse VANTAGE+ fuel assembly to meet future PWR operating requirements

    SciTech Connect

    Doshi, P.K.; Chapin, D.L.; Scherpereel, L.R.

    1988-01-01

    Many utilities operating pressurized water reactors (PWRs) are implementing longer reload cycles. Westinghouse is addressing this trend with fuel products that increase fuel utilization through higher discharge burnups. Higher burnup helps to offset added enriched uranium costs necessary to enable the higher energy output of longer cycles. Current fuel products have burnup capabilities in the area of 40,000 MWd/tonne U or more. There are three main phenomena that must be addressed to achieve even higher burnup levels: accelerated cladding, waterside corrosion, and hydriding; increased fission gas production; and fuel rod growth. Long cycle lengths also require efficient burnable absorbers to control the excess reactivity associated with increased fuel enrichment while maintaining a low residual absorber penalty at the end of cycle. Westinghouse VANTAGE + PWR fuel incorporates features intended to enhance fuel performance at very high burnups, including advances in the three basic elements of the fuel assembly: fuel cladding, fuel rod, and fuel assembly skeleton. ZIRLO {sup TM} cladding, an advanced Zircaloy cladding that contains niobium, offers a significant improvement in corrosion resistance relative to Zircaloy-4. Another important Westinghouse PWR fuel feature that facilitates long cycles is the zirconium diboride integral fuel burnable absorber (ZrB{sub 2}IFBA).

  11. 21-PWR Waste Package Side and End Impacts

    SciTech Connect

    V. Delabrosse

    2003-02-27

    The objective of this calculation is to determine the structural response of a 21-Pressurized Water Reactor (PWR) spent nuclear fuel waste package impacting an unyielding surface. A range of initial velocities and initial angles between the waste package and the unyielding surface is studied. The scope of this calculation is limited to estimating the area of the outer shell (OS) where the residual stress exceeds a given limit (hereafter ''damaged area''). The stress limit is defined as a fraction of the yield strength of the OS material, Alloy 22 (SB-575 N06022), at the appropriate temperature. The design of the 21-PWR waste package used in this calculation is that defined in Reference 8. However, a value of 4 mm was used for the gap between the inner shell and the OS, and the thickness of the OS was reduced by 2 mm. The sketch in Attachment I provides additional information not included in Reference 8. All obtained results are valid for this design only. This calculation is associated with the waste package design and was performed by the Specialty Analyses and Waste Package Design Section. The waste package (i.e. uncanistered spent nuclear fuel disposal container) is classified as Quality Level 1.

  12. 21-PWR Waste Package Side and End Impacts

    SciTech Connect

    T. Schmitt

    2005-08-29

    The objective of this calculation is to determine the structural response of a 21-Pressurized Water Reactor (PWR) spent nuclear fuel waste package impacting an unyielding surface. A range of initial velocities and initial angles between the waste package and the unyielding surface is studied. The scope of this calculation is limited to estimating the area of the outer shell (OS) where the residual stress exceeds a given limit (hereafter ''damaged area''). The stress limit is defined as a fraction of the yield strength of the OS material, Alloy 22 (SB-575 N06022), at the appropriate temperature. The design of the 21-PWR waste package used in this calculation is that defined in Reference 8. However, a value of 4 mm was used for the gap between the inner shell and the OS, and the thickness of the OS was reduced by 2 mm. The sketch in Attachment I provides additional information not included in Reference 8. All obtained results are valid for this design only. This calculation is associated with the waste package design and was performed by the Specialty Analyses and Waste Package Design Section. The waste package (i.e. uncanistered spent nuclear fuel disposal container) is classified as Quality Level 1.

  13. Advanced Integral-type Small-size PWR - SMART

    SciTech Connect

    Chang, Moon H.; Zee, Sung Q.; Kim, Keung K.; Kim, Si-Hwan

    2004-07-01

    SMART - an advanced integral-type small-size PWR has been developed for the dual purpose applications of seawater desalination and small-scale power generation. SMART, rated thermal power of 330 MW, adopts various new and innovative design features along with proven PWR technologies, and the non-site-specific basic design has been completed. Highly enhanced safety and reliability, improved performance, simplicity, and modularization are those of strongly emphasized design philosophies which were applied to the system design. The inherent safety improving design and passive safety design features are the key safety design features uniquely characterizing SMART compared to the conventional loop-type reactors. Various transients and accidents were analyzed for the SMART basic design, and the results confirm that safety is assured with margins in any postulated transient and accident. Further, the level-1 full power PSA shows that the core damage frequency is about two orders of magnitude less than those of the existing conventional PWRs. Based on the safety and reliability analyses, it is found that design optimization will further improve the level of safety. Various design verification efforts have been carried out and others are currently underway. (authors)

  14. VERA Core Simulator Methodology for PWR Cycle Depletion

    SciTech Connect

    Kochunas, Brendan; Collins, Benjamin S; Jabaay, Daniel; Kim, Kang Seog; Graham, Aaron; Stimpson, Shane; Wieselquist, William A; Clarno, Kevin T; Palmtag, Scott; Downar, Thomas; Gehin, Jess C

    2015-01-01

    This paper describes the methodology developed and implemented in MPACT for performing high-fidelity pressurized water reactor (PWR) multi-cycle core physics calculations. MPACT is being developed primarily for application within the Consortium for the Advanced Simulation of Light Water Reactors (CASL) as one of the main components of the VERA Core Simulator, the others being COBRA-TF and ORIGEN. The methods summarized in this paper include a methodology for performing resonance self-shielding and computing macroscopic cross sections, 2-D/1-D transport, nuclide depletion, thermal-hydraulic feedback, and other supporting methods. These methods represent a minimal set needed to simulate high-fidelity models of a realistic nuclear reactor. Results demonstrating this are presented from the simulation of a realistic model of the first cycle of Watts Bar Unit 1. The simulation, which approximates the cycle operation, is observed to be within 50 ppm boron (ppmB) reactivity for all simulated points in the cycle and approximately 15 ppmB for a consistent statepoint. The verification and validation of the PWR cycle depletion capability in MPACT is the focus of two companion papers.

  15. CNCS AmeriCorps State and National FY2015 Partnership Challenge Grant

    Energy.gov [DOE]

    Through the AmeriCorps Partnership Challenge, nonprofit organizations or public agencies – together with their funding partners – will develop proposals for addressing community needs by engaging AmeriCorps members.

  16. U.S. Army Corps of Engineers' Nationwide Permit Information Website...

    OpenEI (Open Energy Information) [EERE & EIA]

    U.S. Army Corps of Engineers' Nationwide Permit Information Website Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: U.S. Army Corps of Engineers'...

  17. 33 CFR 209.140 Operations of the Corps of Engineers under the...

    OpenEI (Open Energy Information) [EERE & EIA]

    Corps of Engineers under the Federal Power ActLegal Abstract Outlines policies and procedures applicable to those operations in which the Corps of Engineers may be called upon to...

  18. SWTC v. Arizona Corp. Comn, 142 P3d 1240 (2006) | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    SWTC v. Arizona Corp. Comn, 142 P3d 1240 (2006) Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal CaseHearing: SWTC v. Arizona Corp. Comn, 142 P3d 1240...

  19. April 13 2011 Webinar: A Guide to Using AmeriCorps NCCC Teams to Execute Your Mission

    Energy.gov [DOE]

    April 13 2011 Webinar: A Guide to Using AmeriCorps NCCC Teams to Execute Your Mission; help with program implementating AmeriCorps’ National Civilian Community Corps.

  20. Fracture mechanics evaluation for at typical PWR primary coolant pipe

    SciTech Connect

    Tanaka, T.; Shimizu, S.; Ogata, Y.

    1997-04-01

    For the primary coolant piping of PWRs in Japan, cast duplex stainless steel which is excellent in terms of strength, corrosion resistance, and weldability has conventionally been used. The cast duplex stainless steel contains the ferrite phase in the austenite matrix and thermal aging after long term service is known to change its material characteristics. It is considered appropriate to apply the methodology of elastic plastic fracture mechanics for an evaluation of the integrity of the primary coolant piping after thermal aging. Therefore we evaluated the integrity of the primary coolant piping for an initial PWR plant in Japan by means of elastic plastic fracture mechanics. The evaluation results show that the crack will not grow into an unstable fracture and the integrity of the piping will be secured, even when such through wall crack length is assumed to equal the fatigue crack growth length for a service period of up to 60 years.

  1. PWR loss of feedwater ATWS: analysis and sensitivity study

    SciTech Connect

    Shier, W.G.; Lu, M.S.; Levine, M.M.; Diamond, D.J.

    1983-01-01

    The incident at the Salem Nuclear plant has presented a renewed interest in the analysis of the consequences of anticipated transients without scram (ATWS). This paper presents the results of an analysis of a complete loss of feedwater ATWS for a typical 4-loop PWR. The loss of feedwater transient was selected since previous analyses have shown that this transient produces one of the more limiting overpressure conditions in the primary system. These results provide a detailed analysis of this transient using current analytical techniques and show the sensitivity to several important parameters and plant modeling techniques. The RELAP5/MOD1 computer code has been used for this analysis. The code version is designated as Cycle 13 with additional modifications provided by both INEL and BNL.

  2. Comment submitted by InterMetro Industries Corp. regarding the Energy Star Verification Testing Program

    Energy.gov [DOE]

    This document is a comment submitted by InterMetro Industries Corp. regarding the Energy Star Verification Testing Program

  3. DOE's Lab-Corps at Idaho National Laboratory | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    DOE's Lab-Corps at Idaho National Laboratory DOE's Lab-Corps at Idaho National Laboratory Addthis 1 of 4 Idaho National Laboratory (INL) Director Mark Peters (right) talks with INL researcher Jaya Tumuluru, whose DOE Lab-Corps project is a high-moisture pelleting process for the raw biomass material that feeds biofuel refineries. Image: Idaho National Laboratory 2 of 4 Idaho National Laboratory (INL) Director Mark Peters (left) talks with INL research lead Tedd Lister, whose DOE Lab-Corps

  4. Corps of Engineers, SEPA, TVA, and TVPPA sign memorandum of agreement |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Corps of Engineers, SEPA, TVA, and TVPPA sign memorandum of agreement Corps of Engineers, SEPA, TVA, and TVPPA sign memorandum of agreement June 28, 2016 - 12:00pm Addthis Corps of Engineers, SEPA, TVA, and TVPPA sign memorandum of agreement The U.S. Army Corps of Engineers, Nashville District joined forces with the Southeastern Power Administration, the Tennessee Valley Authority, the Tennessee Valley Public Power Association, Inc., and their preference customers on

  5. U.S. Army Corps of Engineers Sites | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    U.S. Army Corps of Engineers Sites U.S. Army Corps of Engineers Sites U.S. Army Corps of Engineers Sites Transfer of Remediated FUSRAP Sites to DOE Office of Legacy Management In 1997, Congress directed the U.S. Army Corps of Engineers (USACE) to conduct assessment, remedial action, and site closure activities for Formerly Utilized Sites Remedial Action Program (FUSRAP) sites. The DOE Office of Legacy Management (LM) retains responsibility for determining eligibility for site cleanup under

  6. Design study of long-life PWR using thorium cycle (Journal Article...

    Office of Scientific and Technical Information (OSTI)

    life PWR core because it gives reactivity swing less than 1%Deltakk and longer ... long time operation with reduced excess reactivity as low as 0.53%Deltakk and reduced ...

  7. Conceptual design study of small long-life PWR based on thorium...

    Office of Scientific and Technical Information (OSTI)

    The optimization of 350 MWt small long life PWR result small excess reactivity and reduced ... on advances in nuclear science and engineering, Denpasar, Bali (Indonesia), 16-19 Sep ...

  8. PWR and BWR spent fuel assembly gamma spectra measurements

    DOE PAGES [OSTI]

    Vaccaro, S.; Tobin, Stephen J.; Favalli, Andrea; Grogan, Brandon R.; Jansson, Peter; Liljenfeldt, Henrik; Mozin, Vladimir; Hu, Jianwei; Schwalbach, P.; Sjoland, A.; et al

    2016-07-17

    A project to research the application of nondestructive assay (NDA) to spent fuel assemblies is underway. The research team comprises the European Atomic Energy Community (EURATOM), embodied by the European Commission, DG Energy, Directorate EURATOM Safeguards; the Swedish Nuclear Fuel and Waste Management Company (SKB); two universities; and several United States national laboratories. The Next Generation of Safeguards Initiative–Spent Fuel project team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detectmore » the diversion or replacement of pins, (3) estimate the plutonium mass, (4) estimate the decay heat, and (5) determine the reactivity of spent fuel assemblies. This study focuses on spectrally resolved gamma-ray measurements performed on a diverse set of 50 assemblies [25 pressurized water reactor (PWR) assemblies and 25 boiling water reactor (BWR) assemblies]; these same 50 assemblies will be measured with neutron-based NDA instruments and a full-length calorimeter. Given that encapsulation/repository and dry storage safeguards are the primarily intended applications, the analysis focused on the dominant gamma-ray lines of 137Cs, 154Eu, and 134Cs because these isotopes will be the primary gamma-ray emitters during the time frames of interest to these applications. This study addresses the impact on the measured passive gamma-ray signals due to the following factors: burnup, initial enrichment, cooling time, assembly type (eight different PWR and six different BWR fuel designs), presence of gadolinium rods, and anomalies in operating history. As a result, to compare the measured results with theory, a limited number of ORIGEN-ARP simulations were performed.« less

  9. Study of a Station Blackout Event in the PWR Plant

    SciTech Connect

    Ching-Hui Wu; Tsu-Jen Lin; Tsu-Mu Kao [Institute of Nuclear Energy Research P.O. Box 3-3, Longtan, 32500, Taiwan (China)

    2002-07-01

    On March 18, 2001, a PWR nuclear power plant located in the Southern Taiwan occurred a Station Blackout (SBO) event. Monsoon seawater mist caused the instability of offsite power grids. High salt-contained mist caused offsite power supply to the nuclear power plant very unstable, and forced the plant to be shutdown. Around 24 hours later, when both units in the plant were shutdown, several inadequate high cycles of bus transfer between 345 kV and 161 kV startup transformers degraded the emergency 4.16 kV switchgears. Then, in the Train-A switchgear room of Unit 1 occurred a fire explosion, when the degraded switchgear was hot shorted at the in-coming 345 kV breaker. Inadequate configuration arrangement of the offsite power supply to the emergency 4.16 kV switchgears led to loss of offsite power (LOOP) events to both units in the plant. Both emergency diesel generators (EDG) of Unit 1 could not be in service in time, but those of Unit 2 were running well. The SBO event of Unit 1 lasted for about two hours till the fifth EDG (DG-5) was lined-up to the Train-B switchgear. This study investigated the scenario of the SBO event and evaluated a risk profile for the SBO period. Guidelines in the SBO event, suggested by probabilistic risk assessment (PRA) procedures were also reviewed. Many related topics such as the re-configuration of offsite power supply, the addition of isolation breakers of the emergency 4.16 kV switchgears, the betterment of DG-5 lineup design, and enhancement of the reliability of offsite power supply to the PWR plant, etc., will be in further studies. (authors)

  10. Identification and evaluation of PWR in-vessel severe accident management strategies

    SciTech Connect

    Dukelow, J S [Pacific Northwest Lab., Richland, WA (United States); Harrison, D G [Jason Associates, Idaho Falls, ID (United States); Morgenstern, M [Battelle Human Affairs Research Center, Seattle, WA (United States)

    1992-03-01

    This reports documents work performed the NRC/RES Accident Management Guidance Program to evaluate possible strategies for mitigating the consequences of PWR severe accidents. The selection and evaluation of strategies was limited to the in-vessel phase of the severe accident, i.e., after the initiation of core degradation and prior to RPV failure. A parallel project at BNL has been considering strategies applicable to the ex-vessel phase of PWR severe accidents.

  11. Lab-Corps Program Trains Scientists in Commercialization

    Office of Energy Efficiency and Renewable Energy (EERE)

    This video features an introduction to the Office of Energy Efficiency and Renewable Energy’s (EERE’s) Lab Corps program - a specialized training curriculum aimed at accelerating the transfer of clean energy technologies from national laboratories into the commercial marketplace.

  12. The Department Of Energy Has Joined The Civilian Response Corps

    Energy.gov [DOE]

    Secretaries Clinton and Chu announce that the Department of Energy has joined the Civilian Response Corps, the U.S. Government’s expeditionary, interagency civilian force dedicated to conflict prevention, response, and peacebuilding. The Office of Electricity Delivery and Energy Reliability will lead this effort for DOE.

  13. The Entrepreneurial Mentor Corps at Work: Algaeventure Systems

    Energy.gov [DOE]

    Algaeventure Systems (AVS) is one of many innovative new companies participating in “Entrepreneurial Mentor Corps,” a one-year pilot program to connect clean energy startups with mentors who can help support these companies through early-stage challenges and increase their chance for success.

  14. Alternative Fuels Data Center: MedCorp Fuels Emergency Vehicles With

    Alternative Fuels and Advanced Vehicles Data Center

    Propane in Ohio MedCorp Fuels Emergency Vehicles With Propane in Ohio to someone by E-mail Share Alternative Fuels Data Center: MedCorp Fuels Emergency Vehicles With Propane in Ohio on Facebook Tweet about Alternative Fuels Data Center: MedCorp Fuels Emergency Vehicles With Propane in Ohio on Twitter Bookmark Alternative Fuels Data Center: MedCorp Fuels Emergency Vehicles With Propane in Ohio on Google Bookmark Alternative Fuels Data Center: MedCorp Fuels Emergency Vehicles With Propane in

  15. Lab-Corps: Training National Lab Entrepreneurs to Take Clean Energy to

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Market | Department of Energy Lab-Corps: Training National Lab Entrepreneurs to Take Clean Energy to Market Lab-Corps: Training National Lab Entrepreneurs to Take Clean Energy to Market March 18, 2016 - 8:54am Addthis Lab-Corps: Training National Lab Entrepreneurs to Take Clean Energy to Market Victor Kane Director, National Lab Impact Initiative Jennifer Ramsey Lab-Corps Program Manager Want to know more? Visit the Lab-Corps page on the EERE website. It's Day 1 of training. You have a busy

  16. Application to Export Electric Energy OE Docket No. EA-145-E Powerex Corp:

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Comment from Jean Public | Department of Energy Corp: Comment from Jean Public Application to Export Electric Energy OE Docket No. EA-145-E Powerex Corp: Comment from Jean Public Application from Powerex Corp to export electric energy to Mexico. Comment for EA-145-E Powerex Corp.pdf (141.49 KB) More Documents & Publications EA-145-E Powerex Corp. Application to Export Electric Energy OE Docket No. EA-145-E Powerex Corporation Application to Export Electric Energy OE Docket No. EA-145-D

  17. Video: Lab-Corps Third Cohort Graduates in Washington, D.C. | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Lab-Corps Third Cohort Graduates in Washington, D.C. Video: Lab-Corps Third Cohort Graduates in Washington, D.C. August 25, 2016 - 2:10pm Addthis Learn More About Lab-Corps Some of the nation's top researchers recently graduated from the Office of Energy Efficiency and Renewable Energy's Lab-Corps program designed to help scientists better understand the commercialization process. Addthis Related Articles Graduates Reflect on Energy Department's Lab-Corps Program National Lab

  18. Scoping Study Investigating PWR Instrumentation during a Severe Accident Scenario

    SciTech Connect

    Rempe, J. L.; Knudson, D. L.; Lutz, R. J.

    2015-09-01

    The accidents at the Three Mile Island Unit 2 (TMI-2) and Fukushima Daiichi Units 1, 2, and 3 nuclear power plants demonstrate the critical importance of accurate, relevant, and timely information on the status of reactor systems during a severe accident. These events also highlight the critical importance of understanding and focusing on the key elements of system status information in an environment where operators may be overwhelmed with superfluous and sometimes conflicting data. While progress in these areas has been made since TMI-2, the events at Fukushima suggests that there may still be a potential need to ensure that critical plant information is available to plant operators. Recognizing the significant technical and economic challenges associated with plant modifications, it is important to focus on instrumentation that can address these information critical needs. As part of a program initiated by the Department of Energy, Office of Nuclear Energy (DOE-NE), a scoping effort was initiated to assess critical information needs identified for severe accident management and mitigation in commercial Light Water Reactors (LWRs), to quantify the environment instruments monitoring this data would have to survive, and to identify gaps where predicted environments exceed instrumentation qualification envelop (QE) limits. Results from the Pressurized Water Reactor (PWR) scoping evaluations are documented in this report. The PWR evaluations were limited in this scoping evaluation to quantifying the environmental conditions for an unmitigated Short-Term Station BlackOut (STSBO) sequence in one unit at the Surry nuclear power station. Results were obtained using the MELCOR models developed for the US Nuclear Regulatory Commission (NRC)-sponsored State of the Art Consequence Assessment (SOARCA) program project. Results from this scoping evaluation indicate that some instrumentation identified to provide critical information would be exposed to conditions that

  19. Wisconsin Public Service Corp's Weston 4 earns Power's highest honor

    SciTech Connect

    Peltier, R.

    2008-08-15

    Wisconsin Public Service Corp. placed its world-class Weston 4 into commercial service on June 30 and is now enjoying the benefits of coal-fired supercritical technology's inherently higher efficiency, operating flexibility and lower CO{sub 2} emissions. For its unequalled environmental protection credentials, well-integrated project team, and employing the most advanced coal-fired steam generation technology in the US today, Weston 4 is awarded Power magazine's 2008 Plant of the Year Award. 10 figs., 4 tabs.

  20. Notices Marine Corps Base Camp Smith HI Landholding Agency: Navy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    503 Federal Register / Vol. 81, No. 156 / Friday, August 12, 2016 / Notices Marine Corps Base Camp Smith HI Landholding Agency: Navy Property Number: 77201630011 Status: Excess Comments: Public access denied and no alternative method to gain access without compromising national security. Reasons: Secured Area Iowa L80004, RTHBUN-29396 Shower Building in South Fork area Rathbun Project; 13736 Shrike Pl. Mystic IA 52574 Landholding Agency: COE Property Number: 31201630003 Status: Excess Comments:

  1. Notices SUMMARY: The U.S. Army Corps of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    602 Federal Register / Vol. 81, No. 62 / Thursday, March 31, 2016 / Notices SUMMARY: The U.S. Army Corps of Engineers (USACE) intends to prepare a Draft Integrated Feasibility Report and Environmental Impact Statement (DIFR- EIS) for the Coastal Texas Protection and Restoration Feasibility Study. This study will identify and evaluate the feasibility of developing a comprehensive plan for flood risk management, hurricane and storm risk management, and ecosystem restoration for the coastal areas

  2. Analysis of Potential Hydrogen Risk in the PWR Containment

    SciTech Connect

    Deng Jian; Xuewu Cao [Shanghai Jiaotong University, Shanghai (China)

    2006-07-01

    Various studies have shown that hydrogen combustion is one of major risk contributors to threaten the integrity of the containment in a nuclear power plant. That hydrogen risk should be considered in severe accident strategies in current and future NPPs has been emphasized in the latest policies issued by the National Nuclear Safety Administration of China (NNSA). According to a deterministic approach, three typical severe accident sequences for a PWR large dry containment, such as the large break loss-of-coolant (LLOCA), the station blackout (SBO), and the small break loss-of-coolant (SLOCA) are analyzed in this paper with MELCOR code. Hydrogen concentrations in different compartments are observed to evaluate the potential hydrogen risk. The results show that there is a great amount of hydrogen released into the containment, which causes the containment pressure to increase and some potential in-consecutive burning. Therefore, certain hydrogen management strategies should be considered to reduce the risk to threaten the containment integrity. (authors)

  3. Assessment of PWR waterside corrosion models and data. Final report

    SciTech Connect

    Cox, B.

    1985-10-01

    The published data on waterside corrosion of PWR fuel cladding and unfuelled components have been reviewed, and the models used to assess the data have been studied. All corrosion models use too simplified a view of the corrosion process to obtain other than a general trend for the actual oxidation data. The in-reactor post-transition oxidation of the Zircaloys appears to be heavily dependent on water chemistry variations both between reactors, and along the length of an individual fuel rod. Crud deposition may be one primary cause of this, perhaps by allowing the independent development of the water chemistry within the crud layer, as much as by its effect on cladding surface temperatures. However, the effect of the thickening of the oxide film, which permits the development of an independent water chemistry inside the oxide, leading to an accelerating oxidation rate at large oxide thicknesses, seems to be the most important factor. It is concluded that a spectrum of results ranging from essentially no in-reactor enhancement of the oxidation rate to a sizeable enhancement (>10) may be seen depending upon the thickness of the oxide films, the water chemistry of the reactor, and crud deposition. A post-irradiation test that may help to distinguish between the factors involved has been suggested. 105 refs., 38 figs.

  4. Corrosion fatigue characterization of reactor pressure vessel steels. [PWR; BWR

    SciTech Connect

    Van Der Sluys, W.A.

    1982-12-01

    During routine operation, light water reactor (LWR) pressure vessels are subjected to a variety of transients that result in time-varying stresses. Consequently, fatigue and environmentally-assisted fatigue are mechanisms of growth relevant to flaws in these pressure vessels. To provide a better understanding of the resistance of nuclear pressure vessel steels to these flaw growth processes, fracture mechanics data were generated on the rates of fatigue crack growth for SA508-2 and SA533B-1 steels in both room temperature air and 288/sup 0/C water. Areas investigated were: the relationship of crack growth rate to prior loading history; the effects of loading frequency and R ratio (K/sub min//K/sub max/) on crack growth rate as a function of the stress intensity factor range (..delta..K); transient aspects of the fatigue crack growth behavior; the effect of material chemistry (sulphur content) on fatigue crack; and growth rate; water chemistry effects (high-purity water versus simulated pressurized water reactotr (PWR) primary coolant).

  5. Coupled Neutronics Thermal-Hydraulic Solution of a Full-Core PWR Using VERA-CS

    SciTech Connect

    Clarno, Kevin T; Palmtag, Scott; Davidson, Gregory G; Salko, Robert K; Evans, Thomas M; Turner, John A; Belcourt, Kenneth; Hooper, Russell; Schmidt, Rodney

    2014-01-01

    The Consortium for Advanced Simulation of Light Water Reactors (CASL) is developing a core simulator called VERA-CS to model operating PWR reactors with high resolution. This paper describes how the development of VERA-CS is being driven by a set of progression benchmark problems that specify the delivery of useful capability in discrete steps. As part of this development, this paper will describe the current capability of VERA-CS to perform a multiphysics simulation of an operating PWR at Hot Full Power (HFP) conditions using a set of existing computer codes coupled together in a novel method. Results for several single-assembly cases are shown that demonstrate coupling for different boron concentrations and power levels. Finally, high-resolution results are shown for a full-core PWR reactor modeled in quarter-symmetry.

  6. Study on Equilibrium Characteristics of Thorium-Plutonium-Minor Actinides Mixed Oxides Fuel in PWR

    SciTech Connect

    Waris, A.; Permana, S.; Kurniadi, R.; Su'ud, Z.; Sekimoto, H.

    2010-06-22

    A study on characteristics of thorium-plutonium-minor actinides utilization in the pressurized water reactor (PWR) with the equilibrium burnup model has been conducted. For a comprehensive evaluation, several fuel cycles scenario have been included in the present study with the variation of moderator-to-fuel volume ratio (MFR) of PWR core design. The results obviously exhibit that the neutron spectra grow to be harder with decreasing of the MFR. Moreover, the neutron spectra also turn into harder with the rising number of confined heavy nuclides. The required {sup 233}U concentration for criticality of reactor augments with the increasing of MFR for all heavy nuclides confinement and thorium and uranium confinement in PWR.

  7. Assessment of PWR Steam Generator modelling in RELAP5/MOD2. International Agreement Report

    SciTech Connect

    Putney, J.M.; Preece, R.J.

    1993-06-01

    An assessment of Steam Generator (SG) modelling in the PWR thermal-hydraulic code RELAP5/MOD2 is presented. The assessment is based on a review of code assessment calculations performed in the UK and elsewhere, detailed calculations against a series of commissioning tests carried out on the Wolf Creek PWR and analytical investigations of the phenomena involved in normal and abnormal SG operation. A number of modelling deficiencies are identified and their implications for PWR safety analysis are discussed -- including methods for compensating for the deficiencies through changes to the input deck. Consideration is also given as to whether the deficiencies will still be present in the successor code RELAP5/MOD3.

  8. Microsoft Word - Corp Impl 10-05-06.final.doc | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Corp Impl 10-05-06.final.doc Microsoft Word - Corp Impl 10-05-06.final.doc Microsoft Word - Corp Impl 10-05-06.final.doc (422.79 KB) More Documents & Publications ESTABLISHMENT OF MANAGEMENT DECISIONS ON OFFICE OF INSPECTOR GENERAL REPORTS, DOE O 221.3 Microsoft Word - AL2007-01.doc DOE Systems Engineering Methodology (SEM): Stage Exit V

  9. Lab-Corps Program Pitch Competition - April 17, 2015 | Argonne National

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Department of Energy Lab-Corps Initiative Moves High-Impact Innovations into the Marketplace Lab-Corps Initiative Moves High-Impact Innovations into the Marketplace October 23, 2015 - 11:40am Addthis Clean energy technologies like the solar energy innovations underway at Lawrence Berkeley National Lab are transitioning into the marketplace more rapidly because of a new initiative called Lab-Corps. Clean energy technologies like the solar energy innovations underway at Lawrence Berkeley

  10. In-core and ex-core calculations of the VENUS simulated PWR benchmark experiment

    SciTech Connect

    Williams, M.L.; Chowdhury, P.; Landesman, M.; Kam, F.B.K.

    1985-01-01

    The VENUS PWR engineering mockup experiment was established to simulate a beginning-of-life, generic PWR configuration at the zero-power VENUS critical facility located at CEN/SCK, Mol, Belgium. The experimental measurement program consists of (1) gamma scans to determine the core power distribution, (2) in-core and ex-core foil activations, (3) neutron spectrometer measurements, and (4) gamma heating measurements with TLD's. Analysis of the VENUS benchmark has been performed with two-dimensional discrete ordinates transport theory, using the DOT-IV code.

  11. Effects of Lower Drying-Storage Temperatures on the DBTT of High Burnup PWR

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Cladding | Department of Energy Effects of Lower Drying-Storage Temperatures on the DBTT of High Burnup PWR Cladding Effects of Lower Drying-Storage Temperatures on the DBTT of High Burnup PWR Cladding The purpose of the research effort is to determine the effects of canister and/or cask drying and storage on radial hydride precipitation in, and potential embrittlement of, high-burnup (HBU) pressurized water reactor cladding alloys during cooling for a range of storage temperatures and hoop

  12. NREL Engineers Accomplish Training for Participation in Pilot Lab-Corps

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Program | Wind | NREL Engineers Accomplish Training for Participation in Pilot Lab-Corps Program January 19, 2016 Katherine Dykes and Rick Damiani completed six weeks of training as part of the U.S. Department of Energy's pilot Lab-Corps program. Lab-Corps seeks to "help move innovative technologies from national labs into the marketplace." Dykes and Damiani competed against other teams to represent the National Renewable Energy Laboratory (NREL) in the Lab-Corps program as

  13. Lab-Corps Pilot Accelerates Private-Sector Adoption of Game-Changing...

    Energy.gov [DOE] (indexed site)

    Teams were initially introduced to private sector and consumer interests - like ... Lab-Corps Pilot Accelerates Private-Sector Adoption of Game-Changing ...

  14. EERE Success Story-FEMP and U.S. Army Corps of Engineers Partner...

    Energy.gov [DOE] (indexed site)

    Federal Energy Management Program (FEMP) developed a Memorandum of Understanding ... Related Articles U.S. Army Corps of Engineers and FEMP Partner to Drive Down Federal ...

  15. U.S. Marine Corps Base Camp Pendleton: Using The Sun For Hot Water And Electricity

    SciTech Connect

    2009-09-23

    Case study overview of integrated solar hot water/photovoltaic systems at the U.S. Marine Corps Camp Pendleton training pools.

  16. U.S. Army Corps of Engineers Delivers Cost and Schedule Validation for

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Hanford Waste Treatment Plant | Department of Energy Army Corps of Engineers Delivers Cost and Schedule Validation for Hanford Waste Treatment Plant U.S. Army Corps of Engineers Delivers Cost and Schedule Validation for Hanford Waste Treatment Plant September 7, 2006 - 8:53am Addthis Corps Report Validates Cost of $12.2 billion and Construction Completion in November 2019 WASHINGTON, DC - The U.S. Department of Energy (DOE) today released the U.S. Army Corps of Engineers (USACE) report

  17. U.S. Marine Corps Stand at Forefront of Energy and Water Savings |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Marine Corps Stand at Forefront of Energy and Water Savings U.S. Marine Corps Stand at Forefront of Energy and Water Savings This fact sheet is an overview of the U.S. Marine Corps Beaufort Air Station's energy and water savings accomplishments. Download the U.S. Marine Corps Beaufort Air Station's energy and water savings accomplishments fact sheet. (307.94 KB) More Documents & Publications Trane U.S. Inc. ESCO Qualification Sheet Energy Savings Performance Contract

  18. U.S. Marine Corps Stand at Forefront of Energy and Water Savings (Fact Sheet)

    SciTech Connect

    Not Available

    2012-12-01

    This fact sheet is an overview of the U.S. Marine Corps Beaufort Air Station's energy and water savings accomplishments.

  19. " Best Practices Scorecard (c) GA Tech Research Corp.

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Best Practices Scorecard (c) GA Tech Research Corp. (c) Texas Industries of the Future" "Instructions for Using the Best Practice Scorecard Calculator" "This calculator was developed for use with the Superior Energy Performance's Best Practice Scorecard, revision 9, dated December 5, 2012." "How to use this calculator:" "1. On the Summary tab, press the hide or unhide buttons to show desired detail." "2. Click on the category links in the

  20. Radionuclide release from PWR spent fuel specimens with induced cladding defects

    SciTech Connect

    Wilson, C.N.; Oversby, V.M.

    1984-03-01

    Radionuclide releases from pressurized water reactor (PWR) spent fuel rod specimens containing various artificially induced cladding defects were compared by leach testing. The study was conducted in support of the Nevada Nuclear Waste Storage Investigations (NNWSI) Waste Package Task to evaluate the effectiveness of failed cladding as a barrier to radionuclide release. Test description and results are presented. 6 references, 4 figures.

  1. Radionuclide release from PWR spent fuel specimens with induced cladding defects

    SciTech Connect

    Wilson, C.N.; Oversby, V.M.

    1984-03-01

    Radionuclide releases from pressurized water reactor (PWR) spent fuel rod specimens containing various artificially induced cladding defects were compared by leach testing. The study was conducted in support of the Nevada Nuclear Waste Storage Investigations (NNWSI) Waste Package Task to evaluate the effectiveness of failed cladding as a barrier to radionuclide release. Test description and results are presented.

  2. Performance evaluation of two-stage fuel cycle from SFR to PWR

    SciTech Connect

    Fei, T.; Hoffman, E.A.; Kim, T.K.; Taiwo, T.A.

    2013-07-01

    One potential fuel cycle option being considered is a two-stage fuel cycle system involving the continuous recycle of transuranics in a fast reactor and the use of bred plutonium in a thermal reactor. The first stage is a Sodium-cooled Fast Reactor (SFR) fuel cycle with metallic U-TRU-Zr fuel. The SFRs need to have a breeding ratio greater than 1.0 in order to produce fissile material for use in the second stage. The second stage is a PWR fuel cycle with uranium and plutonium mixed oxide fuel based on the design and performance of the current state-of-the-art commercial PWRs with an average discharge burnup of 50 MWd/kgHM. This paper evaluates the possibility of this fuel cycle option and discusses its fuel cycle performance characteristics. The study focuses on an equilibrium stage of the fuel cycle. Results indicate that, in order to avoid a positive coolant void reactivity feedback in the stage-2 PWR, the reactor requires high quality of plutonium from the first stage and minor actinides in the discharge fuel of the PWR needs to be separated and sent back to the stage-1 SFR. The electricity-sharing ratio between the 2 stages is 87.0% (SFR) to 13.0% (PWR) for a TRU inventory ratio (the mass of TRU in the discharge fuel divided by the mass of TRU in the fresh fuel) of 1.06. A sensitivity study indicated that by increasing the TRU inventory ratio to 1.13, The electricity generation fraction of stage-2 PWR is increased to 28.9%. The two-stage fuel cycle system considered in this study was found to provide a high uranium utilization (>80%). (authors)

  3. Proceedings: 1983 Workshop on Secondary-Side Stress Corrosion Cracking and Intergranular Corrosion of PWR Steam Generator Tubing

    SciTech Connect

    1986-03-01

    Participants in this international workshop discussed research investigating mechanisms and propagation rates of intergranular corrosion in PWR steam generators. Laboratory test results, which have been consistent with power plant experience, permitted preliminary definition of corrosion rates in alloy 600 tubing.

  4. DOSE RATES FOR WESTINGHOUSE 17X17 MOX PWR SNF IN A WASTE PACKAGE (SCPB: N/A)

    SciTech Connect

    T.L. Lotz

    1997-01-29

    This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to estimate the dose rate on and near the surface a Multi-Purpose Canister (MPC) PWR waste package (WP) which is loaded with Westinghouse 17 x 17 mixed oxide (MOX) PWR fuel. The 21 PWR MPC WP is used to provide an upper bound for waste package designs since the 12 PWR MPC WP will have a smaller source term and an equivalent amount of shielding. the objectives of this evaluation are to calculate the requested dose rate(s) and document the calculation in a fashion to allow comparisons to other waste forms and WP designs at a future time.

  5. Lab-Corps Program Announces Second Round of Training for Entrepreneurial

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Teams at National Labs | Department of Energy Lab-Corps Program Announces Second Round of Training for Entrepreneurial Teams at National Labs Lab-Corps Program Announces Second Round of Training for Entrepreneurial Teams at National Labs March 17, 2016 - 4:00pm Addthis The Office of Energy Efficiency and Renewable Energy's Lab-Corps program today launched its second round of clean energy entrepreneurship trainings this week in Golden, Colorado. The $2.3 million pilot, started in 2014, is

  6. Application for Presidential Permit OE Docket No. EA-171-D Powerex Corp:

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Federal Register Notice, Volume 80, No. 126 - July 1, 2015 | Department of Energy EA-171-D Powerex Corp: Federal Register Notice, Volume 80, No. 126 - July 1, 2015 Application for Presidential Permit OE Docket No. EA-171-D Powerex Corp: Federal Register Notice, Volume 80, No. 126 - July 1, 2015 Application from Powerex Corp. to export electric energy to Canada. Federal Register Notice. EA-171-D Powerex (CN).pdf (123.17 KB) More Documents & Publications Application to Export Electric

  7. EERE Success Story-FEMP and U.S. Army Corps of Engineers Partner to Drive

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Down Federal Energy Costs | Department of Energy and U.S. Army Corps of Engineers Partner to Drive Down Federal Energy Costs EERE Success Story-FEMP and U.S. Army Corps of Engineers Partner to Drive Down Federal Energy Costs March 26, 2015 - 2:12pm Addthis With hundreds of thousands of facilities and vehicles spread across the globe, the United States government is one of the world's largest consumers of energy. The U.S. Army Corps of Engineers (USACE) and the U.S. Department of Energy's

  8. Eight Questions with the Idaho National Lab Director on the DOE Lab-Corps

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Program | Department of Energy Eight Questions with the Idaho National Lab Director on the DOE Lab-Corps Program Eight Questions with the Idaho National Lab Director on the DOE Lab-Corps Program November 1, 2016 - 11:13am Addthis Idaho National Laboratory (INL) Director Mark Peters (right) talks with INL researcher Jaya Tumuluru, whose DOE Lab-Corps project is a high moisture pelleting process for the raw biomass material that feeds biofuel refineries. Image: Idaho National Laboratory. Idaho

  9. 8 Questions with Idaho National Lab Director on the DOE Lab-Corps Program |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy 8 Questions with Idaho National Lab Director on the DOE Lab-Corps Program 8 Questions with Idaho National Lab Director on the DOE Lab-Corps Program October 28, 2016 - 10:15am Addthis 1 of 4 Idaho National Laboratory (INL) Director Mark Peters (right) talks with INL researcher Jaya Tumuluru, whose DOE Lab-Corps project is a high-moisture pelleting process for the raw biomass material that feeds biofuel refineries. Image: Idaho National Laboratory 2 of 4 Idaho National

  10. U.S. Army Corps of Engineers and FEMP Partner to Drive Down Federal Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Costs | Department of Energy Army Corps of Engineers and FEMP Partner to Drive Down Federal Energy Costs U.S. Army Corps of Engineers and FEMP Partner to Drive Down Federal Energy Costs March 4, 2015 - 4:47pm Addthis The U.S. Army Corps of Engineers (USACE) and the U.S. Department of Energy's Federal Energy Management Program (FEMP) developed a partnership to help drive down the federal government's energy costs through the government-wide adoption of performance contracting processes.

  11. Conceptual design study of small long-life PWR based on thorium cycle fuel

    SciTech Connect

    Subkhi, M. Nurul; Su'ud, Zaki; Waris, Abdul; Permana, Sidik

    2014-09-30

    A neutronic performance of small long-life Pressurized Water Reactor (PWR) using thorium cycle based fuel has been investigated. Thorium cycle which has higher conversion ratio in thermal region compared to uranium cycle produce some significant of {sup 233}U during burn up time. The cell-burn up calculations were performed by PIJ SRAC code using nuclear data library based on JENDL 3.3, while the multi-energy-group diffusion calculations were optimized in whole core cylindrical two-dimension R-Z geometry by SRAC-CITATION. this study would be introduced thorium nitride fuel system which ZIRLO is the cladding material. The optimization of 350 MWt small long life PWR result small excess reactivity and reduced power peaking during its operation.

  12. Optimization of small long-life PWR based on thorium fuel

    SciTech Connect

    Subkhi, Moh Nurul; Suud, Zaki Waris, Abdul; Permana, Sidik

    2015-09-30

    A conceptual design of small long-life Pressurized Water Reactor (PWR) using thorium fuel has been investigated in neutronic aspect. The cell-burn up calculations were performed by PIJ SRAC code using nuclear data library based on JENDL 3.2, while the multi-energy-group diffusion calculations were optimized in three-dimension X-Y-Z geometry of core by COREBN. The excess reactivity of thorium nitride with ZIRLO cladding is considered during 5 years of burnup without refueling. Optimization of 350 MWe long life PWR based on 5% {sup 233}U & 2.8% {sup 231}Pa, 6% {sup 233}U & 2.8% {sup 231}Pa and 7% {sup 233}U & 6% {sup 231}Pa give low excess reactivity.

  13. Preliminary assessment of PWR Steam Generator modelling in RELAP5/MOD3. International Agreeement Report

    SciTech Connect

    Preece, R.J.; Putney, J.M.

    1993-07-01

    A preliminary assessment of Steam Generator (SG) modelling in the PWR thermal-hydraulic code RELAP5/MOD3 is presented. The study is based on calculations against a series of steady-state commissioning tests carried out on the Wolf Creek PWR over a range of load conditions. Data from the tests are used to assess the modelling of primary to secondary side heat transfer and, in particular, to examine the effect of reverting to the standard form of the Chen heat transfer correlation in place of the modified form applied in RELAP5/MOD2. Comparisons between the two versions of the code are also used to show how the new interphase drag model in RELAP5/MOD3 affects the calculation of SG liquid inventory and the void fraction profile in the riser.

  14. MELCOR model for an experimental 17x17 spent fuel PWR assembly.

    SciTech Connect

    Cardoni, Jeffrey

    2010-11-01

    A MELCOR model has been developed to simulate a pressurized water reactor (PWR) 17 x 17 assembly in a spent fuel pool rack cell undergoing severe accident conditions. To the extent possible, the MELCOR model reflects the actual geometry, materials, and masses present in the experimental arrangement for the Sandia Fuel Project (SFP). The report presents an overview of the SFP experimental arrangement, the MELCOR model specifications, demonstration calculation results, and the input model listing.

  15. Application to Export Electric Energy OE Docket No. EA-296-B Rainbow Energy Marketing Corp: Federal Register Notice, Volume 77, No. 66- April 4, 2012

    Energy.gov [DOE]

    Application from Rainbow Energy Marketing Corp to export electric energy to Canada. Federal Register Notice.

  16. PCI-related cladding failures during off-normal events - draft. [PWR; BWR

    SciTech Connect

    Van Houten, R.; Tokar, M.; MacDonald, P.E.

    1984-05-01

    Pellet-cladding interaction (PCI) has long been identified as a fuel rod failure mechanism during power increases in both pressurized and boiling water reactors, and commercial guidelines have practically eliminated such failures during standard operations. A question remains regarding the possible formation of through-wall cladding cracks during several types of postulated off-normal reactor events involving power increases. This report includes preliminary findings for reactor events of the type addressed by Chapter 15 of the NRC Standard Review Plan. Specifically, the BWR turbine trip without bypass, PWR control rod withdrawal error, subcritical PWR control rod withdrawal error, BWR control blade withdrawal error, and the PWR steamline break are analyzed on the joint bases of peak rod power, power increase, ramp rate, and duration at elevated power. These Chapter 15 events are compared to numerous test reactor results and to other relevant investigations, and tentative conclusions on transient severity and data base adequacy are presented. Progress in developing computer codes for predicting PCI-induced fuel rod failures is also discussed. 49 references.

  17. 34730,"AGWAY PETRO CORP",1,231,"PROPANE/NGL",0712,"CHAMPL-RS...

    Energy Information Administration (EIA) (indexed site)

    CORP",7,850,"UNFINISHED OILS, RESIDUUM",1903,"PASCAGOULA, MS","MISSISSIPPI",3,830,"SPAIN",219,0,0,"CHEVRON USA INC","PASCAGOULA","MS","MISSISSIPPI",3 34730,"CHEVRON...

  18. Air Flow North America Corp.- FE Dkt. No. 14-206-LNG

    Energy.gov [DOE]

    The Office of Fossil Energy gives notice of receipt of an Application filed December 16, 2014, by Air Flow North America Corp. (Air Flow), seeking a long-term multi-contract authorization to export...

  19. Alaska ADEC Process for Issuing a 401 Waiver of Corps 404 Permits...

    OpenEI (Open Energy Information) [EERE & EIA]

    Environmental Conservation. ADEC Process for Issuing a 401 Waiver of Corps 404 Permits. 4p. GuideHandbook sent to Retrieved from "http:en.openei.orgwindex.php?titleAlaskaAD...

  20. Air Flow North America Corp. – FE Dkt. No. 14-53-LNG (Re-export)

    Energy.gov [DOE]

    The Office of Fossil Energy (FE) of the Department of Energy (DOE) gives notice of receipt of an application filed on March 25, 2014, by Air Flow North America Corp. (AIR FLOW) requesting short...

  1. U.S. Army Corps of Engineers Delivers Cost and Schedule Validation...

    Energy Saver

    for Hanford Waste Treatment Plant U.S. Army Corps of Engineers Delivers Cost and Schedule Validation for Hanford Waste Treatment Plant September 7, 2006 - 8:53am Addthis ...

  2. Oregon Senator Jeff Merkley to Visit Surprise Valley Electrification Corp. Project Site

    Energy.gov [DOE]

    Senator Jeff Merkley of Oregon will be stopping by our ARRA Low-Temperature project, Surprise Valley Electrification Corp., this Sunday, August 28, 2011, for a brief site visit.

  3. SonnenEnergy Corp SonnenEnergie GmbH | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    to: navigation, search Name: SonnenEnergy Corp (SonnenEnergie GmbH) Place: Polling, Germany Zip: D-82398 Product: PV systems integrator and installer, serving residential and...

  4. Energy Corps Takes Root in Montana, Seeks to Make America Greener...

    Energy.gov [DOE] (indexed site)

    vowing to "get things done for America-to make our people safer, smarter and healthier." ... agency that oversees AmeriCorps, has 12 people scattered throughout the state, serving ...

  5. FEMP and U.S. Army Corps of Engineers Partner to Drive Down Federal Energy Costs

    Energy.gov [DOE]

    With hundreds of thousands of facilities and vehicles spread across the globe, the United States government is one of the worlds largest consumers of energy. The U.S. Army Corps of Engineers ...

  6. 2013 Federal Energy and Water Management Award Winner Marine Corps Recruit

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    San Diego | Department of Energy Marine Corps Recruit San Diego 2013 Federal Energy and Water Management Award Winner Marine Corps Recruit San Diego fewm13_usmc_mcdepotsandiego_highres.pdf (3.9 MB) fewm13_usmc_mcdepotsandiego.pdf (1.48 MB) More Documents & Publications Save Energy Now Assessment Helps Expand Energy Management Program at Shaw Industries 2013 Federal Energy and Water Management Award Winners Chris Manis, Randy Monohan, Laura Nelson, Mark Rodriguez, and Mick Wasco

  7. DOE Cites Safety and Ecology Corp. for Violating Nuclear Safety Rules |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Safety and Ecology Corp. for Violating Nuclear Safety Rules DOE Cites Safety and Ecology Corp. for Violating Nuclear Safety Rules June 14, 2005 - 4:53pm Addthis WASHINGTON, D.C. -- The Department of Energy (DOE) today notified Safety and Ecology Corporation, the contractor responsible for radiological safety at the Portsmouth Gaseous Diffusion Project in Portsmouth, Ohio, that it will fine the company $55,000 for violating the department's regulations prohibiting

  8. Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii:

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Assessment and Recommendations | Department of Energy Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment and Recommendations Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment and Recommendations NREL performed a comprehensive assessment to appraise the potential of MCBH Kaneohe Bay to achieve net zero energy status through energy efficiency, renewable energy, and electric vehicle integration. This report summarizes the results of the

  9. TEE-0062 - In the Matter of United CoolAir Corp. | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    62 - In the Matter of United CoolAir Corp. TEE-0062 - In the Matter of United CoolAir Corp. This Decision and Order considers an Application for Exception filed by United CoolAir Corporation (United CoolAir) seeking exception relief from the provisions of 10 C.F.R. Part 431, Subpart F, Energy Conservation Program for Certain Commercial and Industrial Equipment: Commercial Air Conditioners and Heat Pumps Energy Conservation Standards (Commercial Air Conditioner Standards).1 In its Application,

  10. Diesel fuel to dc power: Navy & Marine Corps Applications

    SciTech Connect

    Bloomfield, D.P.

    1996-12-31

    During the past year Analytic Power has tested fuel cell stacks and diesel fuel processors for US Navy and Marine Corps applications. The units are 10 kW demonstration power plants. The USN power plant was built to demonstrate the feasibility of diesel fueled PEM fuel cell power plants for 250 kW and 2.5 MW shipboard power systems. We designed and tested a ten cell, 1 kW USMC substack and fuel processor. The complete 10 kW prototype power plant, which has application to both power and hydrogen generation, is now under construction. The USN and USMC fuel cell stacks have been tested on both actual and simulated reformate. Analytic Power has accumulated operating experience with autothermal reforming based fuel processors operating on sulfur bearing diesel fuel, jet fuel, propane and natural gas. We have also completed the design and fabrication of an advanced regenerative ATR for the USMC. One of the significant problems with small fuel processors is heat loss which limits its ability to operate with the high steam to carbon ratios required for coke free high efficiency operation. The new USMC unit specifically addresses these heat transfer issues. The advances in the mill programs have been incorporated into Analytic Power`s commercial units which are now under test.

  11. A Study on the Conceptual Design of a 1,500 MWe Passive PWR with Annular Fuel

    SciTech Connect

    Kwi Lim Lee; Soon Heung Chang

    2004-07-01

    In this study, the preliminary conceptual design of a 1500 MWe pressurized water reactor (PWR) with annular fuel has been performed. This design is derived from the AP1000 which is a 1000 MWe PWR with two-loop. However, the present design is a 1500 MWe PWR with three-loop, passive safety features and extensive plant simplifications to enhance the construction, operation, and maintenance. The preliminary design parameters of this reactor have been determined through simple relation to those of AP1000 for reactor, reactor coolant system, and passive safety injection system. Using the MATRA code, we analyze the core designs for two alternatives on fuel assembly types: solid fuel and annular fuel. The performance of reactor cooling systems is evaluated through the accident of the cold leg break in the core makeup tank loop by using MARS2.1 code. This study presents the developmental strategy, preliminary design parameters and safety analysis results. (authors)

  12. Analysis of a double-ended cold-leg break simulation: THTF Test 3. 05. 5B. [PWR

    SciTech Connect

    Craddick, W.G.; Pevey, R.E.

    1982-09-01

    On July 3, 1980, an experiment was performed in the Oak Ridge National Laboratory Thermal-Hydraulic Test Facility that simulated a double-ended cold-leg break pressurized-water reactor (PWR) accident. Analysis of the experiment revealed that nuclear fuel rods exposed to the same hydrodynamic environment as that which existed in the experiment would have departed from nucleate boiling both earlier and later than the fuel rod simulator (FRS), depending on the size of the gap between the nuclear fuel pellets and cladding and on the initial power of the nuclear fuel rod. Comparison of the results of the current experiment, which used an FRS bundle with geometry similar to 17 x 17 PWR fuel assemblies, to the results of earlier experiments, which used an FRS bundle with geometry similar to 15 x 15 PWR fuel assemblies, revealed no differences that can be attributed to the difference in geometries.

  13. Thermal Response of the 21-PWR Waste Package to a Fire Accident

    SciTech Connect

    F.P. Faucher; H. Marr; M.J. Anderson

    2000-10-03

    The objective of this calculation is to evaluate the thermal response of the 21-PWR WP (pressurized water reactor waste package) to the regulatory fire event. The scope of this calculation is limited to the two-dimensional waste package temperature calculations to support the waste package design. The information provided by the sketches attached to this calculation (Attachment IV) is that of the potential design of the type of waste package considered in this calculation. The procedure AP-3.12Q.Calculations (Reference 1), and the Development Plan (Reference 24) are used to develop this calculation.

  14. Neutronics and safety characteristics of a 100% MOX fueled PWR using weapons grade plutonium

    SciTech Connect

    Biswas, D.; Rathbun, R.; Lee, Si Young; Rosenthal, P.

    1993-12-31

    Preliminary neutronics and safety studies, pertaining to the feasibility of using 100% weapons grade mixed-oxide (MOX) fuel in an advanced PWR Westinghouse design are presented in this paper. The preliminary results include information on boron concentration, power distribution, reactivity coefficients and xenon and control rode worth for the initial and the equilibrium cycle. Important safety issues related to rod ejection and steam line break accidents and shutdown margin requirements are also discussed. No significant change from the commercial design is needed to denature weapons-grade plutonium under the current safety and licensing criteria.

  15. SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions

    SciTech Connect

    Radulescu, Georgeta; Gauld, Ian C; Ilas, Germina

    2010-03-01

    The purpose of this calculation report is to document the comparison to measurement of the isotopic concentrations for pressurized water reactor (PWR) spent nuclear fuel determined with the Standardized Computer Analysis for Licensing Evaluation (SCALE) 5.1 (Ref. ) epletion calculation method. Specifically, the depletion computer code and the cross-section library being evaluated are the twodimensional (2-D) transport and depletion module, TRITON/NEWT,2, 3 and the 44GROUPNDF5 (Ref. 4) cross-section library, respectively, in the SCALE .1 code system.

  16. The unsteady 2-D numerical analysis for thermal stratification in surge line of PWR

    SciTech Connect

    Youm, H.K.; Park, M.H.; Jin, T.E.

    1995-12-01

    In this paper, the unsteady 2-dimensional model for thermal stratification in a pressurizer surge line of PWR plant is proposed to numerically investigate, the heat transfer and flow characteristics. The dimensionless governing equations are solved by using the SIMPLE (Semi-Implicit Method for Pressure Linked Equations) algorithm. The results are compared with simulated experimental results of TEMR Test. The time-dependent temperature profiles in the fluid and pipe wall are, shown with the thermal stratification occurring in the horizontal section of the pipe. The corresponding thermal stresses are, also presented.

  17. Steam-generator chemical-cleaning Demonstration Test No. 3 in a pot boiler. [PWR

    SciTech Connect

    Fink, G.C.; Helyer, M.H.; Key, G.L.

    1983-04-01

    Steam generators in pressurized water reactor (PWR) plants have experienced tubing degradation and support structure damage by a variety of corrosion mechanisms related to the accumulation of secondary side corrosion products. The Steam Generator Owners Group (SGOG) and the Electric Power Research Institute (EPRI) have sponsored a program to develop a process for the chemical removal of steam generator corrosion product accumulations. In this report, the contractor describes the results of a pot boiler demonstration test of the SGOG/EPRI Mark III Chemical Cleaning process.

  18. Steam-generator chemical-cleaning process development. Final report. [PWR

    SciTech Connect

    Schneidmiller, D.; Stiteler, D.

    1983-04-01

    As a result of work sponsored by the Steam Generator Owners Group (SGOG) and managed by the Electric Power Research Institute (EPRI), a process for chemical removal of iron- and copper-bearing sludges and tube-to-support plate crevice corrosion product deposits from the secondary side of pressurized water reactor (PWR) steam generators has been developed. The process has undergone extensive pilot-scale testing and has shown to be effective for the removal of both synthetic and actual steam generator corrosion product deposits. This report documents the results of UNC Nuclear Industries' participation in the SGOG chemical cleaning development program.

  19. VERA Modeling and Simulation of the AP1000 PWR Cycle 1 Depletion

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    CASL-U-2015-0302-000 VERA Modeling and Simulation of the AP1000 PWR Cycle 1 Depletion L3:VMA.AMA.P11.06 David Salazar, Westinghouse Fausto Franceschini, Westinghouse September 30, 2015 L3:VMA.AMA.P11.06 Official Use Only ii Protected under CASL Master NDA CASL-U-2015-0302-000 REVISION LOG Revision Date Affected Pages Revision Description 0 09/30/2015 All Initial issuance Document pages that are: Export Controlled ____________No______________________________________ IP/Proprietary/NDA

  20. Application of LBB to high energy piping systems in operating PWR

    SciTech Connect

    Swamy, S.A.; Bhowmick, D.C.

    1997-04-01

    The amendment to General Design Criterion 4 allows exclusion, from the design basis, of dynamic effects associated with high energy pipe rupture by application of leak-before-break (LBB) technology. This new approach has resulted in substantial financial savings to utilities when applied to the Pressurized Water Reactor (PWR) primary loop piping and auxiliary piping systems made of stainless steel material. To date majority of applications pertain to piping systems in operating plants. Various steps of evaluation associated with the LBB application to an operating plant are described in this paper.

  1. Secondary Startup Neutron Sources as a Source of Tritium in a Pressurized Water Reactor (PWR) Reactor Coolant System (RCS)

    SciTech Connect

    Shaver, Mark W.; Lanning, Donald D.

    2010-02-01

    The hypothesis of this paper is that the Zircaloy clad fuel source is minimal and that secondary startup neutron sources are the significant contributors of the tritium in the RCS that was previously assigned to release from fuel. Currently there are large uncertainties in the attribution of tritium in a Pressurized Water Reactor (PWR) Reactor Coolant System (RCS). The measured amount of tritium in the coolant cannot be separated out empirically into its individual sources. Therefore, to quantify individual contributors, all sources of tritium in the RCS of a PWR must be understood theoretically and verified by the sum of the individual components equaling the measured values.

  2. Application of the MELCOR code to design basis PWR large dry containment analysis.

    SciTech Connect

    Phillips, Jesse; Notafrancesco, Allen; Tills, Jack Lee

    2009-05-01

    The MELCOR computer code has been developed by Sandia National Laboratories under USNRC sponsorship to provide capability for independently auditing analyses submitted by reactor manufactures and utilities. MELCOR is a fully integrated code (encompassing the reactor coolant system and the containment building) that models the progression of postulated accidents in light water reactor power plants. To assess the adequacy of containment thermal-hydraulic modeling incorporated in the MELCOR code for application to PWR large dry containments, several selected demonstration designs were analyzed. This report documents MELCOR code demonstration calculations performed for postulated design basis accident (DBA) analysis (LOCA and MSLB) inside containment, which are compared to other code results. The key processes when analyzing the containment loads inside PWR large dry containments are (1) expansion and transport of high mass/energy releases, (2) heat and mass transfer to structural passive heat sinks, and (3) containment pressure reduction due to engineered safety features. A code-to-code benchmarking for DBA events showed that MELCOR predictions of maximum containment loads were equivalent to similar predictions using a qualified containment code known as CONTAIN. This equivalency was found to apply for both single- and multi-cell containment models.

  3. Study of a transient identification system using a neural network for a PWR plant

    SciTech Connect

    Ishihara, Yoshinao; Kasai, Masao; Kambara, Masayuki [Mitsubishi Heavy Industries, Ltd., Yokohama (Japan); Mitsuda, Hiromichi; Kurata, Toshikazu; Shirosaki, Hidekazu [Inst. of Nuclear Safety System, Inc., Kyoto (Japan)

    1996-08-01

    This paper presents the procedure and results of a system for identifying PWR plant abnormal events, which uses neural network techniques. The neural network recognizes the abnormal event from the patterns of the transient changes of analog data from plant parameters when they deport from their normal state. For the identification of abnormal events in this study, events that cause a reactor to scram during power operation were selected as the design base events. The test data were prepared by simulating the transients on a compact PWR simulator. The simulation data were analyzed to determine how the plant parameters respond after the occurrence of a transient. A method of converting the pattern of the transient changes into characteristic parameters by fitting the data to pre-determined functions was developed. These characteristic parameters were used as the input data to the neural network. The neural network learning procedure used a generalized delta rule, namely a back-propagation algorithm. The neural network can identify the type of an abnormal event from a limited set of events by using these characteristic parameters obtained from the pattern of the changes in the analog data. From the results of this application of a neural network, it was concluded that it would be possible to use the method to identify abnormal events in a nuclear power plant.

  4. Validation of the new code package APOLLO2.8 for accurate PWR neutronics calculations

    SciTech Connect

    Santamarina, A.; Bernard, D.; Blaise, P.; Leconte, P.; Palau, J. M.; Roque, B.; Vaglio, C.; Vidal, J. F.

    2013-07-01

    This paper summarizes the Qualification work performed to demonstrate the accuracy of the new APOLLO2.S/SHEM-MOC package based on JEFF3.1.1 nuclear data file for the prediction of PWR neutronics parameters. This experimental validation is based on PWR mock-up critical experiments performed in the EOLE/MINERVE zero-power reactors and on P.I. Es on spent fuel assemblies from the French PWRs. The Calculation-Experiment comparison for the main design parameters is presented: reactivity of UOX and MOX lattices, depletion calculation and fuel inventory, reactivity loss with burnup, pin-by-pin power maps, Doppler coefficient, Moderator Temperature Coefficient, Void coefficient, UO{sub 2}-Gd{sub 2}O{sub 3} poisoning worth, Efficiency of Ag-In-Cd and B4C control rods, Reflector Saving for both standard 2-cm baffle and GEN3 advanced thick SS reflector. From this qualification process, calculation biases and associated uncertainties are derived. This code package APOLLO2.8 is already implemented in the ARCADIA new AREVA calculation chain for core physics and is currently under implementation in the future neutronics package of the French utility Electricite de France. (authors)

  5. Recommendations for Addressing Axial Burnup in the PWR Burnup Credit Analyses

    SciTech Connect

    Wagner, J.C.

    2002-10-23

    This report presents studies performed to support the development of a technically justifiable approach for addressing the axial-burnup distribution in pressurized-water reactor (PWR) burnup-credit criticality safety analyses. The effect of the axial-burnup distribution on reactivity and proposed approaches for addressing the axial-burnup distribution are briefly reviewed. A publicly available database of profiles is examined in detail to identify profiles that maximize the neutron multiplication factor, k{sub eff}, assess its adequacy for PWR burnup credit analyses, and investigate the existence of trends with fuel type and/or reactor operations. A statistical evaluation of the k{sub eff} values associated with the profiles in the axial-burnup-profile database was performed, and the most reactive (bounding) profiles were identified as statistical outliers. The impact of these bounding profiles on k{sub eff} is quantified for a high-density burnup credit cask. Analyses are also presented to quantify the potential reactivity consequence of loading assemblies with axial-burnup profiles that are not bounded by the database. The report concludes with a discussion on the issues for consideration and recommendations for addressing axial burnup in criticality safety analyses using burnup credit for dry cask storage and transportation.

  6. Code System for PWR & BWR Multicompartment Containment Analysis, Versions MOD5

    Energy Science and Technology Software Center

    1999-06-02

    CONTEMPT4/MOD6 describes the response of multicompartment containment systems subjected to postulated loss-of-coolant accident (LOCA) conditions. The program can accommodate both pressurized water reactor (PWR) and boiling water reactor (BWR) containment systems. Also, both design basis accident (DBA) and degraded core type LOCA conditions can be analyzed. The program calculates the time variation of compartment pressures, temperatures, and mass and energy inventories due to inter-compartment mass and energy exchange taking into account user-supplied descriptions of compartments,more » inter-compartment junction flow areas, LOCA source terms, and user-selected problem features. Analytical models available to describe containment systems include models for containment fans and pumps, cooling sprays, heat conducting structures, sump drains, PWR ice condensers, and BWR pressure suppression systems. CONTEMPT4/MOD6 also provides analytical models for hydrogen and carbon monoxide combustion within compartments and energy transfer due to gas radiation to accommodate degraded core type accidents.« less

  7. Phenomenon analysis of stress corrosion cracking in the vessel head penetrations of French PWR`s

    SciTech Connect

    Pichon, C.; Buisine, D.; Faidy, C.; Gelpi, A.; Vaindirlis, M.

    1995-12-31

    During a hydrotest in 1991, a leak was detected on,a reactor vessel head (RVH) penetration of a French PWR. This leak was due to a phenomenon of Primary Water Stress Corrosion Cracking (PWSCC) affecting these penetrations in Alloy 600. The destructive and non-destructive examinations undertaken during the following months highlighted the generic nature of the degradations. In order to well understand this phenomenon and implement the most suitable maintenance policy, a large scale scientific program was decided and performed jointly by Electricite de France and FRAMATOME. The paper will present all the results obtained in this program concerning the parameters governing the PWSCC. In particular the following fields will be developed: (1) the material, its microstructure in line with the manufacturing and its susceptibility to PWSCC; (2) the stresses and their evaluations by measurements, mock up corrosion tests and Finite Element Analysis (FEA); (3) the effect of surface finish on crack initiation; and (4) the crack growth rate. This phenomenon analysis will be useful for evaluating the risk of PWSCC on other Alloy 600 areas in PWR`s primary system.

  8. Department of Energy, Department of the Interior and Army Corps of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Engineers Renew Five-Year Partnership to Advance Hydropower | Department of Energy Energy, Department of the Interior and Army Corps of Engineers Renew Five-Year Partnership to Advance Hydropower Department of Energy, Department of the Interior and Army Corps of Engineers Renew Five-Year Partnership to Advance Hydropower March 24, 2015 - 3:56pm Addthis NEWS MEDIA CONTACT 202-586-4940 DOENews@hq.doe.gov WASHINGTON - The U.S. Department of Energy, U.S. Department of the Interior and U.S.

  9. Maximim Accelerations On The Fuel Assemblies Of a 21-PWR Waste Package During End Impacts 

    SciTech Connect

    V. DeLa Brosse

    2003-03-27

    The objective of this calculation is to determine the acceleration of the fuel assemblies contained in a 21-Pressurized Water Reactor (PWR) spent nuclear fuel waste package impacting an unyielding surface. A range of initial velocities of the waste package is studied. The scope of this calculation is limited to estimating the acceleration of the fuel assemblies during the impact.

  10. Maximim Accelerations On The Fuel Assemblies Of a 21-PWR Waste Package During End Impacts 

    SciTech Connect

    T. Schmitt

    2005-08-17

    The objective of this calculation is to determine the acceleration of the fuel assemblies contained in a 21-Pressurized Water Reactor (PWR) spent nuclear fuel waste package impacting an unyielding surface. A range of initial velocities of the waste package is studied. The scope of this calculation is limited to estimating the acceleration of the fuel assemblies during the impact.

  11. Development of a model for predicting intergranular stress corrosion cracking of Alloy 600 tubes in PWR primary water. Final report

    SciTech Connect

    Garud, Y.S.

    1985-01-01

    A preliminary mathematical model developed in this study may make it possible to predict stress corrosion cracking on the primary side of PWR steam generator tubing. The study outlines a comprehensive testing program that will provide the operational and experimental data to further develop and verify the model.

  12. Application to Export Electric Energy OE Docket No. EA-345-A New Brunswick Energy Marketing Corp: Federal Register Notice, Volume 78, No. 208- Oct. 28, 2013

    Energy.gov [DOE]

    Application from New Brunswick Energy Marketing Corp to export electric energy to Canada.  Federal Register Notice.

  13. Lab-Corps Program Helping to Accelerate Commercialization of Clean Energy Technologies from our National Labs

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Lab-Corps pilot program was launched last year to accelerate the transfer of new clean energy technologies from the U.S. Department of Energy's National Laboratories into the commercial marketplace. Just six months into the program, we are already seeing some exciting results.

  14. U.S. Marine Corps Stand at Forefront of Energy and Water Savings

    SciTech Connect

    2012-12-01

    Located in the heart of South Carolina, the U.S. Marine Corps Air Station (MCAS) Beaufort is among the military’s most important installations. Located on 6,900 acres 70 miles southwest of Charleston, the installation has established an energy- and water-saving culture that explores and implements new strategies and management approaches aimed at surpassing presidential mandates.

  15. Grid-to-rod flow-induced impact study for PWR fuel in reactor

    DOE PAGES [OSTI]

    Jiang, Hao; Qu, Jun; Lu, Roger Y.; Wang, Jy-An John

    2016-06-10

    The source for grid-to-rod fretting in a pressurized water nuclear reactor (PWR) is the dynamic contact impact from hydraulic flow-induced fuel assembly vibration. In order to support grid-to-rod fretting wear mitigation research, finite element analysis (FEA) was used to evaluate the hydraulic flow-induced impact intensity between the fuel rods and the spacer grids. Three-dimensional FEA models, with detailed geometries of the dimple and spring of the actual spacer grids along with fuel rods, were developed for flow impact simulation. The grid-to-rod dynamic impact simulation provided insights of the contact phenomena at grid-rod interface. Finally, it is an essential and effectivemore » way to evaluate contact forces and provide guidance for simulative bench fretting-impact tests.« less

  16. Decay Heat of Major Radionuclides for PWR Spent Fuels to 10,000 Years

    SciTech Connect

    J.S. Tang

    2001-12-20

    The objective of this calculation is to determine decay heat of a pressurized-water reactor (PWR) spent nuclear fuel (SNF) assembly with four different initial-enrichment and burnup characteristics. The major contributing radionuclides to the decay heat are also identified and graphically presented. The scope of this calculation is limited to the time period of the first 10,000 years after discharge from reactors. The results of this calculation will be used to evaluate the effects of the projected commercial spent nuclear fuel (CSNF) inventory on the repository design based on revised nuclear energy forecasts. This calculation was performed in accordance with the ''Technical Work Plan for: Waste Package Design Description for LA'' (BSC (Bechtel SAIC Company) 2001). AP-3.12Q, Calculations, is used to perform the calculation and develop the document. This calculation is associated with the repository design activity.

  17. A comparison of the CHF between tubes and annuli under PWR thermal-hydraulic conditions

    SciTech Connect

    Herer, C.

    1995-09-01

    Critical Heat Flux (CHF) tests were carried out in three tubes with inside diameters of 8, 13, and 19.2 mm and in two annuli with an inner tube of 9.5 mm and an outer tube of 13 or 19.2 mm. All axial heat flux distributions in the test sections were uniform. The coolant fluid was Refrigerant 12 (Freon-12) under PWR thermal-hydraulic conditions (equivalent water conditions - Pressure: 7 to 20 MPa, Mass Velocity: 1000 to 6000 kg/m2/s, Local Quality: -75% to +45%). The effect of tube diameter is correlated for qualities under 15%. The change from the tube to the annulus configuration is correctly taken into account by the equivalent hydraulic diameter. Useful information is also provided concerning the effect of a cold wall in an annulus.

  18. On the explanation and calculation of anomalous reflood hydrodynamics in large PWR cores

    SciTech Connect

    Rodriguez, S.E.

    1985-01-01

    Reflood hydrodynamics from large-scale (1:20) test facilities in Japan have yielded apparently anomalous behavior relative to FLECHT tests. Namely, even at reflooding rates below one inch per second, very large liquid volume fractions (10-15%) exist above the quench fronts shortly after flood begins; thus cladding temperature excursions are terminated early in the reflood phase. This paper discusses an explanation for this behavior: liquid films on the core's unheated rods. The experimental findings are shown to be correctly simulated with a new four-field (vapor, films, droplets) version of the best-estimate TRAC-PF1 computer code, TRAC-FF. These experimental and analytical findings have important implications for PWR large-break LOCA licensing.

  19. Effect of coolant chemistry on PWR radiation transport processes. Progress report on reactor loop studies

    SciTech Connect

    Brown, D.J.; Flynn, G.; Haynes, J.W.; Kitt, G.P.; Large, N.R.; Lawson, D.; Mead, A.P.; Nichols, J.L.; Woodwark, D.R.

    1986-05-01

    The effect of various PWR-type coolant chemistry regimes on the behavior of corrosion products has been studied in the DIDO Water Loop at Harwell. There are strong indications that the in-core deposition behavior of corrosion product species is not fully accounted for by the solubility model based on nickel ferrite; boric acid plays a role apart from its influence on pH, and corrosion products are adsorbed to some extent in the zirconium oxide film on the fuel cladding. In DWL, soluble species appear to be dominant in deposition processes. A most important factor governing deposition behavior is surface condition; the influence of weld regions and the effect of varying pretreatment conditions have both been demonstrated. 13 figs.

  20. Fuel-rod response during the large-break LOCA Test LOC-6. [PWR

    SciTech Connect

    Vinjamuri, K.; Cook, B.A.; Hobbins, R.R.

    1981-01-01

    The large break Loss of Coolant Accident (LOCA) Test LOC-6 was conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory by EG and G Idaho, Inc. The objectives of the PBF LOCA tests are to obtain in-pile cladding ballooning data under blowdown and reflood conditions and assess how well out-of-pile ballooning data represent in-pile fuel rod behavior. The primary objective of the LOC-6 test was to determine the effects of internal rod pressures and prior irradiation on the deformation behavior of fuel rods that reached cladding temperatures high in the alpha phase of zircaloy. Test LOC-6 was conducted with four rods of PWR 15 x 15 design with the exception of fuel stack length (89 cm) and enrichment (12.5 W% /sup 235/U). Each rod was surrounded by an individual flow shroud.

  1. LOCA rupture strains and coolability of full-length PWR fuel bundles

    SciTech Connect

    Mohr, C.L.; Hesson, G.M.

    1983-03-01

    The LOCA Simulation Program tests sponsored by the United States Nuclear Regulatory Commission are the first full-length nuclear-heated experiments designed to investigate the deformation and rupture characteristics as well as the coolability of nuclear-heated fuel under accident conditions. The results of the seven tests preformed in the program using 32-rod full-length PWR fuel bundles have shown that for a wide range of flow blockage condtions no significant reduction in coolability of the fuel bundle could be found. These results have been confirmed by data from out-of-pile electrically-heated experiments. Although there is a difference between nuclear and electrically-heated test data, the conclusion is still the same. Coolability of a deformed bundle during reflood is dominated by the dispersion of droplets in the deformed zone which provides adequate cooling and which is not reduced by the deformation of the fuel rod cladding.

  2. Source term experiment STEP-3 simulating a PWR severe station blackout

    SciTech Connect

    Simms, R.; Baker, L. Jr.; Ritzman, R.L.

    1987-05-21

    For a severe PWR accident that leads to a loss of feedwater to the steam generators, such as might occur in a station blackout, fission product decay heating will cause a water boiloff. Without effective cooling of the core, steam will begin to oxidize the Zircaloy cladding. The noble gases and volatile fission products, such as Cs and I, that are major contributors to the radiological source term, will be released from the damaged fuel shortly after cladding failure. The accident environment when these volatile fission products escape was simulated in STEP-3 using four fuel elements from the Belgonucleaire BR3 reactor. The primary objective was to examine the releases in samples collected as close to the test zone as possible. In this paper, an analysis of the temperatures and hydrogen generation is compared with the measurements. The analysis is needed to estimate releases and characterize conditions at the source for studies of fission product transport.

  3. Electrically heated ex-reactor pellet-cladding interaction (PCI) simulations utilizing irradiated Zircaloy cladding. [PWR

    SciTech Connect

    Barner, J.O.; Fitzsimmons, D.E.

    1985-02-01

    In a program sponsored by the Fuel Systems Research Branch of the US Nuclear Regulatory Commission, a series of six electrically heated fuel rod simulation tests were conducted at Pacific Northwest Laboratory. The primary objective of these tests was to determine the susceptibility of irradiated pressurized-water reactor (PWR) Zircaloy-4 cladding to failures caused by pellet-cladding mechanical interaction (PCMI). A secondary objective was to acquire kinetic data (e.g., ridge growth or relaxation rates) that might be helpful in the interpretation of in-reactor performance results and/or the modeling of PCMI. No cladding failures attributable to PCMI occurred during the six tests. This report describes the testing methods, testing apparatus, fuel rod diametral strain-measuring device, and test matrix. Test results are presented and discussed.

  4. IMPACT OF FISSION PRODUCTS IMPURITY ON THE PLUTONIUM CONTENT IN PWR MOX FUELS

    SciTech Connect

    Gilles Youinou; Andrea Alfonsi

    2012-03-01

    This report presents the results of a neutronics analysis done in response to the charter IFCA-SAT-2 entitled 'Fuel impurity physics calculations'. This charter specifies that the separation of the fission products (FP) during the reprocessing of UOX spent nuclear fuel assemblies (UOX SNF) is not perfect and that, consequently, a certain amount of FP goes into the Pu stream used to fabricate PWR MOX fuel assemblies. Only non-gaseous FP have been considered (see the list of 176 isotopes considered in the calculations in Appendix 1). This mixture of Pu and FP is called PuFP. Note that, in this preliminary analysis, the FP losses are considered element-independent, i.e., for example, 1% of FP losses mean that 1% of all non-gaseous FP leak into the Pu stream.

  5. Probability and consequences of a rapid boron dilution sequence in a PWR

    SciTech Connect

    Diamond, D.J.; Kohut, P.; Nourbakhsh, H.; Valtonen, K.; Secker, P.

    1995-11-01

    The reactor restart scenario is one of several beyond-design-basis events in a pressurized water reactor (PWR) which can lead to rapid boron dilution in the core. This in turn can lead to a power excursion and the potential for fuel damage. A probabilistic analysis had been done for this event for a European PWR. The estimated core damage frequency was found to be high partially because of a high frequency for a LOOP and assumptions regarding operator actions. As a result, a program of analysis and experiment was initiated and corrective actions were taken. A system was installed so that the suction of the charging pumps would switch to the highly borated refueling water storage tank (RWST) when there was a trip of the RCPs. This was felt to reduce the estimated core damage frequency to an acceptable level. In the US, this original study prompted the Nuclear Regulatory Commission to issue an information notice to follow work being done in this area and to initiate studies such as the work at BNL reported herein. In order to see if the core damage frequency might be as high in US plants, a probabilistic assessment of this scenario was done for three plants. Two important conservative assumptions in this analysis were that (1) the mixing of the injectant was insignificant and (2) fuel damage occurs when the slug passes through the core. In order to study the first assumption, analysis was carried out for two of the plants using a mixing model. The second assumption was studied by calculating the neutronic response of the core to a slug of deborated water for one of the plants. All three types of analyses are summarized below. More information is available in the original report.

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

    SciTech Connect

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

    1986-11-01

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

  7. Irradiation Test of Advanced PWR Fuel in Fuel Test Loop at HANARO

    SciTech Connect

    Yang, Yong Sik; Bang, Je Geon; Kim, Sun Ki; Song, Kun Woo; Park, Su Ki; Seo, Chul Gyo

    2007-07-01

    A new fuel test loop has been constructed in the research reactor HANARO at KAERI. The main objective of the FTL (Fuel Test Loop) is an irradiation test of a newly developed LWR fuel under PWR or Candu simulated conditions. The first test rod will be loaded within 2007 and its irradiation test will be continued until a rod average their of 62 MWd/kgU. A total of five test rods can be loaded into the IPS (In-Pile Section) and fuel centerline temperature, rod internal pressure and fuel stack elongation can be measured by an on-line real time system. A newly developed advanced PWR fuel which consists of a HANA{sup TM} alloy cladding and a large grain UO{sub 2} pellet was selected as the first test fuel in the FTL. The fuel cladding, the HANA{sup TM} alloy, is an Nb containing Zirconium alloy that has shown better corrosion and creep resistance properties than the current Zircaloy-4 cladding. A total of six types of HANA{sup TM} alloy were developed and two or three of these candidate alloys will be used as test rod cladding, which have shown a superior performance to the others. A large-grain UO{sub 2} pellet has a 14{approx}16 micron 2D diameter grain size for a reduction of a fission gas release at a high burnup. In this paper, characteristics of the FTL and IPS are introduced and the expected operation and irradiation conditions are summarized for the test periods. Also the preliminary fuel performance analysis results, such as the cladding oxide thickness, fission gas release and rod internal pressure, are evaluated from the test rod safety analysis aspects. (authors)

  8. Radionuclide release from PWR fuels in a reference tuff repository groundwater subsquently changed to Radionuclide release from PWR fuels in J-13 well water

    SciTech Connect

    Wilson, C.N.; Oversby, V.M.

    1985-04-01

    The Nevada Nuclear Waste Storage Investigations Project (NNWSI) is studying the suitability of the welded devitrified Topopah Spring tuff at Yucca Mountain, Nye County, Nevada, for potential use as a high level nuclear waste repository. In support of the Waste Package task of NNWSI, tests have been conducted under ambient air environment to measure radionuclide release from two pressurized water reactor (PWR) spent fuels in water obtained from the J-13 well near the Yucca Mountain site. Four specimen types, representing a range of fuel physical conditions that may exist in a failed waste canister containing a limited amount of water were tested. The specimen types were: (1) fuel rod sections split open to expose bare fuel particles; (2) rod sections with water-tight end fittings with a 2.5-cm long by 150-{mu}m wide slit through the cladding; (3) rod sections with water-tight end fittings and two 200-{mu}m diameter holes through the cladding; and (4) undefected rod segments with water-tight end fittings. Radionuclide release results from the first 223-day test runs on H.B. Robinson spent fuel specimens in J-13 water are reported and compared to results from a previous test series in which similar Turkey Point reactor spent fuel specimens were tested in deionized water. Selected initial results are also given for Turkey Point fuel specimens tested in J-13 water. Results suggest that the actinides Pu, Am, Cm and Np are released congruently with U as the UO{sub 2} spent fuel matrix dissolves. Fractional release of {sup 137}Cs and {sup 99}Tc was greater than that measured for the actinides. Generally, lower radionuclide releases were measured for the H.B. Robinson fuel in J-13 water than for Turkey Point Fuel in deionized water.

  9. Analysis of results from a loss-of-offsite-power-initiated ATWS experiment in the LOFT facility. [PWR

    SciTech Connect

    Varacalle, D.J. Jr.; Koizumi, Y.; Giri, A.H.; Koske, J.E.; Sanchez-Pope, A.E.

    1983-01-01

    An anticipated transient without scram (ATWS), initiated by loss-of-offsite power, was experimentally simulated in the Loss-of-Fluid Test (LOFT) pressurized water reactor (PWR). Primary system pressure was controlled using a scaled safety relief valve (SRV) representative of those in a commercial PWR, while reactor power was reduced by moderator reactivity feedback in a natural circulation mode. The experiment showed that reactor power decreases more rapidly when the primary pumps are tripped in a loss-of-offsite-power ATWS than in a loss-of-feedwater induced ATWS when the primary pumps are left on. During the experiment, the SRV had sufficient relief capacity to control primary system pressure. Natural circulation was effective in removing core heat at high temperature, pressure, and core power. The system transient response predicted using the RELAP5/MOD1 computer code showed good agreement with the experimental data.

  10. Results and analysis of a loss-of-feedwater induced ATWS experiment in the LOFT facility. [PWR

    SciTech Connect

    Grush, W.H.; Woerth, S.C.; Koizumi, Y.

    1983-01-01

    An anticipated transient without scram (ATWS), initiated by a loss of feedwater, was experimentally simulated in the Loss-of-Fluid Test (LOFT) pressurized water reactor (PWR). Primary system pressure was controlled using a two-position actuator relief valve to simulate a scaled power-operated relief valve (PORV) and safety relief valve (SRV) representative of those in a commercial PWR. Auxiliary feedwater injection was delayed during the experiment until the plant recovery phase where long-term shutdown was achieved by an operator-controlled plant recovery procedure without inserting the control rods. The system transient response predicted by the RELAP5/MOD1 computer code showed good agreement with the experimental data.

  11. SAS2H Generated Isotopic Concentrations For B&W 15X15 PWR Assembly (SCPB:N/A)

    SciTech Connect

    J.W. Davis

    1996-08-29

    This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to provide pressurized water reactor (PWR) isotopic composition data as a function of time for use in criticality analyses. The objectives of this evaluation are to generate burnup and decay dependant isotopic inventories and to provide these inventories in a form which can easily be utilized in subsequent criticality calculations.

  12. ConocoPhillips Alaska Natural Gas Corp. (ConocoPhillips)- EXPORT TO CANADA- FE DKT. 15-149-LNG

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Office of Fossil Energy gives notice of receipt of an Application filed September 28, 2015, by ConocoPhillips Alaska Natural Gas Corp. (ConocoPhillips), seeking a long-term multi-contract...

  13. Final Report Recommended Actions to Reduce Electrical Peak Loads at the Marine Corps Air Station at Camp Pendleton, California

    SciTech Connect

    Hail, John C.; Brown, Daryl R.; McCullough, Jeffrey J.; Underhill, Ronald M.

    2001-05-08

    PNNL conducted a walk-through audit of Marine Corps Air Station at Camp Pendleton. The audit inspected a significant portion of the site and identified a large number of similar energy saving opportunities across all building types.

  14. Lab-Corps Pilot Accelerates Private-Sector Adoption of Game-Changing Technologies

    Energy.gov [DOE]

    Last week, the EERE Lab-Corps Initiative graduated its first class of top scientists who’ve gone back to school to gain an entrepreneurial education. With technologies ranging from bioenergy to building efficiencies, this $2.3 million pilot program, managed by the National Renewable Energy Laboratory (NREL), trains top lab researchers across the nation on how to move high-impact national laboratory-invented technologies into the market.

  15. APPENDIX A DISTRIBUTION LIST Federal Government Agencies Army Corps of Engineers, Sacramento District Headquarter Office

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    A DISTRIBUTION LIST Federal Government Agencies Army Corps of Engineers, Sacramento District Headquarter Office Engineering/Design Branch, Regulatory Branch, Planning Branch 1325 J Street, Room 1350 Sacramento, California 95814 Phone: (916) 557-5250 Fax: (916) 557-5306 Department of the Interior San Francisco Regional Office - AS, AZ, CA, CNMI, GU, HI, NV Ms. Patricia Sanderson Port Regional Environmental Officer Department of the Interior 333 Bush Street San Francisco, CA 94104 Phone:

  16. Microsoft Word - DOE Overseas Corps Training Program _Final complete_.doc

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    DOE/NNSA Overseas Presence Advisory Board's Overseas Corps Training Program Agreement Purpose of Training Program under this Agreement The Department of Energy provides workforce resources to support the Department's mission and strategic plan objectives and requirements in overseas assignments. The individuals and their families carrying out these assignments need to be prepared to work with other Federal agencies, such as the Departments of State (DOS) and Defense (DOD), and with

  17. Two Argonne teams win pitch competition, advance to national Lab-Corps

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    training program | Argonne National Laboratory Argonne postdoctoral appointee and computational scientist Diego Fazi presents before Lab-Corps judges as part of a team competing for funds to help commercialize their idea called the Frequency Sensing Charge Controller, which is a device that helps to stabilize the electric grid by automatically adjusting the charging load of electric vehicles. (Click image to view larger.) Argonne postdoctoral appointee and computational scientist Diego Fazi

  18. Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment and Recommendations

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment and Recommendations K. Burman, A. Kandt, L. Lisell, S. Booth, A. Walker, J. Roberts and J. Falcey Technical Report NREL/ TP-7A40-52897 November 2011 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. National Renewable Energy Laboratory 1617 Cole Boulevard Golden, Colorado 80401 303-275-3000 *

  19. Development and Application of Laser Peening System for PWR Power Plants

    SciTech Connect

    Masaki Yoda; Itaru Chida; Satoshi Okada; Makoto Ochiai; Yuji Sano; Naruhiko Mukai; Gaku Komotori; Ryoichi Saeki; Toshimitsu Takagi; Masanori Sugihara; Hirokata Yoriki

    2006-07-01

    Laser peening is a process to improve residual stress from tensile to compressive in surface layer of materials by irradiating high-power laser pulses on the material in water. Toshiba has developed a laser peening system composed of Q-switched Nd:YAG laser oscillators, laser delivery equipment and underwater remote handling equipment. We have applied the system for Japanese operating BWR power plants as a preventive maintenance measure for stress corrosion cracking (SCC) on reactor internals like core shrouds or control rod drive (CRD) penetrations since 1999. As for PWRs, alloy 600 or 182 can be susceptible to primary water stress corrosion cracking (PWSCC), and some cracks or leakages caused by the PWSCC have been discovered on penetrations of reactor vessel heads (RVHs), reactor bottom-mounted instrumentation (BMI) nozzles, and others. Taking measures to meet the unconformity of the RVH penetrations, RVHs themselves have been replaced in many PWRs. On the other hand, it's too time-consuming and expensive to replace BMI nozzles, therefore, any other convenient and less expensive measures are required instead of the replacement. In Toshiba, we carried out various tests for laser-peened nickel base alloys and confirmed the effectiveness of laser peening as a preventive maintenance measure for PWSCC. We have developed a laser peening system for PWRs as well after the one for BWRs, and applied it for BMI nozzles, core deluge line nozzles and primary water inlet nozzles of Ikata Unit 1 and 2 of Shikoku Electric Power Company since 2004, which are Japanese operating PWR power plants. In this system, laser oscillators and control devices were packed into two containers placed on the operating floor inside the reactor containment vessel. Laser pulses were delivered through twin optical fibers and irradiated on two portions in parallel to reduce operation time. For BMI nozzles, we developed a tiny irradiation head for small tubes and we peened the inner surface around J

  20. Examination of spent PWR fuel rods after 15 years in dry storage.

    SciTech Connect

    Einziger, R.E.; Tsai, H.C.; Billone, M.C.; Hilton, B.A.

    2002-02-11

    Virginia Power Surry Nuclear Station Pressurized Water Reactor (PWR) fuel was stored in a dry inert atmosphere Castor V/21 cask at the Idaho National Environmental and Engineering Laboratory (INEEL) for 15 years at peak cladding temperatures decreasing from about 350 to 150 C. Prior to the storage, the loaded cask was subjected to extensive thermal benchmark tests. The cask was opened to examine the fuel for degradation and to determine if it was suitable for extended storage. No rod breaches had occurred and no visible degradation or crud/oxide spallation were observed. Twelve rods were removed from the center of the T11 assembly and shipped from INEEL to the Argonne-West HFEF for profilometric scans. Four of these rods were punctured to determine the fission gas release from the fuel matrix and internal pressure in the rods. Three of the four rods were cut into five segments each, then shipped to the Argonne-East AGHCF for detailed examination. The test plan calls for metallographic examination of six samples from two of the rods, microhardness and hydrogen content measurements at or near the six metallographic sample locations, tensile testing of six samples from the two rods, and thermal creep testing of eight samples from the two rods to determine the extent of residual creep life. The results from the profilometry (12 rods), gas release measurements (4 rods), metallographic examinations (2 samples from 1 rod), and microhardness and hydrogen content characterization (2 samples from 1 rod) are reported here. The tensile and creep studies are just starting and will be reported at a later date, along with the additional characterization work to be performed. Although only limited prestorage characterization is available, a number of preliminary conclusions can be drawn based on comparison with characterization of Florida Power Turkey Point rods of a similar vintage. Based on this comparison, it appears that little or no cladding thermal creep and fission gas

  1. Examination of Spent PWR Fuel Rods After 15 Years in Dry Storage

    SciTech Connect

    Einziger, R.E.; Tsai, H.C.; Billone, M.C.; Hilton, B.A.

    2002-07-01

    Virginia Power Surry Nuclear Station Pressurized Water Reactor (PWR) fuel was stored in a dry inert atmosphere Castor V/21 cask at the Idaho National Environmental and Engineering Laboratory (INEEL) for 15 years at peak cladding temperatures decreasing from about 350 to 150 deg. C. Prior to the storage, the loaded cask was subjected to extensive thermal benchmark tests. The cask was opened to examine the fuel for degradation and to determine if it was suitable for extended storage. No rod breaches had occurred and no visible degradation or crud/oxide spallation were observed. Twelve rods were removed from the center of the T11 assembly and shipped from INEEL to the Argonne-West HFEF for profilometric scans. Four of these rods were punctured to determine the fission gas release from the fuel matrix and internal pressure in the rods. Three of the four rods were cut into five segments each, then shipped to the Argonne-East AGHCF for detailed examination. The test plan calls for metallographic examination of six samples from two of the rods, microhardness and hydrogen content measurements at or near the six metallographic sample locations, tensile testing of six samples from the two rods, and thermal creep testing of eight samples from the two rods to determine the extent of residual creep life. The results from the profilometry (12 rods), gas release measurements (4 rods), metallographic examinations (2 samples from 1 rod), and microhardness and hydrogen content characterization (2 samples from 1 rod) are reported here. The tensile and creep studies are just starting and will be reported at a later date, along with the additional characterization work to be performed. Although only limited pre-storage characterization is available, a number of preliminary conclusions can be drawn based on comparison with characterization of Florida Power Turkey Point rods of a similar vintage. Based on this comparison, it appears that little or no cladding thermal creep and fission

  2. TREAT source-term experiment STEP-1 simulating a PWR LOCA

    SciTech Connect

    Simms, R.; Baker, L. Jr.; Blomquist, C.A.; Ritzman, R.L.

    1986-01-01

    In a hypothetical pressurized water reactor (PWR) large-break loss-of-coolant accident (LOCA) in which the emergency core cooling system fails, fission product decay heating causes water boil-off and reduced heat removal. Zircaloy cladding is oxidized by the steam. The noble gases and volatile fission products such as cesium and iodine that constitute a principal part of the source term will be released from the damaged fuel at or shortly after the time of cladding failure. TREAT test STEP-1 simulated the LOCA environment when the volatile fission products would be released using four fuel elements from the Belgonucleaire BR3 reactor. The principal objective was to collect a portion of the releases carried by the flow stream in a region as close as possible to the test zone. In this paper, the test is described and the results of an analysis of the thermal and steam/hydrogen environment are compared with the test measurements in order to provide a characterization for analysis of fission product releases and aerosol formation. The results of extensive sample examinations are reported separately.

  3. The stress corrosion cracking behavior of alloys 690 and 152 WELD in a PWR environment.

    SciTech Connect

    Alexandreanu, B.; Chopra, O. K.; Shack, W. J.

    2009-01-01

    Alloys 690 and 152 are the replacement materials of choice for Alloys 600 and 182, respectively. The latter two alloys are used as structural materials in pressurized water reactors (PWRs) and have been found to undergo stress corrosion cracking (SCC). The objective of this work is to determine the crack growth rates (CGRs) in a simulated PWR water environment for the replacement alloys. The study involved Alloy 690 cold-rolled by 26% and a laboratory-prepared Alloy 152 double-J weld in the as-welded condition. The experimental approach involved pre-cracking in a primary water environment and monitoring the cyclic CGRs to determine the optimum conditions for transitioning from the fatigue transgranular to intergranular SCC fracture mode. The cyclic CGRs of cold-rolled Alloy 690 showed significant environmental enhancement, while those for Alloy 152 were minimal. Both materials exhibited SCC of 10{sup -11} m/s under constant loading at moderate stress intensity factors. The paper also presents tensile property data for Alloy 690TT and Alloy 152 weld in the temperature range 25--870 C.

  4. Pressure vessel fracture studies pertaining to the PWR thermal-shock issue: experiment TSE-7

    SciTech Connect

    Cheverton, R.D.; Ball, D.G.; Bolt, S.E.; Iskander, S.K.; Nanstad, R.K.

    1985-08-01

    Thermal-shock experiment TSE-7 was conducted for the purpose of investigating the behavior of surface flaws under pressurized-water reactor (PWR) overcooling-accident conditions. This experiment was the eighth in a series of thermal-shock experiments conducted for this purpose with large steel cylinders (A 508, class-2 chemistry; 991-mm OD x 152-mm wall x 1.2-m length) as a part of the Heavy-Section Steel Technology (HSST) Program. The initial flaw for TSE-7 was a shallow, semielliptical, inner-surface, axially oriented, sharp crack located at midlength of the test cylinder. The thermal shock was applied to the inner surface only, and this was accomplished by effectively dunking the test cylinder, initially at approx.93/sup 0/C, into a large volume of liquid nitrogen. The specific purpose of TSE-7 was to determine whether, in agreement with analysis, a short and shallow surface flaw, in the absence of cladding, would extend on the surface to effectively become a very long flaw as a result of severe thermal-shock loading. During the experiment, there were three major initiation-arrest events. The first event consisted of some radial propagation and very extensive surface extension, with many bifurcations taking place. The second and third events consisted primarily of radial propagation. A fourth initiation event was prevented by warm prestressing. These results were in good agreement with predictions. 50 refs., 77 figs., 13 tabs.

  5. LBB evaluation for a typical Japanese PWR primary loop by using the US NRC approved methods

    SciTech Connect

    Swamy, S.A.; Bhowmick, D.C.; Prager, D.E.

    1997-04-01

    The regulatory requirements for postulated pipe ruptures have changed significantly since the first nuclear plants were designed. The Leak-Before-Break (LBB) methodology is now accepted as a technically justifiable approach for eliminating postulation of double-ended guillotine breaks (DEGB) in high energy piping systems. The previous pipe rupture design requirements for nuclear power plant applications are responsible for all the numerous and massive pipe whip restraints and jet shields installed for each plant. This results in significant plant congestion, increased labor costs and radiation dosage for normal maintenance and inspection. Also the restraints increase the probability of interference between the piping and supporting structures during plant heatup, thereby potentially impacting overall plant reliability. The LBB approach to eliminate postulating ruptures in high energy piping systems is a significant improvement to former regulatory methodologies, and therefore, the LBB approach to design is gaining worldwide acceptance. However, the methods and criteria for LBB evaluation depend upon the policy of individual country and significant effort continues towards accomplishing uniformity on a global basis. In this paper the historical development of the U.S. LBB criteria will be traced and the results of an LBB evaluation for a typical Japanese PWR primary loop applying U.S. NRC approved methods will be presented. In addition, another approach using the Japanese LBB criteria will be shown and compared with the U.S. criteria. The comparison will be highlighted in this paper with detailed discussion.

  6. U.S. Marine Corps Base Camp Pendleton: Using The Sun For Hot Water And Electricity, Federal Energy Management Program (FEMP) (Fact Sheet)

    SciTech Connect

    Not Available

    2009-09-01

    Case study overview of integrated solar hot water/photovoltaic systems at the U.S. Marine Corps Camp Pendleton training pools.

  7. US Synthetic Corp (TRL 4 Component)- The Development of Open, Water Lubricated Polycrystalline Diamond Thrust Bearings for use in Marine Hydrokinetic (MHK) Energy Machines

    Energy.gov [DOE]

    US Synthetic Corp (TRL 4 Component) - The Development of Open, Water Lubricated Polycrystalline Diamond Thrust Bearings for use in Marine Hydrokinetic (MHK) Energy Machines

  8. CEPAN method of analyzing creep collapse of oval cladding. Volume 5. Evaluation of interpellet gap formation and clad collapse in modern PWR fuel rods

    SciTech Connect

    Adams, W.M.; Fisher, H.D.; Litke, H.J.; Mordarski, W.J.

    1985-04-01

    This report presents the results from a review of interpellet-gap formation, ovality, creepdown and clad collapse data in modern PWR fuel rods. Conclusions are reached regarding the propensity of modern PWR fuel to form such gaps and to undergo clad collapse. CEPAN, a creep-collapse predictor approved by the NRC in 1976, has been reformulated to include the creep analysis of cladding with finite interpellet gaps. The basis for this reformulation is discussed in detail. The model previously used in the calculation of the augmentation factor, a peak linear heat rate penalty due to the presence of interpellet gaps within the fuel rod, has been modified to incorporate gap-formation statistics from modern fuel. Finnally, the benefits of the limited gap formation and the CEPAN reformulation for the licensing of modern PWR fuel rods are evaluated.

  9. Implementation Approach for Electric Vehicles at Marine Corps Base Camp Lejeune. Task 4

    SciTech Connect

    Schey, Stephen; Francfort, Jim

    2015-11-01

    Battelle Energy Alliance, LLC, managing and operating contractor for the U.S. Department of Energy’s Idaho National Laboratory, is the lead laboratory for U.S. Department of Energy Advanced Vehicle Testing. Battelle Energy Alliance, LLC contracted with Intertek Testing Services, North America (Intertek) to conduct several U.S. Department of Defense base studies to identify potential U.S. Department of Defense transportation systems that are strong candidates for introduction or expansion of plug-in electric vehicles (PEVs). This study is focused on the Marine Corps Base Camp Lejeune (MCBCL) located in North Carolina. Task 1 consisted of a survey of the non-tactical fleet of vehicles at MCBCL to begin the review of vehicle mission assignments and types of vehicles in service. In Task 2, daily operational characteristics of vehicles were identified to select vehicles for further monitoring and attachment of data loggers. Task 3 recorded vehicle movements in order to characterize the vehicles’ missions. The results of the data analysis and observations were provided. Individual observations of the selected vehicles provided the basis for recommendations related to PEV adoption, i.e., whether a battery electric vehicle (BEV) or plug-in hybrid electric vehicle (PHEV) (collectively PEVs) can fulfill the mission requirements. It also provided the basis for recommendations related to placement of PEV charging infrastructure. This report focuses on an implementation plan for the near-term adoption of PEVs into the MCBCL fleet. Intertek acknowledges the support of Idaho National Laboratory, Marine Corps headquarters, and Marine Corps Base Camp Lejeune fleet management and personnel for participation in this study. Intertek is pleased to provide this report and is encouraged by enthusiasm and support from MCBCL personnel.

  10. Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment and Recommendations

    SciTech Connect

    Burman, K.; Kandt, A.; Lisell, L.; Booth, S.; Walker, A.; Roberts, J.; Falcey, J.

    2011-11-01

    DOD's U.S. Pacific Command has partnered with the U.S. Department of Energy's (DOE) National Renewable Energy Laboratory (NREL) to assess opportunities for increasing energy security through renewable energy and energy efficiency in Hawaii installations. NREL selected Marine Corps Base Hawaii (MCBH), Kaneohe Bay to receive technical support for net zero energy assessment and planning funded through the Hawaii Clean Energy Initiative (HCEI). NREL performed a comprehensive assessment to appraise the potential of MCBH Kaneohe Bay to achieve net zero energy status through energy efficiency, renewable energy, and electric vehicle integration. This report summarizes the results of the assessment and provides energy recommendations.

  11. On-line PWR RHR pump performance testing following motor and impeller replacement

    SciTech Connect

    DiMarzo, J.T.

    1996-12-01

    On-line maintenance and replacement of safety-related pumps requires the performance of an inservice test to determine and confirm the operational readiness of the pumps. In 1995, major maintenance was performed on two Pressurized Water Reactor (PWR) Residual Heat Removal (RHR) Pumps. A refurbished spare motor was overhauled with a new mechanical seal, new motor bearings and equipped with pump`s `B` impeller. The spare was installed into the `B` train. The motor had never been run in the system before. A pump performance test was developed to verify it`s operational readiness and determine the in-situ pump performance curve. Since the unit was operating, emphasis was placed on conducting a highly accurate pump performance test that would ensure that it satisfied the NSSS vendors accident analysis minimum acceptance curve. The design of the RHR System allowed testing of one train while the other was aligned for normal operation. A test flow path was established from the Refueling Water Storage Tank (RWST) through the pump (under test) and back to the RWST. This allowed staff to conduct a full flow range pump performance test. Each train was analyzed and an expression developed that included an error vector term for the TDH (ft), pressure (psig), and flow rate (gpm) using the variance error vector methodology. This method allowed the engineers to select a test instrumentation system that would yield accurate readings and minimal measurement errors, for data taken in the measurement of TDH (P,Q) versus Pump Flow Rate (Q). Test results for the `B` Train showed performance well in excess of the minimum required. The motor that was originally in the `B` train was similarly overhauled and equipped with `A` pump`s original impeller, re-installed in the `A` train, and tested. Analysis of the `A` train results indicate that the RHR pump`s performance was also well in excess of the vendors requirements.

  12. Analyses of High Pressure Molten Debris Dispersion for a Typical PWR Plant

    SciTech Connect

    Osamu KAawabata; Mitsuhiro Kajimoto [Japan Nuclear Energy Safety Organization (Japan)

    2006-07-01

    In such severe core damage accident, as small LOCAs with no ECCS injection or station blackout, in which the primary reactor system remains pressurized during core melt down, certain modes of vessel failure would lead to a high pressure ejection of molten core material. In case of a local failure of the lower head, the molten materials would initially be ejected into the cavity beneath the pressure vessel may subsequently be swept out from the cavity to the containment atmosphere and it might cause the early containment failure by direct contact of containment steel liner with core debris. When the contribution of a high-pressure scenario in a core damage frequency increases, early conditional containment failure probability may become large. In the present study, the verification analysis of PHOENICS code and the combining analysis with MELCOR and PHOENICS codes were performed to examine the debris dispersion behavior during high pressure melt ejection. The PHOENICS code which can treat thermal hydraulic phenomena, was applied to the verification analysis for melt dispersion experiments conducted by the Purdue university in the United States. A low pressure melt dispersion experiment at initial pressure 1.4 MPas used metal woods as a molten material was simulated. The analytical results with molten debris dispersion mostly from the model reactor cavity compartment showed an agreement with the experimental result, but the analysis result of a volumetric median diameter of the airborne debris droplets was estimated about 1.5 times of the experimental result. The injection rates of molten debris and steam after reactor vessel failure for a typical PWR plant were analyzed using the MELCOR code. In addition, PHOENICS was applied to a 3D analysis for debris dispersion with low primary pressure at the reactor vessel failure. The analysis result showed that almost all the molten debris were dispersed from the reactor vessel cavity compartment by about 45 seconds after the

  13. Radionuclide release from PWR fuels in a reference tuff repository groundwater

    SciTech Connect

    Wilson, C.N.; Oversby, V.M.

    1985-03-01

    The Nevada Nuclear Waste Storage Investigations Project (NNWSI) is studying the suitability of the welded devitrified Topopah Spring tuff at Yucca Mountain, Nye County, Nevada, for potential use as a high-level nuclear waste repository. In support of the Waste Package task of NNWSI, tests have been conducted under ambient air environment to measure radionuclide release from two pressurized water reactor (PWR) spent fuels in water obtained from the J-13 well near the Yucca Mountain site. Four specimen types, representing a range of fuel physical conditions that may exist in a failed waste canister containing a limited amount of water were tested. The specimen types were: fuel rod sections split open to expose bare fuel particles; rod sections with water-tight end fittings with a 2.5-cm long by 150-{mu}m wide slit through the cladding; rod sections with water-tight end fittings and two 200-{mu}m-diameter holes through the cladding; and undefected rod segments with water-tight end fittings. Radionuclide release results from the first 223-day test runs on H.B. Robinson spent fuel specimens in J-13 water are reported and compared to results from a previous test series in which similar Turkey Point reactor spent fuel specimens were tested on deionized water. Selected initial results are also given for Turkey Point fuel specimens tested on J-13 water. Results suggest that the actinides Pu, Am, Cm and Np are released congruently with U as the UO{sub 2} spent fuel matrix dissolves. Fractional release of {sup 137}Cs and {sup 99}Tc was greater than that measured for the actinides. Generally, lower radionuclide releases were measured for the H.B. Robinson fuel in J-13 water than for Turkey Point Fuel in deionized water. 8 references, 7 figures, 9 tables.

  14. Severe accident modeling of a PWR core with different cladding materials

    SciTech Connect

    Johnson, S. C.; Henry, R. E.; Paik, C. Y.

    2012-07-01

    The MAAP v.4 software has been used to model two severe accident scenarios in nuclear power reactors with three different materials as fuel cladding. The TMI-2 severe accident was modeled with Zircaloy-2 and SiC as clad material and a SBO accident in a Zion-like, 4-loop, Westinghouse PWR was modeled with Zircaloy-2, SiC, and 304 stainless steel as clad material. TMI-2 modeling results indicate that lower peak core temperatures, less H 2 (g) produced, and a smaller mass of molten material would result if SiC was substituted for Zircaloy-2 as cladding. SBO modeling results indicate that the calculated time to RCS rupture would increase by approximately 20 minutes if SiC was substituted for Zircaloy-2. Additionally, when an extended SBO accident (RCS creep rupture failure disabled) was modeled, significantly lower peak core temperatures, less H 2 (g) produced, and a smaller mass of molten material would be generated by substituting SiC for Zircaloy-2 or stainless steel cladding. Because the rate of SiC oxidation reaction with elevated temperature H{sub 2}O (g) was set to 0 for this work, these results should be considered preliminary. However, the benefits of SiC as a more accident tolerant clad material have been shown and additional investigation of SiC as an LWR core material are warranted, specifically investigations of the oxidation kinetics of SiC in H{sub 2}O (g) over the range of temperatures and pressures relevant to severe accidents in LWR 's. (authors)

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

    SciTech Connect

    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.

  16. In-pile post-DNB behavior of a nine-rod PWR-type fuel bundle

    SciTech Connect

    Gunnerson, F.S.; MacDonald, P.E.

    1980-01-01

    The results of an in-pile power-cooling-mismatch (PCM) test designed to investigate the behavior of a nine-rod, PWR-type fuel bundle under intermittent and sustained periods of high temperature film boiling operation are presented. Primary emphasis is placed on the DNB and post-DNB events including rod-to-rod interactions, return to nucleate boiling (RNB), and fuel rod failure. A comparison of the DNB behavior of the individual bundle rods with single-rod data obtained from previous PCM tests is also made.

  17. Containment pressurization and burning of combustible gases in a large, dry PWR containment during a station blackout sequence

    SciTech Connect

    Lee, M.; Fan, C.T. (National Tsing-Hua Univ., Dept. of Nuclear Engineering, Hsinchu (TW))

    1992-07-01

    In this paper, responses of a large, dry pressurized water reactor (PWR) containment in a station blackout sequence are analyzed with the CONTAIN, MARCH3, and MAAP codes. Results show that the predicted containment responses in a station blackout sequence of these three codes are substantially different. Among these predictions, the MAAP code predicts the highest containment pressure because of the large amount of water made available to quench the debris upon vessel failure. The gradual water boiloff by debris pressurizes the containment. The combustible gas burning models in these codes are briefly described and compared.

  18. ORDNANCE CORPS

    Office of Legacy Management (LM)

    Philip A. Krilln, Rwident of the Maudaotnriug Ldmatorier, Ino. lb sp mteriel dll be eblpped to the lienufwtur Laboratoriel3, Inc., untAl web time w pemiee%en ta do w ie received ...

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

    SciTech Connect

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

    1983-01-01

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

  20. Experiment data report for LOFT large-break loss-of-coolant experiment L2-5. [PWR

    SciTech Connect

    Bayless, P.D.; Divine, J.M.

    1982-08-01

    Selected pertinent and uninterpreted data from the third nuclear large break loss-of-coolant experiment (Experiment L2-5) conducted in the Loss-of-Fluid Test (LOFT) facility are presented. The LOFT facility is a 50-MW(t) pressurized water reactor (PWR) system with instruments that measure and provide data on the system thermal-hydraulic and nuclear conditions. The operation of the LOFT system is typical of large (approx. 1000 MW(e)) commercial PWR operations. Experiment L2-5 simulated a double-ended offset shear of a cold leg in the primary coolant system. The primary coolant pumps were tripped within 1 s after the break initiation, simulating a loss of site power. Consistent with the loss of power, the starting of the high- and low-pressure injection systems was delayed. The peak fuel rod cladding temperature achieved was 1078 +- 13 K. The emergency core cooling system re-covered the core and quenched the cladding. No evidence of core damage was detected.

  1. Impact of fuel cladding failure events on occupational radiation exposures at nuclear power plants. Case study: PWR during routine operations

    SciTech Connect

    Moeller, M.P.; Martin, G.F.; Haggard, D.L.

    1986-01-01

    The purpose of this report is to present data in support of evaluating the impact of fuel cladding failure events on occupational radiation exposure. To determine quantitatively whether fuel cladding failure contributes significantly to occupational radiation exposure, radiation exposure measurements were taken at comparable locations in two mirror-image pressurized-water reactors (PWRs) and their common auxiliary building. One reactor, Unit B, was experiencing degraded fuel characterized as 0.125% fuel pin-hole leakers and was operating at approximately 55% of the reactor's licensed maximum core power, while the other reactor, Unit A, was operating under normal conditions with less than 0.01% fuel pin-hole leakers at 100% of the reactor's licensed maximum core power. Measurements consisted of gamma spectral analyses, radiation exposure rates and airborne radionuclide concentrations. In addition, data from primary coolant sample results for the previous 20 months on both reactor coolant systems were analyzed. The results of the measurements and coolant sample analyses suggest that a 3560-megawatt-thermal (1100 MWe) PWR operating at full power with 0.125% failed fuel can experience an increase of 540% in radiation exposure rates as compared to a PWR operating with normal fuel. In specific plant areas, the degraded fuel may elevate radiation exposure rates even more.

  2. LOFTRAN/RETRAN comparison calculations for a postulated loss-of-feedwater ATWS in the Sizewell 'B' PWR

    SciTech Connect

    Papez, K.L.; Risher, D.H.

    1983-05-01

    The loss-of-main-feedwater transient without reactor trip (scram) has received particular attention in pressurized water reactor (PWR) anticipated transient without scram (ATWS) analysis primarily due to the potential for reactor coolant system over pressurization. To assist in the licensing of the U.K. PWR, Sizewell 'B', comparative calculations of a loss-of-feedwater ATWS have been performed using the Westinghouse-developed LOFTRAN loop analysis code and the Electric Power Research Institute/ Energy Incorporated-developed RETRAN-01 code. The calculations were performed with and without the emergency boration system (EBS), which is included in the Sizewell reference design. Initial results showed good agreement between the codes for the major features of the transient, but also a time shift in the transient profiles at the time of the pressurizer pressure peak. This was found to be due to differences in the steam generator modeling, which resulted in a difference in the onset of the very rapid degradation in heat transfer as the steam generators approach dryout. When the same model was used in both codes, very good agreement was obtained. Remaining differences in the results are attributed primarily to differences in the boron injection models, which resulted in an over-prediction of the core boron concentration in the RETRAN calculation. The results with an EBS indicate that the peak pressurizer pressure is relatively insensitive to variations in modeling.

  3. In-Vessel Retention of Molten Core Debris in the Westinghouse AP1000 Advanced Passive PWR

    SciTech Connect

    Scobel, James H.; Conway, L.E.; Theofanous, T.G.

    2002-07-01

    In-vessel retention (IVR) of molten core debris via external reactor vessel cooling is the hallmark of the severe accident management strategies in the AP600 passive PWR. The vessel is submerged in water to cool its external surface via nucleate boiling heat transfer. An engineered flow path through the reactor vessel insulation provides cooling water to the vessel surface and vents steam to promote IVR. For the 600 MWe passive plant, the predicted heat load from molten debris to the lower head wall has a large margin to the critical heat flux on the external surface of the vessel, which is the upper limit of the cooling capability. Up-rating the power of the passive plant from 600 to 1000 MWe (AP1000) significantly increases the heat loading from the molten debris to the reactor vessel lower head in the postulated bounding severe accident sequence. To maintain a large margin to the coolability limit for the AP1000, design features and severe accident management (SAM) strategies to increase the critical heat flux on the external surface of the vessel wall need to be implemented. A test program at the ULPU facility at University of California Santa Barbara (UCSB) has been initiated to investigate design features and SAM strategies that can enhance the critical heat flux. Results from ULPU Configuration IV demonstrate that with small changes to the ex-vessel design and SAM strategies, the peak critical heat flux in the AP1000 can be increased at least 30% over the peak critical heat flux predicted for the AP600 configuration. The design and SAM strategy changes investigated in ULPU Configuration IV can be implemented in the AP1000 design and will allow the passive plant to maintain the margin to critical heat flux for IVR, even at the higher power level. Continued testing for IVR phenomena is being performed at UCSB to optimize the AP1000 design and to ensure that vessel failure in a severe accident is physically unreasonable. (authors)

  4. Fuel Assembly Shaker Test for Determining Loads on a PWR Assembly under Surrogate Normal Conditions of Truck Transport R0.1

    Energy.gov [DOE]

    Results of testing employing surrogate instrumented rods (non-high-burnup, 17 x 17 PWR fuel assembly) to capture the response to the loadings experienced during normal conditions of transport indicate that strain- or stress-based failure of fuel rods seems unlikely; performance of high-burnup fuels continues to be assessed.

  5. Cooperative Research between NREL and Solar Junction Corp: Cooperative Research and Development Final Report, CRADA Number CRD-08-306

    SciTech Connect

    Friedman, D.

    2015-03-01

    NREL and Solar Junction Corp. will perform cooperative research on materials and devices that are alternatives to standard approaches with the goal of improving solar cell efficiency while lowering cost. The general purpose of this work is to model the performance of a multi-junction concentrator cell of Solar Junction, Inc. design under normal concentrator operating conditions.

  6. Assessment of Charging Infrastructure for Plug-in Electric Vehicles at Marine Corps Base Camp Lejeune. Task 3

    SciTech Connect

    Schey, Stephen; Francfort, Jim

    2015-11-01

    Battelle Energy Alliance, LLC, managing and operating contractor for the U.S. Department of Energy’s Idaho National Laboratory, is the lead laboratory for the U.S. Department of Energy’s advanced vehicle testing. Battelle Energy Alliance, LLC contracted with Intertek Testing Services, North America (Intertek) to conduct several U.S. Department of Defense-based studies to identify potential U.S. Department of Defense transportation systems that are strong candidates for introduction or expansion of plug-in electric vehicles (PEVs). Task 1 consisted of a survey of the non-tactical fleet of vehicles at Marine Corps Base Camp Lejeune to begin the review of vehicle mission assignments and types of vehicles in service. Task 2 selected vehicles for further monitoring and involved identifying daily operational characteristics of these select vehicles. Data logging of vehicle movements was initiated in order to characterize the vehicle’s mission. The Task 3 vehicle utilization report provided results of the data analysis and observations related to the replacement of current vehicles with PEVs. Finally, this report provides an assessment of charging infrastructure required to support the suggested PEV replacements. Intertek acknowledges the support of Idaho National Laboratory, Marine Corps headquarters, and Marine Corps Base Camp Lejeune Fleet management and personnel for participation in this study. Intertek is pleased to provide this report and is encouraged by enthusiasm and support from Marine Corps Base Camp Lejeune personnel.

  7. Electric Vehicle Preparedness: Task 1, Assessment of Fleet Inventory for Marine Corps Base Camp Lejeune

    SciTech Connect

    Schey, Stephen; Francfort, Jim

    2015-01-01

    Several U.S. Department of Defense-based studies were conducted to identify potential U.S. Department of Defense transportation systems that are strong candidates for introduction or expansion of plug-in electric vehicles (PEVs). Task 1 included a survey of the inventory of non-tactical fleet vehicles at the Marine Corps Base Camp Lejeune (MCBCL) to characterize the fleet. This information and characterization will be used to select vehicles for monitoring that takes place during Task 2. This monitoring involves data logging of vehicle operation in order to identify the vehicle’s mission and travel requirements. Individual observations of these selected vehicles provide the basis for recommendations related to PEV adoption. It also identifies whether a battery electric vehicle or plug-in hybrid electric vehicle (collectively referred to as PEVs) can fulfill the mission requirements and provides observations related to placement of PEV charging infrastructure.

  8. Utilization Assessment of Target Electrification Vehicles at Marine Corps Base Camp Lejeune. Task 3

    SciTech Connect

    Schey, Stephen; Francfort, Jim

    2015-11-01

    Battelle Energy Alliance, LLC, managing and operating contractor for the U.S. Department of Energy’s Idaho National Laboratory, is the lead laboratory for U.S. Department of Energy Advanced Vehicle Testing. Battelle Energy Alliance, LLC contracted with Intertek Testing Services, North America (Intertek) to conduct several U.S. Department of Defense base studies to identify potential U.S. Department of Defense transportation systems that are strong candidates for introduction or expansion of plug-in electric vehicles (PEVs). Task 1 consisted of a survey of the non-tactical fleet of vehicles at MCBCL to begin the review of vehicle mission assignments and types of vehicles in service. Task 2 involved identifying daily operational characteristics of select vehicles and initiating data logging of vehicle movements in order to characterize the vehicle’s mission. Individual observations of these selected vehicles provide the basis for recommendations related to PEV adoption and whether a battery electric vehicle or plug-in hybrid electric vehicle (collectively referred to as PEVs) can fulfill the mission requirements and provide observations related to placement of PEV charging infrastructure. This report provides the results of the data analysis and observations related to replacement of current vehicles with PEVs. This fulfills part of the Task 3 requirements. Task 3 also includes an assessment of the charging infrastructure required to support this replacement, which is the subject of a separate report. Intertek acknowledges the support of Idaho National Laboratory, Marine Corps headquarters, and Marine Corps Base Camp Lejeune Fleet management and personnel for participation in this study. Intertek is pleased to provide this report and is encouraged by enthusiasm and support from MCBCL personnel.

  9. Targeting Net Zero Energy at Marine Corps Base Hawaii, Kaneohe Bay: Preprint

    SciTech Connect

    Burman, K.; Kandt, A.; Lisell, L.; Booth, S.

    2012-05-01

    This paper summarizes the results of an NREL assessment of Marine Corps Base Hawaii (MCBH), Kaneohe Bay to appraise the potential of achieving net zero energy status through energy efficiency, renewable energy, and hydrogen vehicle integration. In 2008, the U.S. Department of Defense's U.S. Pacific Command partnered with the U.S. Department of Energy's (DOE's) National Renewable Energy Laboratory (NREL) to assess opportunities for increasing energy security through renewable energy and energy efficiency at Hawaii military installations. DOE selected Marine Corps Base Hawaii (MCBH), Kaneohe Bay, to receive technical support for net zero energy assessment and planning funded through the Hawaii Clean Energy Initiative (HCEI). NREL performed a comprehensive assessment to appraise the potential of MCBH Kaneohe Bay to achieve net zero energy status through energy efficiency, renewable energy, and hydrogen vehicle integration. This paper summarizes the results of the assessment and provides energy recommendations. The analysis shows that MCBH Kaneohe Bay has the potential to make significant progress toward becoming a net zero installation. Wind, solar photovoltaics, solar hot water, and hydrogen production were assessed, as well as energy efficiency technologies. Deploying wind turbines is the most cost-effective energy production measure. If the identified energy projects and savings measures are implemented, the base will achieve a 96% site Btu reduction and a 99% source Btu reduction. Using excess wind and solar energy to produce hydrogen for a fleet and fuel cells could significantly reduce energy use and potentially bring MCBH Kaneohe Bay to net zero. Further analysis with an environmental impact and interconnection study will need to be completed. By achieving net zero status, the base will set an example for other military installations, provide environmental benefits, reduce costs, increase energy security, and exceed its energy goals and mandates.

  10. Ashland oil, Inc. v. Sonford Products Corp., Kelley v. Tiscornia, and United States v. Fleet Factors Corp.: Upholding EPA`s lender liability rule

    SciTech Connect

    Evans, W.D. Jr.

    1993-12-31

    John Grisham`s novel The Firm relates the story of Mitchell McDeere, a young law school graduate who believes that he is joining a {open_quotes}white shoe{close_quotes} Memphis, Tennessee, firm but discovers that the firm is controlled by the Mob. A similar, but different, {open_quotes}surprise{close_quotes} has befallen banks as a result of toxic waste cleanup cost claims. When the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA or Superfund) was passed in 1980, banks had no cause for alarm because the Act provided an exemption from its ownership-based liability for any lender holding {open_quotes}indicia of ownership primarily to protect his security interest{close_quotes} in a hazardous waste facility. Based on the statutory language, it seemed reasonably clear that Congress did not intend to impose liability on secured creditors merely for securing a debt with a deed of trust or mortgage. Unfortunately, lender liability for CERCLA claims arose in the mid-1980s out of two lower federal court decisions and the Eleventh Circuit`s controversial, to say the least, 1990 decision in United States v. Fleet Factors Corp (Fleet Factors II). The major issues currently confronting lenders under CERCLA are (1) the extent to which a secured creditor may involve itself in the debtor`s operations, especially during a loan workout program, without becoming liable for cleanup costs as a CERCLA {open_quotes}owner or operator{close_quotes} and (2) whether a lender who forecloses on collateral and takes title is liable under CERCLA. 94 refs.

  11. PWR core design, neutronics evaluation and fuel cycle analysis for thorium-uranium breeding recycle

    SciTech Connect

    Bi, G.; Liu, C.; Si, S.

    2012-07-01

    This paper was focused on core design, neutronics evaluation and fuel cycle analysis for Thorium-Uranium Breeding Recycle in current PWRs, without any major change to the fuel lattice and the core internals, but substituting the UOX pellet with Thorium-based pellet. The fuel cycle analysis indicates that Thorium-Uranium Breeding Recycle is technically feasible in current PWRs. A 4-loop, 193-assembly PWR core utilizing 17 x 17 fuel assemblies (FAs) was taken as the model core. Two mixed cores were investigated respectively loaded with mixed reactor grade Plutonium-Thorium (PuThOX) FAs and mixed reactor grade {sup 233}U-Thorium (U{sub 3}ThOX) FAs on the basis of reference full Uranium oxide (UOX) equilibrium-cycle core. The UOX/PuThOX mixed core consists of 121 UOX FAs and 72 PuThOX FAs. The reactor grade {sup 233}U extracted from burnt PuThOX fuel was used to fabrication of U{sub 3}ThOX for starting Thorium-. Uranium breeding recycle. In UOX/U{sub 3}ThOX mixed core, the well designed U{sub 3}ThOX FAs with 1.94 w/o fissile uranium (mainly {sup 233}U) were located on the periphery of core as a blanket region. U{sub 3}ThOX FAs remained in-core for 6 cycles with the discharged burnup achieving 28 GWD/tHM. Compared with initially loading, the fissile material inventory in U{sub 3}ThOX fuel has increased by 7% via 1-year cooling after discharge. 157 UOX fuel assemblies were located in the inner of UOX/U{sub 3}ThOX mixed core refueling with 64 FAs at each cycle. The designed UOX/PuThOX and UOX/U{sub 3}ThOX mixed core satisfied related nuclear design criteria. The full core performance analyses have shown that mixed core with PuThOX loading has similar impacts as MOX on several neutronic characteristic parameters, such as reduced differential boron worth, higher critical boron concentration, more negative moderator temperature coefficient, reduced control rod worth, reduced shutdown margin, etc.; while mixed core with U{sub 3}ThOX loading on the periphery of core has no

  12. Simulation of German PKL refill/reflood experiment K9A using RELAP4/MOD7. [PWR

    SciTech Connect

    Hsu, M.T.; Davis, C.B.; Behling, S.R.

    1981-11-01

    This paper describes a RELAP4/MOD7 simulation of West Germany's Kraftwerk Union (KWU) Primary Coolant Loop (PKL) refill/reflood experiment K9A. RELAP4/MOD7, a best-estimate computer program for the calculation of thermal and hydraulic phenomena in a nuclear reactor or related system, is the latest version in the RELAP4 code development series. This study was the first major simulation using RELAP4/MOD7 since its release by the Idaho National Engineering Laboratory (INEL). The PKL facility is a reduced scale (1:134) representation of a typical West German four-loop 1300 MW pressurized water reactor (PWR). A prototypical scale of the total volume to power ratio was maintained. The test facility was designed specifically for an experiment simulating the refill/reflood phase of a Loss-of-Coolant Accident (LOCA).

  13. Development code for sensitivity and uncertainty analysis of input on the MCNPX for neutronic calculation in PWR core

    SciTech Connect

    Hartini, Entin Andiwijayakusuma, Dinan

    2014-09-30

    This research was carried out on the development of code for uncertainty analysis is based on a statistical approach for assessing the uncertainty input parameters. In the butn-up calculation of fuel, uncertainty analysis performed for input parameters fuel density, coolant density and fuel temperature. This calculation is performed during irradiation using Monte Carlo N-Particle Transport. The Uncertainty method based on the probabilities density function. Development code is made in python script to do coupling with MCNPX for criticality and burn-up calculations. Simulation is done by modeling the geometry of PWR terrace, with MCNPX on the power 54 MW with fuel type UO2 pellets. The calculation is done by using the data library continuous energy cross-sections ENDF / B-VI. MCNPX requires nuclear data in ACE format. Development of interfaces for obtaining nuclear data in the form of ACE format of ENDF through special process NJOY calculation to temperature changes in a certain range.

  14. Impact Analysis of a Dipper-Type and Multi Spring-Type Fuel Rod Support Grid Assemblies in PWR

    SciTech Connect

    Song, K.N.; Yoon, K.H.; Park, K.J.; Park, G.J.; Kang, B.S.

    2002-07-01

    A spacer grid is one of the main structural components in a fuel assembly of a Pressurized light Water Reactor (PWR). It supports fuel rods, guides cooling water, and maintains geometry from external impact loads. A simulation is performed for the strength of a spacer grid under impact load. The critical impact load that leads to plastic deformation is identified by a free-fall test. A finite element model is established for the nonlinear simulation of the test. The simulation model is tuned based on the free-fall test. The model considers the aspects of welding and the contacts between components. Nonlinear finite element analysis is carried out by a software system called LS/DYNA3D. The results are discussed from a design viewpoint. (authors)

  15. The influence of dissolved hydrogen on primary water stress corrosion cracking of Alloy 600 at PWR steam generator operating temperatures

    SciTech Connect

    Jacko, R.J.; Economy, G.; Pement, F.W.

    1992-12-31

    PWR primary coolant chemistry uses an intentional dissolved hydrogen concentration of 20 to 50 ml (STP)/kg of water to effect a net suppression of oxygen-producing radiolysis, to minimize corrosion in primary loop materials and to maintain a low redox potential. Speculation has attended a possible influence of dissolved hydrogen on the kinetics of initiation of Primary Water Stress Corrosion Cracking (PWSCC) behavior of Alloy 600 steam generator tubing. Three series of experiments are presented for conditions in which the level of dissolved hydrogen was intentionally varied over the hydrogen and temperature ranges of interest for steam generator operation. No significant effect of dissolved hydrogen was found on PWSCC of Alloy 600.

  16. Determination of the threshold values for corrosion fatigue crack growth rate of pressure vessel steels in PWR primary water

    SciTech Connect

    Haenninen, H.E.; Arilahti, E.; Ehrnsten, U.

    1992-12-31

    Corrosion fatigue crack growth rates over a range of frequencies from 10 Hz to 0.00001 Hz in two materials that have exhibited low-rate (A508 Class 3) and high-rate (A533B) crack growth behaviour at 288{degrees}C were studied at 200{degrees}C in PWR primary water. The frequency values above which marked environmental enhancement was observed were determined. Also the threshold values in terms of {Delta}K{sub th}, above which the marked environmental enhancement was observed in the crack growth rate, were determined both for A533B steel and Soviet pressure vessel steels with certain test parameters. Based on the extensive fractography the crack growth rate results are discussed mechanistically.

  17. The toughness of irradiated pressure water reactor (PWR) vessel shell rings and the effect of segregation zones

    SciTech Connect

    Bethmont, M.; Frund, J.M.; Housin, B.; Soulat, P.

    1996-12-31

    To establish the integrity of pressure water reactor (PWR) vessels it is necessary to determine the toughness of A508Cl.3 steel at the end of its life, that is after thermal aging and irradiation embrittlement. In safety analyses the toughness can be deduced from a reference curve set forth in the code (ASME or RCC-M). The validity of the reference curve has been verified for several years for unirradiated French reactor vessels. Tests were performed on specimens taken from materials having heterogeneities in chemical composition. For most of the test results the reference curve is a lower bound. To solve te problem of determining the toughness of SA 508 Cl.3 steel after irradiation and in the presence of possible heterogeneities, the toughness results were gathered. The synthesis shows that the RCC-M code curve is conservative.

  18. Safety and licensing issues that are being addressed by the Power Burst Facility test programs. [PWR; BWR

    SciTech Connect

    McCardell, R.K.; MacDonald, P.E.

    1980-01-01

    This paper presents an overview of the results of the experimental program being conducted in the Power Burst Facility and the relationship of these results to certain safety and licensing issues. The safety issues that were addressed by the Power-Cooling-Mismatch, Reactivity Initiated Accident, and Loss of Coolant Accident tests, which comprised the original test program in the Power Burst Facility, are discussed. The resolution of these safety issues based on the results of the thirty-six tests performed to date, is presented. The future resolution of safety issues identified in the new Power Burst Facility test program which consists of tests which simulate BWR and PWR operational transients, anticipated transients without scram, and severe fuel damage accidents, is described.

  19. Lab-Corps: Creating Market Pathways for Laboratory Research; U.S. Department of Energy (DOE), Energy Efficiency & Renewable Energy (EERE)

    SciTech Connect

    2015-08-01

    The Lab-Corps program is a specialized training curriculum aimed at accelerating the transfer of clean energy technologies from national laboratories into the commercial marketplace. Administered by the U.S. Department of Energy’s (DOE's) Office of Energy Efficiency and Renewable Energy, Lab-Corps is a new model of engagement as a part of the Lab Impact Initiative. In addition to Lab-Corps, the Lab Impact Initiative utilizes the Small Business Voucher and Technologist-in-Residence programs to increase and enhance laboratory-private sector relationships, streamline access to national laboratory capabilities, and demonstrate the value of laboratory-developed science and technology.

  20. Chemical System Decontamination at PWR Power Stations Biblis A and B by Advanced System Decontamination by Oxidizing Chemistry (ASDOC-D) Process Technology - 13081

    SciTech Connect

    Loeb, Andreas; Runge, Hartmut; Stanke, Dieter; Bertholdt, Horst-Otto; Adams, Andreas; Impertro, Michael; Roesch, Josef

    2013-07-01

    For chemical decontamination of PWR primary systems the so called ASDOC-D process has been developed and qualified at the German PWR power station Biblis. In comparison to other chemical decontamination processes ASDOC-D offers a number of advantages: - ASDOC-D does not require separate process equipment but is completely operated and controlled by the nuclear site installations. Feeding of chemical concentrates into the primary system is done by means of the site's dosing systems. Process control is performed by standard site instrumentation and analytics. - ASDOC-D safely prevents any formation and precipitation of insoluble constituents - Since ASDOC-D is operated without external equipment there is no need for installation of such equipment in high radioactive radiation surrounding. The radioactive exposure rate during process implementation and process performance may therefore be neglected in comparison to other chemical decontamination processes. - ASDOC-D does not require auxiliary hose connections which usually bear high leakage risk. The above mentioned technical advantages of ASDOC-D together with its cost-effectiveness gave rise to Biblis Power station to agree on testing ASDOC-D at the volume control system of PWR Biblis unit A. By involving the licensing authorities as well as expert examiners into this test ASDOC-D received the official qualification for primary system decontamination in German PWR. As a main outcome of the achieved results NIS received contracts for full primary system decontamination of both units Biblis A and B (each 1.200 MW) by end of 2012. (authors)