National Library of Energy BETA

Sample records for river elec pwr

  1. East River Elec Pwr Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

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  2. East Mississippi Elec Pwr Assn | Open Energy Information

    Open Energy Info (EERE)

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  3. Singing River Elec Pwr Assn (Mississippi) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page| Open Energy Information Serbia-Enhancing Capacity forSilicium de Provence SASSinem Geothermal Power

  4. Fall River Rural Elec Coop Inc (Wyoming) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTIONRobertsdale, AlabamaETEC GmbH JumpEllenville,PowerEvaporative||NewFale-Safe, Inc JumpFall River

  5. Lumbee River Elec Member Corp | Open Energy Information

    Open Energy Info (EERE)

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

    Open Energy Info (EERE)

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

    Open Energy Info (EERE)

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  8. Prentiss County Elec Pwr Assn | Open Energy Information

    Open Energy Info (EERE)

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  9. Crawfordsville Elec, Lgt & Pwr | Open Energy Information

    Open Energy Info (EERE)

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  10. Withlacoochee River Elec Coop | Open Energy Information

    Open Energy Info (EERE)

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  11. Elec 331 -Surgical Instruments Surgical Instruments

    E-Print Network [OSTI]

    Pulfrey, David L.

    331 - Surgical Instruments 5 Annealing (Softening) · After quenching · Heat steel ­ Above Austenite arranged in a lattice · Ferrite ­ Steel · Iron Alloy ­ Fe + Other atoms ­ At least 50% Fe · Stainless steel ­ 11% to 30% Cr ­ Up to 2% C #12;Elec

  12. Northeast Missouri El Pwr Coop | Open Energy Information

    Open Energy Info (EERE)

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  13. Elec 331 -Hospital Safety Power Distribution

    E-Print Network [OSTI]

    Pulfrey, David L.

    - Hospital Safety 7 Ground Fault Interrupter Test Reset Gnd Ref Hot Ref Hot Test / Reset Relay Relay : 5 to 30 mA, Test Plug Z Downstream GFI Protection #12;Elec 331 - Hospital Safety 8 = get-out-of-jail-free card · Test it before you touch it ­ Done to code? ­ Breaker labels accurate

  14. Elec Eng 4OI6 Engineering Design

    E-Print Network [OSTI]

    Haykin, Simon

    their work in detail so as to allow another engineering graduate to follow up on the work. In additionElec Eng 4OI6 Engineering Design Course Outline: 2014/2015 Instructors: Dr. Xun Li, lixun introduces the students to basic design methodology, computer aided design (CAD) tools used in the design

  15. Elec 331 -Respiratory System Respiratory & CV Systems

    E-Print Network [OSTI]

    Pulfrey, David L.

    ) during heavy breathing Transport (Respiratory) Natural state of lung #12;Elec 331 - Respiratory System 2 - Respiratory System 4 Measurements · Composition ­ End-tidal CO2 · Volume / Capacity (CC) ­ Spirometry SRC: www.anaesthesiauk.com gas velocity ultrasonic wave velocity gV c xmit recv gV c gV cosg

  16. Unalakleet Valley Elec Coop | Open Energy Information

    Open Energy Info (EERE)

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  17. Matinicus Plantation Elec Co | Open Energy Information

    Open Energy Info (EERE)

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  18. Cumberland Elec Member Corp | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTIONRobertsdale, Alabama (Utility Company)|Alabama:Crofton,Developing andKentucky:Virginia:Elec Member

  19. Central Wisconsin Elec Coop | Open Energy Information

    Open Energy Info (EERE)

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  20. Washington Elec Member Corp | Open Energy Information

    Open Energy Info (EERE)

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  1. Waverly Municipal Elec Utility | Open Energy Information

    Open Energy Info (EERE)

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  2. Elec 331 -Bio-Potential Electrodes Review Definitions

    E-Print Network [OSTI]

    Pulfrey, David L.

    Elec 331 - Bio-Potential Electrodes 1 Review Definitions · Ion Charged particle (molecule / atom - Bio-Potential Electrodes 2 Polarizable Electrodes · No chemical reaction / electron / ion exchange minimizes motion artifact · Pull hard to remove #12;Elec 331 - Bio-Potential Electrodes 3 Non

  3. Pella Cooperative Elec Assn | Open Energy Information

    Open Energy Info (EERE)

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  4. Duck River Elec Member Corp | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTIONRobertsdale, Alabama (UtilityInstrumentsAreafor Geothermal Resources Rules

  5. South River Elec Member Corp | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page| Open Energy Information Serbia-Enhancing Capacity forSiliciumEnergyHouston, Texas:588958°,

  6. Red River Valley Rrl Elec Assn | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onRAPID/Geothermal/Exploration/Colorado <RAPID/Geothermal/WaterEnergy MarketingNewOpenRecycledMesa,

  7. Lynches River Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

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  8. Escambia River Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

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  9. Fall River Rural Elec Coop Inc | Open Energy Information

    Open Energy Info (EERE)

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  10. Raft River Rural Elec Coop Inc | Open Energy Information

    Open Energy Info (EERE)

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  11. Tallapoosa River Elec Coop Inc | Open Energy Information

    Open Energy Info (EERE)

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  12. Fall River Rural Elec Coop Inc (Montana) | Open Energy Information

    Open Energy Info (EERE)

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  13. North Georgia Elec Member Corp | Open Energy Information

    Open Energy Info (EERE)

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

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QAsource History View New PagesSustainableGlynn County, Georgia: EnergyGorlitzLedge, Michigan:River, Ohio: EnergyPwr

  15. Delaware County Elec Coop Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTIONRobertsdale, Alabama (UtilityInstruments IncMississippi: EnergyS ADehumidifiersMunicipalCounty Elec

  16. Mid-Yellowstone Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

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  17. Monroe County Elec Power Assn | Open Energy Information

    Open Energy Info (EERE)

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  18. Cooke County Elec Coop Assn | Open Energy Information

    Open Energy Info (EERE)

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  19. Coleman County Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

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  20. Columbia Basin Elec Cooperative, Inc | Open Energy Information

    Open Energy Info (EERE)

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  1. Columbia Rural Elec Assn, Inc (Oregon) | Open Energy Information

    Open Energy Info (EERE)

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  2. Comanche County Elec Coop Assn | Open Energy Information

    Open Energy Info (EERE)

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  3. Bridger Valley Elec Assn, Inc (Utah) | Open Energy Information

    Open Energy Info (EERE)

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  4. Cavalier Rural Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

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

    Open Energy Info (EERE)

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  6. Central Power Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

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  7. Central Texas Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

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  8. Chariton Valley Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

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  9. Alcorn County Elec Power Assn | Open Energy Information

    Open Energy Info (EERE)

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  10. North Arkansas Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

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  11. North Central Elec Coop, Inc (North Dakota) | Open Energy Information

    Open Energy Info (EERE)

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  12. Northeast Texas Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

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  13. Pointe Coupee Elec Member Corp | Open Energy Information

    Open Energy Info (EERE)

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  14. Public Service Elec & Gas Co | Open Energy Information

    Open Energy Info (EERE)

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  15. Rich Mountain Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop Inc Jump to:Newberg,EnergyEast Jump to: navigation,ReportVelhoMountain Elec Coop,

  16. Jefferson Davis Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LISTStar2-0057-EAInvervar Hydro Jump to: navigation,JumpIAEAPvt Ltd JAPL JumpElec

  17. Jemez Mountains Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LISTStar2-0057-EAInvervar Hydro Jump to: navigation,JumpIAEAPvt Ltd JAPLMountains Elec

  18. Tri-County Rural Elec Coop Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop IncIowa (Utility Company) Jump to: navigation,Power SystemsTri-County Rural Elec

  19. Virginia Mun Elec Assn No 1 | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop IncIowa (Utility Company)Idaho) JumpWinside, NebraskaVirginia Electric &Elec

  20. Southern Pine Elec Coop, Inc | Open Energy Information

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION JEnvironmental Jump to:EA EIS ReportEurope GmbHSolo EnergySouthSouthInformationHillsPine Elec

  1. Alaska Village Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION JEnvironmental Jump to:EAand DaltonSolarOpen5 -Telephone Co Jump to:Elec Coop, Inc Jump to:

  2. Cape Hatteras Elec Member Corp | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION JEnvironmentalBowerbank,Cammack Village, Arkansas: EnergyCounty,NewHatteras Elec Member Corp Jump

  3. Copper Valley Elec Assn, Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTIONRobertsdale, Alabama (Utility Company)| Open(Evans,Oregon: Energy Resources Jump to:NewValley Elec

  4. Central Missouri Elec Coop Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION JEnvironmentalBowerbank,CammackFLIR Jump to:RAPIDCavallo EnergyOhio:Elec Coop Inc Jump to:

  5. Central Valley Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION JEnvironmentalBowerbank,CammackFLIR Jump to:RAPIDCavallo EnergyOhio:Elec Coop Inc

  6. EnergyUnited Elec Member Corp | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoopButtePowerEdisto Electric Coop, Incsource HistoryEnergyConnectEnergyUnited Elec

  7. Bailey County Elec Coop Assn | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop IncIowaWisconsin: EnergyYorkColorado State OfficeBailey County Elec Coop Assn

  8. Wharton County Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop IncIowa (Utility Company)Idaho)VosslohWest Plains ElectricElectricCounty Elec

  9. Yazoo Valley Elec Power Assn | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop IncIowa (UtilityMichigan) Jump to: Name:XinjiangPupingYanyuanValley Elec Power

  10. Concho Valley Elec Coop Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoopButtePower Ventures JumpCommercial Jump(Thompson,InformationConcho Valley Elec

  11. Okanogan County Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIXsourceII Jump to:InformationInformation 6thOhmsett Tow TankOkanogan County Elec

  12. 1. THE RADIATION BELTS The outer zone radiation belts consist of energetic elec-

    E-Print Network [OSTI]

    Elkington, Scot R.

    1. THE RADIATION BELTS The outer zone radiation belts consist of energetic elec- trons trapped in the geomagnetic field. The dynamics of the belts are dictated by the global and local electric and mag- netic, A Review of ULF Interactions with Radiation Belt Electrons Scot R. Elkington Laboratory for Atmospheric

  13. COURSE OUTLINE FOR Elec Eng 4PL4 -Energy Systems and Management Academic

    E-Print Network [OSTI]

    Haykin, Simon

    Generation: different types of conventional power stations and related major plant; renewable sourcesCOURSE OUTLINE FOR Elec Eng 4PL4 - Energy Systems and Management Academic Year 2014-15; Term 1 to consumers, to the final supply and cost regimes for electrical energy. The design and performance of large

  14. HHH FEC Cooperation Mach Elec Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LISTStar2-0057-EA JumpDuimen River Power Co LtdGunther SpelsbergGuyana:H-DHDWHHH FEC

  15. Hamilton County Elec Coop Assn | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LISTStar2-0057-EA JumpDuimen River Power Co LtdGuntherGreen PowerHipooIAEAMember

  16. Harrison County Rrl Elec Coop | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LISTStar2-0057-EA JumpDuimen River Power Co LtdGuntherGreensHareon

  17. Heartland Rural Elec Coop, Inc | Open Energy Information

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LISTStar2-0057-EA JumpDuimen River Power CoHawaii/Incentives <Hdom

  18. Hess Retail Natural Gas and Elec. Acctg. (Connecticut) | Open Energy

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LISTStar2-0057-EA JumpDuimen River PowerHeckert BXTHengyuanUmwelt Jump to:

  19. Hess Retail Natural Gas and Elec. Acctg. (Massachusetts) | Open Energy

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LISTStar2-0057-EA JumpDuimen River PowerHeckert BXTHengyuanUmwelt Jump

  20. Howell-Oregon Elec Coop, Inc | Open Energy Information

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    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LISTStar2-0057-EA JumpDuimen RiverScoring Tool Jump to:Ethanol

  1. Horizontal Drop of 21- PWR Waste Package

    SciTech Connect (OSTI)

    A.K. Scheider

    2007-01-31

    The objective of this calculation is to determine the structural response of the waste package (WP) dropped horizontally from a specified 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. 16). AP-3.12Q, ''Calculations'' (Ref. 1 1) is used to perform the calculation and develop the document. The sketches attached to this calculation provide the potential dimensions and materials for the 21-PWR WP design.

  2. Active and Passive Elec. Comp., September 2003, Vol. 26, pp. 151166 ULTRA-LOW TEMPERATURE COEFFICIENT OF

    E-Print Network [OSTI]

    Azad, Abdul-Majeed

    Active and Passive Elec. Comp., September 2003, Vol. 26, pp. 151­166 ULTRA-LOW TEMPERATURE that this material system possessed low dielectric constant and ultra-low temperature coefficient of capacitance (TCC

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

    SciTech Connect (OSTI)

    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.

  4. Droplet generation during core reflood. [PWR

    SciTech Connect (OSTI)

    Kocamustafaogullari, G.; De Jarlais, G.; Ishii, M.

    1983-01-01

    The process of entrainment and disintegration of liquid droplets by a flow of steam has considerable practical importance in calculating the effectivenes of the emergency core cooling system. Liquid entrainment is also important in determination of the critical heat flux point in general. Thus the analysis of the reflooding phase of a LOCA requires detailed knowledge of droplet size. Droplet size is mainly determined by the droplet generation mechanisms involved. To study these mechanisms, data generated in the PWR FLECHT SEASET series of experiments was analyzed. In addition, an experiment was performed in which the hydrodynamics of low quality post-CHF flow (inverted annular flow) were simulated in an adiabatic test section.

  5. The RenewElec Project: Variable Renewable Energy and the Power System

    SciTech Connect (OSTI)

    Apt, Jay

    2014-02-14

    Variable energy resources, such as wind power, now produce about 4% of U.S. electricity. They can play a significantly expanded role if the U.S. adopts a systems approach that considers affordability, security and reliability. Reaching a 20-30% renewable portfolio standard goal is possible, but not without changes in the management and regulation of the power system, including accurately assessing and preparing for the operational effects of renewable generation. The RenewElec project will help the nation make the transition to the use of significant amounts of electric generation from variable and intermittent sources of renewable power.

  6. Hess Retail Natural Gas and Elec. Acctg. (Maine) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIXsource History View NewGuam: Energyarea, CaliforniaHess Retail Natural Gas and Elec.

  7. Fuel cycle optimization of thorium and uranium fueled PWR systems

    E-Print Network [OSTI]

    Garel, Keith Courtnay

    1977-01-01

    The burnup neutronics of uniform PWR lattices are examined with respect to reduction of uranium ore requirements with an emphasis on variation of the fuel-to-moderator ratio

  8. Turk J Elec Engin, VOL.14, NO.1 2006, c TUBITAK Computational Sciences: At the Intersection of Science

    E-Print Network [OSTI]

    Becker, Peter A.

    plants, and the testing of nuclear 1 #12;Turk J Elec Engin, VOL.14, NO.1, 2006 weapons. Both power-plant]. The simulation of these relatively large systems allows researchers to carry out "virtual experiments" that would to conduct in reality. Expanding on the theme of virtual experimentation, modern computational science

  9. Fault-Tolerance of Embedded Systems with Automotive Applications Ratnesh Kumar, Dept. of Elec. & Comp. Eng., Iowa State Univ. (ISU)

    E-Print Network [OSTI]

    Rajkumar, Ragunathan "Raj"

    Fault-Tolerance of Embedded Systems with Automotive Applications Ratnesh Kumar, Dept. of Elec of operation. New approaches are needed for fault tolerance of safety critical automotive applications. We specs to detect software (component) faults. 2. System (= software + computing-platform + plant) level

  10. ELEC0018-1 Energy markets -Assignement: Impact of a nuclear power phase-out on the electricity price.

    E-Print Network [OSTI]

    Ernst, Damien

    ELEC0018-1 Energy markets - Assignement: Impact of a nuclear power phase-out on the electricity of the energy markets in order to get a reasoned conclusion about the impact that a nuclear power phase care should be given to the following aspects: · Put the nuclear power sector into perspective

  11. PWR representative behavior during a LOCA

    SciTech Connect (OSTI)

    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.

  12. RIS-M-2264 CONSTRUCTION OF PWR NUCLEAR CROSS SECTIONS FOR TRANSIENT

    E-Print Network [OSTI]

    RISØ-M-2264 CONSTRUCTION OF PWR NUCLEAR CROSS SECTIONS FOR TRANSIENT CALCULATIONS. TEST OF THE ANTI recent Westinghouse designs, representing two different PWR reactor cores, are calculated as functions oi; COMPUTER CALCULATIONS; COUPLING CONSTANTS; CROSS SECTIONS; POWER DISTRIBUTION; PWR TYPE REACTORS

  13. A Comparison Between Model Reduction and Controller Reduction: Application to a PWR Nuclear Planty

    E-Print Network [OSTI]

    Gevers, Michel

    A Comparison Between Model Reduction and Controller Reduction: Application to a PWR Nuclear Planty model reduction with controller reduction for the same PWR system. We show that closed-loop techniques to the design of a low-order con- troller for a realistic model of order 42 of a Pressurized Water Reactor (PWR

  14. Ris-M-2209 THE THREE-DIMENSIONAL PWR TRANSIENT CODE

    E-Print Network [OSTI]

    Risø-M-2209 THE THREE-DIMENSIONAL PWR TRANSIENT CODE ANTI; ROD EJECTION TEST CALCULATION A neutronics and thermal-hydraulics descrip- tion of a PWR core under transient conditions. In this report and with closed hydraulic channels. INIS descriptors. A CODES, CONTROL ELEMENTS, HYDRAULICS, PWR TYPE REACTORS

  15. Timing analysis of PWR fuel pin failures

    SciTech Connect (OSTI)

    Jones, K.R.; Wade, N.L.; Katsma, K.R.; Siefken, L.J. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Straka, M. (Halliburton NUS, Idaho Falls, ID (United States))

    1992-09-01

    This report discusses research conducted to develop and demonstrate a methodology for calculation of the time interval between receipt of the containment isolation signals and the first fuel pin failure for loss-of-coolant accidents (LOCAs). Demonstration calculations were performed for a Babcock and Wilcox (B W) design (Oconee) and a Westinghouse (W) four-loop design (Seabrook). Sensitivity studies were performed to assess the impacts of fuel pin burnup, axial peaking factor, break size, emergency core cooling system availability, and main coolant pump trip on these times. The analysis was performed using the following codes: FRAPCON-2, for the calculation of steady-state fuel behavior; SCDAP/RELAP5/MOD3 and TRACPF1/MOD1, for the calculation of the transient thermal-hydraulic conditions in the reactor system; and FRAP-T6, for the calculation of transient fuel behavior. In addition to the calculation of fuel pin failure timing, this analysis provides a comparison of the predicted results of SCDAP/RELAP5/MOD3 and TRAC-PF1/MOD1 for large-break LOCA analysis. Using SCDAP/RELAP5/MOD3 thermal-hydraulic data, the shortest time intervals calculated between initiation of containment isolation and fuel pin failure are 10.4 seconds and 19.1 seconds for the B W and W plants, respectively. Using data generated by TRAC-PF1/MOD1, the shortest intervals are 10.3 seconds and 29.1 seconds for the B W and W plants, respectively. These intervals are for a double-ended, offset-shear, cold leg break, using the technical specification maximum peaking factor and applied to fuel with maximum design burnup. Using peaking factors commensurate with actual burnups would result in longer intervals for both reactor designs. This document provides appendices K and L of this report which provide plots for the timing analysis of PWR fuel pin failures for Oconee and Seabrook respectively.

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

    SciTech Connect (OSTI)

    Faidy, C. [EDF SEPTEN, Villeurbanne (France)

    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.

  17. Effects of Burnable Absorbers on PWR Spent Nuclear Fuel

    SciTech Connect (OSTI)

    P.M. O'Leary; Dr. M.L. Pitts

    2000-08-21

    Burnup credit is an ongoing issue in designing and licensing transportation and storage casks for spent nuclear fuel (SNF). To address this issue, in July 1999, the U.S. Nuclear Regulatory Commission (NRC), Spent Fuel Project Office, issued Interim Staff Guidance-8 (ISG-8), Revision 1 allowing limited burnup credit for pressurized water reactor (PWR) spent nuclear fuel (SNF) to be used in transport and storage casks. However, one of the key limitations for a licensing basis analysis as stipulated in ISG-8, Revision 1 is that ''burnup credit is restricted to intact fuel assemblies that have not used burnable absorbers''. Because many PWR fuel designs have incorporated burnable-absorber rods for more than twenty years, this restriction places an unnecessary burden on the commercial nuclear power industry. This paper summarizes the effects of in-reactor irradiation on the isotopic inventory of PWR fuels containing different types of integral burnable absorbers (BAs). The work presented is illustrative and intended to represent typical magnitudes of the reactivity effects from depleting PWR fuel with different types of burnable absorbers.

  18. Ris9-R-609(EN) Simulation ofa PWR Power Plant

    E-Print Network [OSTI]

    with steam line, turbine and condenser, interconnected with pumps, valves and controllers. The model canRis9-R-609(EN) Simulation ofa PWR Power Plant for Process Control and Diagnosis Finn Ravnsbjerg ^N> for Process Control and Diagnosis Finn Ravnsbjerg Nielsen Risø National Laboratory, Roskilde

  19. Analysis of PWR RCS Injection Strategy During Severe Accident

    SciTech Connect (OSTI)

    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.

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

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LISTStar Energy LLCLtd Jump to: navigation,CauveryGas & Elec CorpEthanolCentralE

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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 all respects except that it contained a partial blockage formed by attaching sleeves (or "balloons") to some of the rods. 6. SOURCE AND SCOPE OF DATA Phenomena Tested - Heat transfer in the core of a PWR during a re-flood phase of postulated large break LOCA. Test Designation - Achilles Rig. The programme includes the following types of experiments: - on an unballooned cluster: -- single phase air flow -- low pressure level swell -- low flooding rate re-flood -- high flooding rate re-flood - on a ballooned cluster containing 80% blockage formed by 16 balloon sleeves -- single phase air flow -- low flooding rate re-flood 7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM N/A 8. DATA FORMAT AND COMPUTER Many Computers (M00019MNYCP00). 9. TYPICAL RUNNING TIME N/A 11. CONTENTS OF LIBRARY The ACHILLES package contains test data and associated data processing software as well as the documentation listed above. 12. DATE OF ABSTRACT November 2013. KEYWORDS: DATABASES, BENCHMARKS, HEAT TRANSFER, LOSS-OF-COLLANT ACCIDENT, PWR REACTORS, REFLOODING

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 OutreachProductswsicloudwsiclouddenDVA N C E D B L OBransenBusinessInitial Validation and BenchmarkPWR Reactor

  4. Michigan South Central Pwr Agy | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QAsource History ViewMayo, Maryland: Energy ResourcesDec 2005 WindPRO is developedShores,Ethanol LLC Jump to:Pwr Agy

  5. Twin County Electric Pwr Assn | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop IncIowa (Utility Company) Jump to:Tucson ElectricTurquoiseCounty Electric Pwr Assn

  6. Vermont Public Pwr Supply Auth | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop IncIowa (Utility Company) JumpGTZUtility RatesComercio eVercipiaVermillion,Pwr

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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).

  9. Hess Retail Natural Gas and Elec. Acctg. (New Hampshire) | Open Energy

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LISTStar2-0057-EA JumpDuimen River PowerHeckert BXTHengyuanUmwelt JumpInformation

  10. Hess Retail Natural Gas and Elec. Acctg. (New York) | Open Energy

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LISTStar2-0057-EA JumpDuimen River PowerHeckert BXTHengyuanUmwelt

  11. TRANSPORT CHARACTERISTICS OF SELECTED PWR LOCA GENERATED DEBRIS.

    SciTech Connect (OSTI)

    A. K. MAJI; B. MARSHALL; ET AL

    2000-10-01

    In the unlikely event of a Loss of Coolant Accident (LOCA) in a pressurized water reactor (PWR), break jet impingement would dislodge thermal insulation from nearby piping, as well as other materials within the containment, such as paint chips, concrete dust, and fire barrier materials. Steam/water flows induced by the break and by the containment sprays would transport debris to the containment floor. Subsequently, debris would likely transport to and accumulate on the suction sump screens of the emergency core cooling system (ECCS) pumps, thereby potentially degrading ECCS performance and possibly even failing the ECCS. In 1998, the U. S. Nuclear Regulatory Commission (NRC) initiated a generic study (Generic Safety Issue-191) to evaluate the potential for the accumulation of LOCA related debris on the PWR sump screen and the consequent loss of ECCS pump net positive suction head (NPSH). Los Alamos National Laboratory (LANL), supporting the resolution of GSI-191, was tasked with developing a method for estimating debris transport in PWR containments to estimate the quantity of debris that would accumulate on the sump screen for use in plant specific evaluations. The analytical method proposed by LANL, to predict debris transport within the water that would accumulate on the containment floor, is to use computational fluid dynamics (CFD) combined with experimental debris transport data to predict debris transport and accumulation on the screen. CFD simulations of actual plant containment designs would provide flow data for a postulated accident in that plant, e.g., three-dimensional patterns of flow velocities and flow turbulence. Small-scale experiments would determine parameters defining the debris transport characteristics for each type of debris. The containment floor transport methodology will merge debris transport characteristics with CFD results to provide a reasonable and conservative estimate of debris transport within the containment floor pool and subsequent accumulation of debris on the sump screen. The complete methodology will, of course, include a means of estimating debris generation, transport to the containment floor, transport to the sump screen, and the resulting loss of NPSH.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    Tanaka, T. [Kansai Electric Power Company, Osaka (Japan); Shimizu, S.; Ogata, Y. [Mitsubishi Heavy Industries, Ltd., Kobe (Japan)

    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.

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

    SciTech Connect (OSTI)

    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)

  15. Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version)

    SciTech Connect (OSTI)

    M. Krug; R. Shogan; A. Fero; M. Snyder

    2004-11-01

    Pressurized water reactor (PWR) cores, operate under extreme environmental conditions due to coolant chemistry, operating temperature, and neutron exposure. Extending the life of PWRs require detailed knowledge of the changes in mechanical and corrosion properties of the structural austenitic stainless steel components adjacent to the fuel. This report contains basic material characterization information of the as-installed samples of reactor internals material which were harvested from a decommissioned PWR.

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

    SciTech Connect (OSTI)

    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.

  17. Characterization of Decommissioned PWR Vessel Internals Material Samples: Tensile and SSRT Testing (Nonproprietary Version)

    SciTech Connect (OSTI)

    M.Krug, R.Shogan

    2004-09-01

    Pressurized water reactor (PWR) cores operate under extreme environmental conditions due to coolant chemistry, operating temperature, and neutron exposure. Extending the life of PWRs requires detailed knowledge of the changes in mechanical and corrosion properties of the structural austenitic stainless steel components adjacent to the fuel (internals) subjected to such conditions. This project studied the effects of reactor service on the mechanical and corrosion properties of samples of baffle plate, former plate, and core barrel from a decommissioned PWR.

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

    SciTech Connect (OSTI)

    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.

  19. Analysis of Potential Hydrogen Risk in the PWR Containment

    SciTech Connect (OSTI)

    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)

  20. PWR FLECHT SEASET unblocked bundle, forced and gravity reflood task data report. Volume 1

    SciTech Connect (OSTI)

    Loftus, M.J.; Hochreiter, L.E.; Conway, C.E.; Dodge, C.E.; Tong, A.; Rosal, E.R.; Valkovic, M.M.; Wong, S.

    1981-09-01

    This report presents data from the Unblocked Bundle, Forced and Gravity Reflood Task of the Full-Length Emergency Core Heat Transfer Separate Effects and Systems Effects Tests (FLECHT SEASET) program. The tests consisted of forced and gravity reflood experiments and steam cooling tests, using electrical heater rods to simulate current nuclear fuel arrays (similar to Westinghouse 17 x 17 assemblies) of PWR and PWR fuel vendors. Data obtained include rod clad temperatures, turnaround and quench times, heat transfer coefficients, inlet flooding rates, overall mass balance, differential pressures and calculated void fractions in the test section, thimble wall and steam temperatures, and exhaust steam and liquid carryover rates.

  1. PWR FLECHT SEASET unblocked bundle, forced and gravity reflood task data report. Volume 2. Appendix C

    SciTech Connect (OSTI)

    Loftus, M.J.; Hochreiter, L.E.; Conway, C.E.; Dodge, C.E.; Tong, A.; Rosal, E.R.; Valkovic, M.M.; Wong, S.

    1981-09-01

    This report presents data from the Unblocked Bundle, Forced and Gravity Reflood Task of the Full-Length Emergency Core Heat Transfer Separate Effects and Systems Effects Tests (FLECHT SEASET) program. The tests consisted of forced and gravity reflood experiments and steam cooling tests, using electrical heater rods to simulate current nuclear fuel arrays (similar to Westinghouse 17 x 17 assemblies) of PWR and PWR fuel vendors. Data obtained include rod clad temperatures, turnaround and quench times, heat transfer coefficients, inlet flooding rates, overall mass balance, differential pressures and calculated void fractions in the test section, thimble wall and steam temperatures, and exhaust steam and liquid carryover rates.

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

    SciTech Connect (OSTI)

    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.

  3. UNDERSTANDING OF HYDRIDING MECHANISMS OF ZIRCALOY-4 ALLOY DURING CORROSION IN PWR SIMULATED CONDITIONS

    E-Print Network [OSTI]

    Motta, Arthur T.

    1 UNDERSTANDING OF HYDRIDING MECHANISMS OF ZIRCALOY-4 ALLOY DURING CORROSION IN PWR SIMULATED CONDITIONS AND INFLUENCE OF ZIRCONIUM HYDRIDES ON ZIRCALOY-4 CORROSION C. BISOR-MELLOUL, M. TUPIN, P. BOSSIS-sur-Yvette ­ France A. MOTTA Mechanical and Nuclear Engineering Department, Penn State University 227 Reber Building

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

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

    SciTech Connect (OSTI)

    Fei, T.; Hoffman, E.A.; Kim, T.K.; Taiwo, T.A. [Nuclear Engineering Division Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL (United States)

    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)

  7. Lakes_Elec_You

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested Parties - WAPA PublicLED ADOPTION REPORT LED8-14DepartmentLabor3-01Lakes,

  8. River Basin Commissions (Indiana)

    Broader source: Energy.gov [DOE]

    This legislation establishes river basin commissions, for the Kankakee, Maumee, St. Joseph, and Upper Wabash Rivers. The commissions facilitate and foster cooperative planning and coordinated...

  9. TITAN code development for application to a PWR steam line break accident : final report 1983-1984

    E-Print Network [OSTI]

    Tsai, Chon-Kwo

    1984-01-01

    Modification of the TITAN computer code which enables it to be applied to a PWR steam line break accident has been accomplished. The code now has the capability of simulating an asymmetric inlet coolant temperature transient ...

  10. Transient thermal analysis of PWR’s by a single-pass procedure using a simplified nodal layout

    E-Print Network [OSTI]

    Liu, Jack S. H.

    1979-01-01

    PWR accident conditions and analysis methods have been reviewed. Limitations of the simplified method with respect to analysis of these accident conditions are drawn and two transients ( loss of coolant flow, seized rotor) ...

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

    SciTech Connect (OSTI)

    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.

  12. Safety analysis of B and W Standard PWR using thorium-based fuels

    SciTech Connect (OSTI)

    Uotinen, V.O.; Carroll, W.P.; Jones, H.M.; Toops, E.C.

    1980-06-01

    A study was performed to assess the safety and licenseability of the Babcock and Wilcox standard 205-fuel assembly PWR when it is fueled with three types of thoria-based fuels denatured (/sup 233/U//sup 238/U-Th)O/sub 2/, denatured (/sup 235//U/sup 238/U-Th)O/sub 2/, and (Th-Pu)O/sub 2/. Selected transients were analyzed using typical PWR safety analysis calculational methods. The results support the conclusion that it is feasible from a safety standpoint to utilize either of the denatured urania-thoria fuels in the standard B and W plant. In addition, it appears that the use of thoria-plutonia fuels would probably also be feasible. These tentative conclusions depend on a data that is more limited than that available for UO/sub 2/ fuels.

  13. An Empirical Approach to Bounding the Axial Reactivity Effects of PWR Spent Nuclear Fuel

    SciTech Connect (OSTI)

    P. M. O'Leary; J. M. Scaglione

    2001-04-04

    One of the significant issues yet to be resolved for using burnup credit (BUC) for spent nuclear fuel (SNF) is establishing a set of depletion parameters that produce an adequately conservative representation of the fuel's isotopic inventory. Depletion parameters (such as local power, fuel temperature, moderator temperature, burnable poison rod history, and soluble boron concentration) affect the isotopic inventory of fuel that is depleted in a pressurized water reactor (PWR). However, obtaining the detailed operating histories needed to model all PWR fuel assemblies to which BUC would be applied is an onerous and costly task. Simplifications therefore have been suggested that could lead to using ''bounding'' depletion parameters that could be broadly applied to different fuel assemblies. This paper presents a method for determining a set of bounding depletion parameters for use in criticality analyses for SNF.

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

    SciTech Connect (OSTI)

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

    SciTech Connect (OSTI)

    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.

  16. River Corridor Achievements

    Broader source: Energy.gov [DOE]

    Washington Closure Hanford and previous contractors have completed much of the cleanup work in the River Corridor, shown here.

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

    SciTech Connect (OSTI)

    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.

  18. Importance of thermal nonequilibrium considerations for the simulation of nuclear reactor LOCA transients. [PWR

    SciTech Connect (OSTI)

    Fischer, S.R.; Nelson, R.A.; Sullivan, L.H.

    1980-01-01

    The purpose of this paper is to show the importance of considering thermal nonequilibrium effects in computer simulations of the refill and reflood portions of pressurized water reactor (PWR) loss-of-coolnat accident (LOCA) transients. Although RELAP4 assumes thermodynamic equilibrium between phases, models that account for the nonequilibrium phenomena associated with the mixing of subcooled emergency cooling water with steam and the superheating of vapor in the presence of liquid droplets have recently been incorporated into the code. Code calculated results, both with and without these new models, have been compared with experimental test data to assess the importance of including thermal nonequilibrium phenomena in computer code simulations.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    Swamy, S.A.; Bhowmick, D.C. [Westinghouse Nuclear Technology Division, Pittsburgh, PA (United States)

    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 (OSTI)

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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)

  4. Non-Linear Dynamics Analysis of a PWR with Up-to-date Fuel Design

    SciTech Connect (OSTI)

    Riverola Gurruchaga, Javier [ENUSA Industrias Avanzadas S.A., Santiago Rusinol 12, 28040 Madrid (Spain)

    2007-07-01

    The Lyapunov stability theorems are applied to a simplified system of non-linear differential equations representative of a current 3 loop /12 feet contemporary PWR (Generation II) with up-to-date 17x17 lattice fuel design. The one-speed non-linear point kinetics model with six delayed neutron groups and lumped parameter heat transfer equations in the fuel rod and coolant along with a reactivity function with Doppler and moderator feedback effects is considered. First, local asymptotic stability is demonstrated at a variety of equilibrium state-points ranging from start-up to 150% nominal power. Then, a Lyapunov V function is found with the mathematical condition for sign definiteness and the stability region of attraction around the equilibrium HFP state is obtained. This study is complemented with the application of the Welton criterion for non linear kinetics and linear feedback in the frequency domain. As expected and consistently with Reactor Physics theory and experience, the strong asymptotic stable trend of a PWR is confirmed again for all analyzed conditions. This method is general and adaptable to other fuel assembly designs and reactor types. (authors)

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

    SciTech Connect (OSTI)

    Phillips, Jesse; Notafrancesco, Allen (USNRC, Office of Nuclear Regulatory Research, Rockville, MD); Tills, Jack Lee (Jack Tills & Associates, Inc., Sandia Park, NM)

    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.

  6. d Onion River Review d river run by

    E-Print Network [OSTI]

    Weaver, Adam Lee

    d Onion River Review d 2009 d river run by Eireann Aspell Jamie Gorton Heidi Lynch Matt Serron #12 lives. #12;BLANK Editors' Note There were portents hinting at the Onion River Review's future as early

  7. TVA's Integrated River System

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

    and controlling floods. So far as may be consistent with such purposes, ...for the generation of electric energy... TVA Power Service Area TVA'S INTEGRATED RIVER SYSTEM | 3...

  8. Large River Floodplains

    E-Print Network [OSTI]

    Dunne, T; Aalto, RE

    2013-01-01

    River, California. Sedimentology 57, 389–407. http://J. (Eds. ), Fluvial Sedimentology VI. Special PublicationsAnatomy of an avulsion. Sedimentology 36, 1–24. Stallard,

  9. San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses

    SciTech Connect (OSTI)

    Hermann, O.W.

    1999-09-01

    The isotopic composition of mixed-oxide fuel (fabricated with both uranium and plutonium isotope) discharged from reactors is of interest to the Fissile Material Disposition Program. The validation of depletion codes used to predict isotopic compositions of MOX fuel, similar to studies concerning uranium-only fueled reactors, thus, is very important. The EEI-Westinghouse Plutonium Recycle Demonstration Program was conducted to examine the use of MOX fuel in the San Onofre PWR, Unit I, during cycles 2 and 3. The data usually required as input to depletion codes, either one-dimensional or lattice codes, were taken from various sources and compiled into this report. Where data were either lacking or determined inadequate, the appropriate data were supplied from other references. The scope of the reactor operations and design data, in addition to the isotopic analyses, were considered to be of sufficient quality for depletion code validation.

  10. Prototypical steam generator (MB-2) transient testing program. Task plan/scaling analysis report. [PWR

    SciTech Connect (OSTI)

    Young, M.Y.; Takeuchi, K.; Mendler, O.J.; Hopkins, G.W.

    1984-03-01

    This report describes the Westinghouse MB-2 model boiler test facility and the test program currently planned (with Westinghouse/EPRI/NRC funding) to investigate various types of possible accidents which might occur in a PWR steam generator. The planned tests will simulate loss of feedwater (LOF) transients, various steam generator tube rupture (SGTR) scenarios, and steamline breaks (SLB). The facility will be extensively modified to allow measurement of local wall and fluid temperatures, and to measure possible moisture carryover during the SLB and SGTR tests. This report is divided into six sections. The first three sections describe the facility and the new components and instrumentation to be installed. The next section is a detailed scaling analysis of MB-2. Section 5 describes the background and objectives of the tests, and section 6 describes the analysis of the data which if planned.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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)

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

    SciTech Connect (OSTI)

    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.

  1. Onion River OnionRiverReview2011dd

    E-Print Network [OSTI]

    Weaver, Adam Lee

    2011 d river run by Lauren Fish Heather Lessard Jenna McCarthy Philip Noonan Erica Sabelawski #12;TheOnion River Review OnionRiverReview2011dd 2011 Our Lives in Dance Alex Dugas We were born with bare. Then we tap-danced on our graves, and back through the womb again, shoeless. #12;d Onion River Review d

  2. d Onion River Review d river run by

    E-Print Network [OSTI]

    Weaver, Adam Lee

    d Onion River Review d 2013 d river run by Alex Dugas Sarah Fraser Bryan Hickey Nick Lemon Diana Marchessault Mickey O'Neill Amy Wilson #12;#12;Editors' Note For this edition of the Onion River Review, we are finally able to present to you this year's edition of the Onion River Review: our love child, our shining

  3. 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 (OSTI)

    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.

  4. Rules of the River

    E-Print Network [OSTI]

    Anonymous,

    1980-01-01

    't overexert. Be careful of sunburn, heat exhaustion and heat stroke. ? Leave car keys hidden at launch point or take-out (with shuttle cars), or firmly attach them to an article of clothing on your person with a strong safety pin. Don't leave valuables... are organized into four parts: ? Planning Your River Trip ? Selecting Your Equipment ? Rules of Safety ? Rules of Conduct When put into practice, these "Rules of the River" may turn an uncomfortable river trip into a lasting and special experience. Read...

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  7. ELEC4705 Fall 2009 ELEC4705 Fall 2009 1

    E-Print Network [OSTI]

    Smy, Tom

    -type substrate a oxide layer and a metal gate, as shown in figure 1. If we apply a positive potential to the gate

  8. ELEC4705 Fall 2009 ELEC4705 Fall 2009 1

    E-Print Network [OSTI]

    Smy, Tom

    -type) See figure 3 Figure 3. Semiconductor Band Structure #12;6 TOM SMY, DEVICES MATERIALS AND PROPERTIES Touching #12;TOM SMY, DEVICES MATERIALS AND PROPERTIES 7 After the metal and semiconductor have been 13. The Diode 1 13.1. Schottky Barriers (Metal-Semiconductor Junctions) 4 13.1.1. Material Band

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

    SciTech Connect (OSTI)

    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.

  10. On tropospheric rivers

    E-Print Network [OSTI]

    Hu, Yuanlong, 1964-

    2002-01-01

    In this thesis, we investigate atmospheric water vapor transport through a distinct synoptic phenomenon, namely, the Tropospheric River (TR), which is a local filamentary structure on a daily map of vertically integrated ...

  11. Savannah River Site Waste Disposition Project

    Office of Environmental Management (EM)

    Terrel J. Spears Assistant Manager Waste Disposition Project DOE Savannah River Operations Office Savannah River Site Savannah River Site Waste Disposition Project Waste...

  12. ELEC 433: Digital Communications Lab Prerequisites: ELEC 220 & ELEC 326. ELEC 430 (or equivalent) is strongly suggested.

    E-Print Network [OSTI]

    ) is strongly suggested. Course Time: Tuesdays 2:30-4:30pm Lab Hours: Thursdays 2:30-5:00pm Place: DSP Lab Generator environment targeting FPGA-based processing boards for all designs. We will meet weekly on Tuesdays at Noon unless indicated otherwise. Lab hours will be held on Thursdays form 2:30 to 5

  13. Examination of spent PWR fuel rods after 15 years in dry storage.

    SciTech Connect (OSTI)

    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 release from the fuel pellets occurred during the thermal benchmark tests or storage. Measurements of the cladding outer-diameter, oxide thickness and wall thickness are in the expected range for cladding of the Surry exposure. The measured hydrogen content is consistent with the oxide thickness. The volume of hydrides varies azimuthally around the cladding, but there is little variation across the thickness, of the cladding. It is most significant that all of the hydrides appear to have retained the circumferential orientation typical of prestorage PWR fuel rods.

  14. Examination of Spent PWR Fuel Rods After 15 Years in Dry Storage

    SciTech Connect (OSTI)

    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 gas release from the fuel pellets occurred during the thermal benchmark tests or storage. Measurements of the cladding outer-diameter, oxide thickness and wall thickness are in the expected range for cladding of the Surry exposure. The measured hydrogen content is consistent with the oxide thickness. The volume of hydrides varies azimuthally around the cladding, but there is little variation across the thickness, of the cladding. It is most significant that all of the hydrides appear to have retained the circumferential orientation typical of pre-storage PWR fuel rods. (authors)

  15. Ecology of the river dolphin, Inia geoffrensis, in the Cinaruco River, Venezuela 

    E-Print Network [OSTI]

    McGuire, Tamara Lee

    1995-01-01

    The Cinaruco River is a tributary of the Orinoco River, and forms the southern boundary of Venezuela's newest national park, Santos Luzardo. Like other rivers of this region, the Cinaruco River undergoes an extreme seasonal flood cycle. River...

  16. TREAT source-term experiment STEP-1 simulating a PWR LOCA

    SciTech Connect (OSTI)

    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.

  17. MELCOR 1.8.2 assessment: Surry PWR TMLB` (with a DCH study)

    SciTech Connect (OSTI)

    Kmetyk, L.N.; Cole, R.K. Jr.; Smith, R.C.; Summers, R.M.; Thompson, S.L.

    1994-02-01

    MELCOR is a fully integrated, engineering-level computer code, being developed at Sandia National Laboratories for the USNRC. This code models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRs. As part of an ongoing assessment program, the MELCOR computer code has been used to analyze a station blackout transient in Surry, a three-loop Westinghouse PWR. Basecase results obtained with MELCOR 1.8.2 are presented, and compared to earlier results for the same transient calculated using MELCOR 1.8.1. The effects of new models added in MELCOR 1.8.2 (in particular, hydrodynamic interfacial momentum exchange, core debris radial relocation and core material eutectics, CORSOR-Booth fission product release, high-pressure melt ejection and direct containment heating) are investigated individually in sensitivity studies. The progress in reducing numeric effects in MELCOR 1.8.2, compared to MELCOR 1.8.1, is evaluated in both machine-dependency and time-step studies; some remaining sources of numeric dependencies (valve cycling, material relocation and hydrogen burn) are identified.

  18. LBB evaluation for a typical Japanese PWR primary loop by using the US NRC approved methods

    SciTech Connect (OSTI)

    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.

  19. d Onion River Review d river run by

    E-Print Network [OSTI]

    Weaver, Adam Lee

    d Onion River Review d 2012 d river run by Alex Dugas Lauren Fish Heather Lessard Jenna Mc jokes. Together these things helped shape the 2012 edition of the Onion River Review. A worthwhile departing on an adventure, you simply have no idea what will happen or who you will meet. You may run

  20. Rivanna River Basin Commission (Virginia)

    Broader source: Energy.gov [DOE]

    The Rivanna River Basin Commission is an independent local entity tasked with providing guidance for the stewardship and enhancement of the water quality and natural resources of the Rivanna River...

  1. Rio Grande River

    E-Print Network [OSTI]

    Hills Photo Shop

    2011-09-05

    FORKS BIRDBEAR-NISKU JEFFERSON GROUP DUPEROW O (IJ o BEAVER HILL LAKE GR UP ELK POINT GROUP SOURIS RIVER Ist. RED BED DAWSON BAY 2ll(IRED BED PRAIRIE EVAP WI NI ASHERN INTERLAKE STONY MOUNTAIN RED RIVER WINN IP EG Figure 3... and is bounded by the Sioux Arch, the Black Hills Uplift, the Miles City Arch, and the Bowdoin Dome. The structural trends within the basin parallel the major structural trends of the Rocky Mountain Belt. The Williston Basin is characterized by gently...

  2. VOLUNTEER-BASED SALMON RIVER

    E-Print Network [OSTI]

    Institute Environment Canada VOLUNTEER-BASED MONITORING PROGRAM FOR THE SALMON RIVER BASIN: USING BENTHICVOLUNTEER-BASED MONITORING PROGRAM FOR THE SALMON RIVER BASIN: USING BENTHIC INDICATORS TO ASSESS INDICATORS TO ASSESS STREAM ECOSYSTEM HEALTH #12;Volunteer-Based Monitoring Program for the Salmon River

  3. UPPER SACRAMENTO RIVER SPORT FISHERY

    E-Print Network [OSTI]

    UPPER SACRAMENTO RIVER SPORT FISHERY Marine Biological Laborato«y L I B R. A. R "ST OCT 2 31950 significant changes in the environmental conditions which affect fisheries in Sacramento River have resulted number of sportsmen who are turning to the Upper Sacramento River is indicative of the magnitude

  4. 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 (OSTI)

    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.

  5. Radionuclide release from PWR fuels in a reference tuff repository groundwater

    SciTech Connect (OSTI)

    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.

  6. Analyses of High Pressure Molten Debris Dispersion for a Typical PWR Plant

    SciTech Connect (OSTI)

    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 start of steam release. (authors)

  7. Containment pressurization and burning of combustible gases in a large, dry PWR containment during a station blackout sequence

    SciTech Connect (OSTI)

    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.

  8. Savannah River Site Robotics

    ScienceCinema (OSTI)

    None

    2012-06-14

    Meet Sandmantis and Frankie, two advanced robotic devices that are key to cleanup at Savannah River Site. Sandmantis cleans hard, residual waste off huge underground storage tanks. Frankie is equipped with unique satellite capabilities and sensing abilties that can determine what chemicals still reside in the tanks in a cost effective manner.

  9. An Analysis of Texas Waterways: A Report on the Physical Characteristics of Rivers, Streams, and Bayous in Texas. 

    E-Print Network [OSTI]

    Belisle, Harold J.; Josselet, Ron

    1977-01-01

    Cree k San Jacinto River, East Fork Spring Creek Taylor Bayou Turkey Creek V. CENTRAL TEXAS WATE RWAYS A. Major Waterways Blanco River Bosque River Brazos River Colorado River Concho River . Frio River Guadalupe River Lampasas River... MAJOR CENTRAL TEXAS WATERWAYS 13. Blanco River 14. Bosque River 15. Brazos River 16. Colorado River 17. Concho River 18. Frio River 19. Guadal upe River 20. Lampasas River 21. Lavaca River 22. Leon River 23. Little River 24. Llano River 25...

  10. First interim examination of defected BWR and PWR rods tested in unlimited air at 229/sup 0/C

    SciTech Connect (OSTI)

    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.

  11. Experiment data report for LOFT large-break loss-of-coolant experiment L2-5. [PWR

    SciTech Connect (OSTI)

    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.

  12. Impact of fuel cladding failure events on occupational radiation exposures at nuclear power plants. Case study: PWR during routine operations

    SciTech Connect (OSTI)

    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.

  13. LOFTRAN/RETRAN comparison calculations for a postulated loss-of-feedwater ATWS in the Sizewell 'B' PWR

    SciTech Connect (OSTI)

    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.

  14. CONFLICTS IN RIVER MANAGEMENT: A CONSERVATIONIST'S PERSPECTIVE ON SACRAMENTO RIVER RIPARIAN HABITATS--

    E-Print Network [OSTI]

    CONFLICTS IN RIVER MANAGEMENT: A CONSERVATIONIST'S PERSPECTIVE ON SACRAMENTO RIVER RIPARIAN, Defenders of Wildlife, Sacramento, California. Abstract: The Sacramento River's historic riparian habi- tats on this conference's plenary session panel, I will provide a conservationist perspective on Sacramento River riparian

  15. CRC DEPLETION CALCULATIONS FOR THE NON-RODDED ASSEMBLIES IN BATCHES 1, 2, AND 3 OF CRYSTAL RIVER UNIT 3

    SciTech Connect (OSTI)

    Kenneth D. Wright

    1997-07-29

    The purpose of this design analysis is to document the SAS2H depletion calculations of certain non-rodded fuel assemblies from batches 1, 2, and 3 of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for Commercial Reactor Critical (CRC) evaluations to support development of the disposal criticality methodology. A non-rodded assembly is one which never contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) during its irradiation history. The objective of this analysis is to provide SAS2H generated isotopic compositions for each fuel assembly's depleted fuel and depleted burnable poison materials. These SAS2H generated isotopic compositions are acceptable for use in CRC benchmark reactivity calculations containing the various fuel assemblies.

  16. CRC DEPLETION CALCULATIONS FOR THE RODDED ASSEMBLIES IN BATCHES 1, 2, 3, AND 1X OF CRYSTAL RIVER UNIT 3

    SciTech Connect (OSTI)

    Kenneth D. Wright

    1997-09-03

    The purpose of this design analysis is to document the SAS2H depletion calculations of certain rodded fuel assemblies from batches 1, 2, 3, and 1X of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for Commercial Reactor Critical (CRC) evaluations to support the development of the disposal criticality methodology. A rodded assembly is one that contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) for some period of time during its irradiation history. The objective of this analysis is to provide SAS2H calculated isotopic compositions of depleted fuel and depleted burnable poison for each fuel assembly to be used in subsequent CRC reactivity calculations containing the fuel assemblies.

  17. CRC DEPLETION CALCULATIONS FOR THE NON-RODDED ASSEMBLIES IN BATCHES 4 AND 5 OF CRYSTAL RIVER UNIT 3

    SciTech Connect (OSTI)

    Kenneth D. Wright

    1997-07-30

    The purpose of this design analysis is to document the SAS2H depletion calculations of certain non-rodded fuel assemblies from batches 4 and 5 of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for commercial Reactor Critical (CRC) evaluations to support the development of the disposal criticality methodology. A non-rodded assembly is one which never contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) during its irradiation history. The objective of this analysis is to provide SAS2H generated isotopic compositions for each fuel assembly's depleted fuel and depleted burnable poison materials. These SAS2H generated isotopic compositions are acceptable for use in CRC benchmark reactivity calculations containing the various fuel assemblies.

  18. Hood River Passive House

    SciTech Connect (OSTI)

    Hales, D.

    2013-03-01

    The Hood River Passive Project was developed by Root Design Build of Hood River Oregon using the Passive House Planning Package (PHPP) to meet all of the requirements for certification under the European Passive House standards. The Passive House design approach has been gaining momentum among residential designers for custom homes and BEopt modeling indicates that these designs may actually exceed the goal of the U.S. Department of Energy's (DOE) Building America program to reduce home energy use by 30%-50% (compared to 2009 energy codes for new homes). This report documents the short term test results of the Shift House and compares the results of PHPP and BEopt modeling of the project.

  19. TOPICAL REPORT ON ACTINIDE-ONLY BURNUP CREDIT FOR PWR SPENT NUCLEAR FUEL PACKAGES

    SciTech Connect (OSTI)

    DOE

    1997-04-01

    A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay. A set of chemical assay benchmarks is presented for this purpose as well as a method for assessing the calculational bias and uncertainty, and conservative correction factors for each isotope. (2) Validate a computer code system to predict the subcritical multiplication factor, k{sub eff}, of a spent nuclear fuel package. Fifty-seven UO{sub 2}, UO{sub 2}/Gd{sub 2}O{sub 3}, and UO{sub 2}/PuO{sub 2} critical experiments have been selected to cover anticipated conditions of SNF. The method uses an upper safety limit on k{sub eff} (which can be a function of the trending parameters) such that the biased k{sub eff}, when increased for the uncertainty is less than 0.95. (3) Establish bounding conditions for the isotopic concentration and criticality calculations. Three bounding axial profiles have been established to assure the ''end effect'' is accounted for conservatively. (4) Use the validated codes and bounding conditions to generate package loading criteria (burnup credit loading curves). Burnup credit loading curves show the minimum burnup required for a given initial enrichment. The utility burnup record is compared to this requirement after the utility accounts for the uncertainty in its record. Separate curves may be generated for each assembly design, various minimum cooling times and burnable absorber histories. (5) Verify that SNF assemblies meet the package loading criteria and confirm proper assembly selection prior to loading. A measurement of the average assembly burnup is required and that measurement must be within 10% of the utility burnup record for the assembly to be accepted. The measurement device must be accurate to within 10%. Each step is described in detail for use with any computer code system and is then demonstrated with the SCALE 4.2 computer code package using 27BURNUPLIB cross sections.

  20. In-Vessel Retention of Molten Core Debris in the Westinghouse AP1000 Advanced Passive PWR

    SciTech Connect (OSTI)

    Scobel, James H.; Conway, L.E. [Westinghouse Electric Company LLC, P.O. Box 355, Pittsburgh, PA 15230-0355 (United States); Theofanous, T.G. [Center for Risk Studies and Safety, University of California Santa Barbara (United States)

    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)

  1. d Onion River Review d OnionRiverReview2010dd

    E-Print Network [OSTI]

    Weaver, Adam Lee

    ://www.smcvt.edu/onionriver/. #12;d Onion River Review d 2010 d river run by Eireann Aspell Lauren Fish Jamie Gorton Heidi Lynchd Onion River Review d 2010 d OnionRiverReview2010dd #12;The Onion River Review is the literary Matt Serron #12;BLANK Editors' Note The only certainty of the Onion River Review is the editors' un

  2. RiverHeath Appleton, WI

    Broader source: Energy.gov [DOE]

    The goal of the project is to produce a closed loop neighborhood-wide geothermal exchange system using the river as the source of heat exchange.

  3. Florida Nuclear Profile - Crystal River

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

    Crystal River1" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

  4. Louisiana Nuclear Profile - River Bend

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

    River Bend" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

  5. Rappahannock River Basin Commission (Virginia)

    Broader source: Energy.gov [DOE]

    The Rappahannock River Basin Commission is an independent local entity tasked with providing guidance for the stewardship and enhancement of the water quality and natural resources of the...

  6. Susquehanna River Basin Compact (Maryland)

    Broader source: Energy.gov [DOE]

    This legislation enables the state's entrance into the Susquehanna River Basin Compact, which provides for the conservation, development, and administration of the water resources of the...

  7. Experiment operations plan for the MT-4 experiment in the NRU reactor. [PWR

    SciTech Connect (OSTI)

    Russcher, G.E.; Wilson, C.L.; Parchen, L.J.; Marshall, R.K.; Hesson, G.M.; Webb, B.J.; Freshley, M.D.

    1983-06-01

    A series of thermal-hydraulic and cladding materials deformation experiments were conducted using light-water reactor fuel bundles as part of the Pacific Northwest Laboratory Loss-of-Coolant Accident (LOCA) Simulation Program. This report is the formal operations plan for MT-4 - the fourth materials deformation experiment conducted in the National Research Universal (NRU) reactor, Chalk River, Ontario, Canada. A major objective of MT-4 was to simulate a pressurized water reactor LOCA that could induce fuel rod cladding deformation and rupture due to a short-term adiabatic transient and a peak fuel cladding temperature of 1200K (1700/sup 0/F).

  8. Spatial design principles for sustainable hydropower development in river basins

    E-Print Network [OSTI]

    Jager, Henriette I.

    : Freshwater reserve design Hydroelectric power Network theory Optimization Regulated rivers River portfolio

  9. Preliminary Notice of Violation, Westinghouse Savannah River...

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

    March 6, 2000 Issued to Westinghouse Savannah River Company, related to Procurement Quality Assurance and Quality Improvement Deficiencies at the Savannah River Site. On March 6,...

  10. Preliminary Notice of Violation, Westinghouse Savannah River...

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

    EA 98-09 Preliminary Notice of Violation, Westinghouse Savannah River Company - EA 98-09 September 21, 1998 Preliminary Notice of Violation issued to Westinghouse Savannah River...

  11. PIA - Savannah River Nuclear Solutions Electronic Safeguards...

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

    Electronic Safeguards Security System (E3S) PIA - Savannah River Nuclear Solutions Electronic Safeguards Security System (E3S) PIA - Savannah River Nuclear Solutions Electronic...

  12. Project Management Institute Highlights Savannah River Nuclear...

    Office of Environmental Management (EM)

    Management Institute Highlights Savannah River Nuclear Solutions in Publication Project Management Institute Highlights Savannah River Nuclear Solutions in Publication February 6,...

  13. Independent Oversight Review, Savannah River Operations Office...

    Office of Environmental Management (EM)

    Savannah River Operations Office - July 2013 Independent Oversight Review, Savannah River Operations Office - July 2013 July 2013 Review of the Employee Concerns Program at the...

  14. Flambeau River Biofuels Demonstration-Scale Biorefinery

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

    in Wisconsin (NewPage Corporation in Wisconsin Rapids and Flambeau River Papers, LLC in Park Falls). NewPage and Flambeau River have demonstrated successful collaboration on...

  15. River Corridor - Hanford Site

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) byMultiday ProductionDesigningResourcesfeed-image Digg:RisingRiver

  16. GOLF COURSES FRASER RIVER BASIN

    E-Print Network [OSTI]

    : Fraser Pollution Abatement Office Fraser River Action Plan Environment Canada North Vancouver, B judgement in light of the knowledge and information available to UMA at the time of preparation. UMA denies by Environment Canada under the Fraser River Action Plan through the Fraser Pollution Abatement Office. The views

  17. Aquatic Supplement Hood River Subbasin

    E-Print Network [OSTI]

    . Table 4. Out-of-subbasin production for three Hood River steelhead populations. Table 5. Life cycle river mile 6 13 Dee ID seepage 13 cold springs 2 city of HR overflow? riverside drive reservoir? 2 stone springs 4 city of HR riverside drive reservoir? 4 middle fork coe branch 15 MFID 15 clear branch 19 MFID

  18. PWR FLECHT SEASET 21-rod bundle flow blockage task. Task plan report. FLECHT SEASET Program report No. 5

    SciTech Connect (OSTI)

    Hochreiter, L.E.; Basel, R.A.; Dennis, R.J.; Lee, N.; Massie, H.W. Jr.; Loftus, M.J.; Rosal, E.R.; Valkovic, M.M.

    1980-10-01

    This report presents a descriptive plan of tests for the 21-Rod Bundle Flow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Separate Effects and Systems Effects Test Program (FLECHT SEASET). This task will consist of forced and gravity reflooding tests utilizing electrical heater rods to simulate PWR nuclear core fuel rod arrays. All tests will be performed with a cosine axial power profile. These tests are planned to be used to determine effects of various flow blockage configurations (shapes and distributions) on reflooding behavior, to aid in development/assessment of computational models in predicting reflooding behavior of flow blockage configurations, and to screen flow blockage configurations for future 161-rod flow blockage bundle tests.

  19. Safety and licensing issues that are being addressed by the Power Burst Facility test programs. [PWR; BWR

    SciTech Connect (OSTI)

    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.

  20. Hood River Passive House

    SciTech Connect (OSTI)

    Hales, D.

    2014-01-01

    The Hood River Passive Project was developed by Root Design Build of Hood River Oregon using the Passive House Planning Package (PHPP) to meet all of the requirements for certification under the European Passive House standards. The Passive House design approach has been gaining momentum among residential designers for custom homes and BEopt modeling indicates that these designs may actually exceed the goal of the U.S. Department of Energy's (DOE) Building America program to reduce home energy use by 30%-50% (compared to 2009 energy codes for new homes). This report documents the short term test results of the Shift House and compares the results of PHPP and BEopt modeling of the project. The design includes high R-Value assemblies, extremely tight construction, high performance doors and windows, solar thermal DHW, heat recovery ventilation, moveable external shutters and a high performance ductless mini-split heat pump. Cost analysis indicates that many of the measures implemented in this project did not meet the BA standard for cost neutrality. The ductless mini-split heat pump, lighting and advanced air leakage control were the most cost effective measures. The future challenge will be to value engineer the performance levels indicated here in modeling using production based practices at a significantly lower cost.

  1. Hood River Passive House

    SciTech Connect (OSTI)

    Hales, David

    2014-01-01

    The Hood River Passive Project was developed by Root Design Build of Hood River Oregon using the Passive House Planning Package (PHPP) to meet all of the requirements for certification under the European Passive House standards. The Passive House design approach has been gaining momentum among residential designers for custom homes and BEopt modeling indicates that these designs may actually exceed the goal of the U.S. Department of Energy's (DOE) Building America program to "reduce home energy use by 30%-50% (compared to 2009 energy codes for new homes). This report documents the short term test results of the Shift House and compares the results of PHPP and BEopt modeling of the project. The design includes high R-Value assemblies, extremely tight construction, high performance doors and windows, solar thermal DHW, heat recovery ventilation, moveable external shutters and a high performance ductless mini-split heat pump. Cost analysis indicates that many of the measures implemented in this project did not meet the BA standard for cost neutrality. The ductless mini-split heat pump, lighting and advanced air leakage control were the most cost effective measures. The future challenge will be to value engineer the performance levels indicated here in modeling using production based practices at a significantly lower cost.

  2. Experiment operations plan for the TH-2 experiment in the NRU reactor. [PWR; BWR

    SciTech Connect (OSTI)

    Russcher, G.E.; Wilson, C.L.; Parchen, L.J.; Freshley, M.D.

    1983-06-01

    A series of thermal-hydraulic and cladding materials deformation experiments were conducted using light-water reactor fuel bundles as part of the Pacific Northwest Laboratory Loss-of-Coolant Accident (LOCA) Simulation Program. This report is the formal operations plan for TH-2--the second experiment in the series of thermal-hydraulic tests conducted in the National Research Universal (NRU) reactor, Chalk River, Ontario, Canada. The major objective of TH-2 was to develop the experiment reflood control parameters and the procedures to be used in subsequent experiments in this program. In this experiment, the data acquisition and control system was used to control the fuel cladding temperature during a simulated LOCA by using variable reflood coolant flow.

  3. Savannah River Site Environmental Data for 1998

    SciTech Connect (OSTI)

    Arnett, M.

    1999-06-09

    This document presents data from Savannah River Site routine effluent monitoring and environmental surveillance programs.

  4. Wood River Levee Reconstruction, Madison County, IL

    E-Print Network [OSTI]

    US Army Corps of Engineers

    Wood River Levee Reconstruction, Madison County, IL 25 October 2006 Abstract: The recommended plan provides for flood damage reduction and restores the original degree of protection of the Wood River Levee-federal sponsor is the Wood River Drainage and Levee District. The Wood River Levee System was authorized

  5. The Columbia River Estuary the Columbia River Basin

    E-Print Network [OSTI]

    " fish and wildlife in the Columbia River as affected by development and operation of the hydroelectric modified in terms of physical and biological processes. The development and operation of the hydroelectric

  6. 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 (OSTI)

    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)

  7. Dayao County Yupao River BasDayao County Yupao River Basin Hydro...

    Open Energy Info (EERE)

    Dayao County Yupao River BasDayao County Yupao River Basin Hydro electricity Development Co Ltd in Jump to: navigation, search Name: Dayao County Yupao River BasDayao County Yupao...

  8. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Mary FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    Risk · Previous Flooding · Flood Forecasting · Local Information · Flood Warnings and Bulletins · Interpreting Flood Warnings and River Height Bulletins · Flood Classifications · Other Links Flood RiskBureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Mary FLOOD

  9. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Nerang FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Forecasting · Local Height Bulletins · Flood Classifications · Other Links Flood Risk The Nerang River catchment is locatedBureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Nerang FLOOD

  10. The River Runs Dry: Examining Water Shortages in the Yellow River Basin

    E-Print Network [OSTI]

    Zusman, Eric

    2000-01-01

    in Transition Zusman/The River Runs Dry Wang Liurong.YRCC’sin Transition Zusman/The River Runs Dry not just importantin Transition Zusman/The River Runs Dry emerging market

  11. Raft River Idaho Magnetotelluric Data

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Gregory Nash

    2015-05-13

    Raw magnetotelluric (MT) data covering the geothermal system at Raft River, Idaho. The data was acquired by Quantec Geoscience. This is a zipped file containing .edi raw MT data files.

  12. Reactor Safety Research Programs. Quarterly report, July-September 1984. Volume 3. [PWR; BWR

    SciTech Connect (OSTI)

    Edler, S.K.

    1985-02-01

    This document summarizes work performed by Pacific Northwest Laboratory from July 1 through September 30, 1984, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission. Results from an instrumented fuel assembly irradiation program being performed at Halden, Norway, are reported. Accelerated pellet-cladding interaction modeling is being conducted to predict the probability of fuel rod failure under normal operating conditions. Experimental data and analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Fuel assemblies and analytical support are being provided for experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory, Idaho Falls, Idaho. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Thermal-hydraulic models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Severe fuel damage accident tests are being conducted in the NRU Reactor, Chalk River, Canada.

  13. Reactor safety research programs. Quarterly report, January-March 1984. Vol. 1. [PWR; BWR

    SciTech Connect (OSTI)

    Edler, S.K.

    1984-06-01

    This document summarizes work performed by Pacific Northwest Laboratory from January 1 through March 31, 1984, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission. Results from an instrumented fuel assembly irradiation program being performed at Halden, Norway, are reported. Accelerated pellet-cladding interaction modeling is being conducted to predict the probability of fuel rod failure under normal operating conditions. Experimental data on analytical models are being provided to aid in decision making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Fuel assemblies and analytical support are being provided for experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory, Idaho Falls, Idaho. High-temperature materials property tests are being conducted to provide data on severe core damage fuel behavior. Thermal-hydraulic models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Severe fuel damage accident tests are being conducted at the NRU reactor, Chalk River, Canada.

  14. Exhibit D: Mirant Potomac River Schedule of Unit Operations:...

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

    Operating Plan of Mirant Potomac River, LLC Exhibit D: Mirant Potomac River Schedule of Unit Operations More Documents & Publications Exhibit D: Mirant Potomac River Schedule of...

  15. Sacramento River Steelhead: Hatchery vs. Natural Smolt Outmigration

    E-Print Network [OSTI]

    Sandstrom, Phil

    2012-01-01

    DELTA SCIENCE PROGRAM Sacramento River Steelhead: HatcheryUC Davis BACKGROUND The Sacramento River steelhead trout (a tributary of the upper Sacramento River. Smolts are young,

  16. EA-1692: Red River Environmental Products, LLC Activated Carbon...

    Office of Environmental Management (EM)

    2: Red River Environmental Products, LLC Activated Carbon Manufacturing Facility, Red River Parish, LA EA-1692: Red River Environmental Products, LLC Activated Carbon Manufacturing...

  17. Level 1 probabilistic risk assessment of low power and shutdown operations at a PWR: Phase 2 results

    SciTech Connect (OSTI)

    Chu, T.L.; Bozoki, G.; Kohut, P.; Musicki, Z.; Wong, S.M.; Yang, J.; Hsu, C.J.; Diamond, D.J.; Su, R.F. [Brookhaven National Lab., Upton, NY (United States); Holmes, B. [AEA Technology, London (United Kingdom); Siu, N. [Massachusetts Inst. of Tech., Cambridge, MA (United States); Bley, D.; Lin, J. [Pickard, Lowe and Garrick, Inc., Newport Beach, CA (United States)

    1992-12-31

    As a result of the Chernobyl accident and other precursor events (e.g., Diablo Canyon), the US Nuclear Regulatory Commission`s (NRC`s) Office of Nuclear Regulatory Research (RES) initiated an extensive project during 1989 to carefully examine the potential risks during Low Power and Shutdown (LP&S) operations. Shortly after the program began, an event occurred at the Vogtle plant during shutdown, which further intensified the effort of the LP&S program. In the LP&S program, one pressurized water reactor (PWR), Surry, and one boiling water reactor (BWR), Grand Gulf, were selected, mainly because they were previously analyzed in the NUREG-1150 Study. The Level-1 Program is being performed in two phases. Phase 1 was dedicated to performing a coarse screening level-1 analysis including internal fire and flood. A draft report was completed in November, 1991. In the phase 2 study, mid-loop operations at the Surry plant were analyzed in detail. The objective of this paper is to present the approach of the phase 2 study and the preliminary results and insights.

  18. Level 1 probabilistic risk assessment of low power and shutdown operations at a PWR: Phase 2 results

    SciTech Connect (OSTI)

    Chu, T.L.; Bozoki, G.; Kohut, P.; Musicki, Z.; Wong, S.M.; Yang, J.; Hsu, C.J.; Diamond, D.J.; Su, R.F. (Brookhaven National Lab., Upton, NY (United States)); Holmes, B. (AEA Technology, London (United Kingdom)); Siu, N. (Massachusetts Inst. of Tech., Cambridge, MA (United States)); Bley, D.; Lin, J. (Pickard, Lowe and Garrick, Inc., Newport Beach, CA (United States))

    1992-01-01

    As a result of the Chernobyl accident and other precursor events (e.g., Diablo Canyon), the US Nuclear Regulatory Commission's (NRC's) Office of Nuclear Regulatory Research (RES) initiated an extensive project during 1989 to carefully examine the potential risks during Low Power and Shutdown (LP S) operations. Shortly after the program began, an event occurred at the Vogtle plant during shutdown, which further intensified the effort of the LP S program. In the LP S program, one pressurized water reactor (PWR), Surry, and one boiling water reactor (BWR), Grand Gulf, were selected, mainly because they were previously analyzed in the NUREG-1150 Study. The Level-1 Program is being performed in two phases. Phase 1 was dedicated to performing a coarse screening level-1 analysis including internal fire and flood. A draft report was completed in November, 1991. In the phase 2 study, mid-loop operations at the Surry plant were analyzed in detail. The objective of this paper is to present the approach of the phase 2 study and the preliminary results and insights.

  19. Effects of Zircaloy oxidation and steam dissociation on PWR core heat-up under conditions simulating uncovered fuel rods

    SciTech Connect (OSTI)

    Viskanta, R.; Mohanty, A.K.

    1986-04-01

    The studies described in this report identify the regimes of slow transients in a partially uncovered core of a PWR. The threshold height and onset time for oxidation of the cladding of a fuel rod have been evaluated. The effects of oxidation in increasing the decay heat load, component temperature, reduction of cladding thickness and generation of hydrogen have been estimated. The condition for steam starvation has been determined. At high uncovered core heights, typically say 2.8 m for a geometry simulating the TMI-2 type of reactor, the solid and coolant temperatures can reach the limits of steam dissociation. The effects of radiation heat exchange between cladding and coolant, Zircaloy oxidation, steam dissociation, gap conductance between fuel and cladding and system pressure on the heatup of fuel rods have been investigated. The time for uncovering a certain core height is taken as the independent parameter. It is seen that if the uncovering process is allowed to continue beyond 9 minutes corresponding to an uncovered height of 1.9 m, onset of cladding oxidation can be a reality. These values provide a guideline for the response time of the emergency core cooling systems. 10 refs., 22 figs.

  20. Benchmark of SCALE (SAS2H) isotopic predictions of depletion analyses for San Onofre PWR MOX fuel

    SciTech Connect (OSTI)

    Hermann, O.W.

    2000-02-01

    The isotopic composition of mixed-oxide (MOX) fuel, fabricated with both uranium and plutonium, after discharge from reactors is of significant interest to the Fissile Materials Disposition Program. The validation of the SCALE (SAS2H) depletion code for use in the prediction of isotopic compositions of MOX fuel, similar to previous validation studies on uranium-only fueled reactors, has corresponding significance. The EEI-Westinghouse Plutonium Recycle Demonstration Program examined the use of MOX fuel in the San Onofre PWR, Unit 1, during cycles 2 and 3. Isotopic analyses of the MOX spent fuel were conducted on 13 actinides and {sup 148}Nd by either mass or alpha spectrometry. Six fuel pellet samples were taken from four different fuel pins of an irradiated MOX assembly. The measured actinide inventories from those samples has been used to benchmark SAS2H for MOX fuel applications. The average percentage differences in the code results compared with the measurement were {minus}0.9% for {sup 235}U and 5.2% for {sup 239}Pu. The differences for most of the isotopes were significantly larger than in the cases for uranium-only fueled reactors. In general, comparisons of code results with alpha spectrometer data had extreme differences, although the differences in the calculations compared with mass spectrometer analyses were not extremely larger than that of uranium-only fueled reactors. This benchmark study should be useful in estimating uncertainties of inventory, criticality and dose calculations of MOX spent fuel.

  1. Preliminary Notice of Violation, Westinghouse Savannah River...

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

    8, 2000 Issued to Westinghouse Savannah River Company, related to Unplanned Exposures and Radioactive Material Intakes at the Savannah River Site (EA-2000-08) On July 18, 2000, the...

  2. BITTERROOT RIVER SUBBASIN INVENTORY FOR FISH AND

    E-Print Network [OSTI]

    of the Columbia River hydropower system. Nothing in this Plan, or the participation in its development, or related to, the development and operation of the Columbia River hydropower system. Nothing in this Plan

  3. BITTERROOT RIVER SUBBASIN MANAGEMENT PLAN FOR FISH

    E-Print Network [OSTI]

    from the development and operation of the Columbia River hydropower system. Nothing in this Plan and exclusively resulting from, or related to, the development and operation of the Columbia River hydropower

  4. WAMweisman art museum 333 east river road

    E-Print Network [OSTI]

    Thomas, David D.

    WAMweisman art museum press release 333 east river road minneapolis, MN 55455 www government that allowed tax-supported institutions (like the University of Minnesota) to acquire these works: The Weisman is located at 333 E. River Road in

  5. INTEGRATED RIVER QUALITY MANAGEMENT USING INTERNET TECHNOLOGIES

    E-Print Network [OSTI]

    INTEGRATED RIVER QUALITY MANAGEMENT USING INTERNET TECHNOLOGIES P. Cianchi*, S. Marsili such a computing architecture can be implemented using current internet technologies. Based on the "intelligent a normal web browser. KEYWORDS River water quality, Environmental management, Internet computing, Systems

  6. Bureau Home > Australia> Queensland> Rainfall& River Conditions > River Brochures> Barron FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    in this document is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Warning and River Height Bulletins · Flood Classifications · Other Links Flood Risk The Barron River has a catchmentBureau Home > Australia> Queensland> Rainfall& River Conditions > River Brochures> Barron FLOOD

  7. Effect of spill on adult salmon passage delay at Columbia River and Snake River dams

    E-Print Network [OSTI]

    Washington at Seattle, University of

    Effect of spill on adult salmon passage delay at Columbia River and Snake River dams W. Nicholas dams in the Columbia/Snake River hydrosystem may delay the upstream passage of the adults. To evaluate-to-day variations of spill and upstream fish passage at the eight dams of the Columbia/Snake river hydrosystem

  8. In-River Backwards Run Reconstruction of Fraser River Sockeye Fisheries from 2002 -2009 and

    E-Print Network [OSTI]

    In-River Backwards Run Reconstruction of Fraser River Sockeye Fisheries from 2002 - 2009: Master of Resource Management Title of Research Project: In-River Backwards Run Reconstruction of Fraser managers I develop an in-river backwards run reconstruction to provide Conservation Unit (CU) specific

  9. Hydropower production and river rehabilitation: A case study on an alpine river

    E-Print Network [OSTI]

    Introduction For centuries, man has modified running waters [51]. In alpine rivers, production of hydropower of power plants are commonly in use: (1) run-of-river power plants that continuously pro- cessHydropower production and river rehabilitation: A case study on an alpine river M. Fette & C. Weber

  10. Grays River Watershed Geomorphic Analysis

    SciTech Connect (OSTI)

    Geist, David R.

    2005-04-30

    This investigation, completed for the Pacific Northwest National Laboratory (PNNL), is part of the Grays River Watershed and Biological Assessment commissioned by Bonneville Power Administration under project number 2003-013-00 to assess impacts on salmon habitat in the upper Grays River watershed and present recommendations for habitat improvement. This report presents the findings of the geomorphic assessment and is intended to support the overall PNNL project by evaluating the following: 􀂃 The effects of historical and current land use practices on erosion and sedimentation within the channel network 􀂃 The ways in which these effects have influenced the sediment budget of the upper watershed 􀂃 The resulting responses in the main stem Grays River upstream of State Highway 4 􀂃 The past and future implications for salmon habi

  11. Bayer Material Science (TRL 1 2 3 System)- River Devices to Recover Energy with Advanced Materials(River DREAM)

    Broader source: Energy.gov [DOE]

    Bayer Material Science (TRL 1 2 3 System) - River Devices to Recover Energy with Advanced Materials(River DREAM)

  12. Columbia River Component Data Evaluation Summary Report

    SciTech Connect (OSTI)

    C.S. Cearlock

    2006-08-02

    The purpose of the Columbia River Component Data Compilation and Evaluation task was to compile, review, and evaluate existing information for constituents that may have been released to the Columbia River due to Hanford Site operations. Through this effort an extensive compilation of information pertaining to Hanford Site-related contaminants released to the Columbia River has been completed for almost 965 km of the river.

  13. Diets of the Arkansas River Shiner and Peppered Chub in the Canadian River, New Mexico and Texas

    E-Print Network [OSTI]

    Wilde, Gene

    Diets of the Arkansas River Shiner and Peppered Chub in the Canadian River, New Mexico and Texas)collectedfrom the Canadian River in New Mexico andTexasfrom September1996to August 1998. Both the Ark~n~~ River streamsand rivers of the Arkansas River drainage systemof Arkansas,Colorado, Kansas,New Mexico, Kansas

  14. Rod consolidation of RG and E's (Rochester Gas and Electric Corporation) spent PWR (pressurized water reactor) fuel

    SciTech Connect (OSTI)

    Bailey, W.J.

    1987-05-01

    The rod consolidation demonstration involved pulling the fuel rods from five fuel assemblies from Unit 1 of RG and E's R.E. Ginna Nuclear Power Plant. Slow and careful rod pulling efforts were used for the first and second fuel assemblies. Rod pulling then proceeded smoothly and rapidly after some minor modifications were made to the UST and D consolidation equipment. The compaction ratios attained ranged from 1.85 to 2.00 (rods with collapsed cladding were replaced by dummy rods in one fuel assembly to demonstrate the 2:1 compaction ratio capability). This demonstration involved 895 PWR fuel rods, among which there were some known defective rods (over 50 had collapsed cladding); no rods were broken or dropped during the demonstration. However, one of the rods with collapsed cladding unexplainably broke during handling operations (i.e., reconfiguration in the failed fuel canister), subsequent to the rod consolidation demonstration. The broken rod created no facility problems; the pieces were encapsulated for subsequent storage. Another broken rod was found during postdemonstration cutting operations on the nonfuel-bearing structural components from the five assemblies; evidence indicates it was broken prior to any rod consolidation operations. During the demonstration, burnish-type lines or scratches were visible on the rods that were pulled; however, experience indicates that such lines are generally produced when rods are pulled (or pushed) through the spacer grids. Rods with collapsed cladding would not enter the funnel (the transition device between the fuel assembly and the canister that aids in obtaining high compaction ratios). Reforming of the flattened areas of the cladding on those rods was attempted to make the rod cross sections more nearly circular; some of the reformed rods passed through the funnel and into the canister.

  15. River System Hydrology in Texas 

    E-Print Network [OSTI]

    Wurbs, R.; Zhang, Y.

    2014-01-01

    and databases maintained by the Texas Water Development Board and the U.S. Geological Survey. River basin volume budgets and trend and frequency metrics for simulated naturalized and regulated stream flows and reservoir storage are developed using the WAM System...

  16. PWR FLECHT SEASET 163-Rod Bundle Flow Blockage Task data report. NRC/EPRI/Westinghouse report No. 13, August-October 1982

    SciTech Connect (OSTI)

    Loftus, M J; Hochreiter, L E; McGuire, M F; Valkovic, M M

    1983-10-01

    This report presents data from the 163-Rod Bundle Blow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Systems Effects and Separate Effects Test Program (FLECHT SEASET). The task consisted of forced and gravity reflooding tests utilizing electrical heater rods with a cosine axial power profile to simulate PWR nuclear core fuel rod arrays. These tests were designed to determine effects of flow blockage and flow bypass on reflooding behavior and to aid in the assessment of computational models in predicting the reflooding behavior of flow blockage in rod bundle arrays.

  17. Evaluation of the thermal-hydraulic response and fuel rod thermal and mechanical deformation behavior during the power burst facility test LOC-3. [PWR

    SciTech Connect (OSTI)

    Yackle, T.R.; MacDonald, P.E.; Broughton, J.M.

    1980-01-01

    An evaluation of the results from the LOC-3 nuclear blowdown test conducted in the Power Burst Facility is presented. The test objective was to examine fuel and cladding behavior during a postulated cold leg break accident in a pressurized water reactor (PWR). Separate effects of rod internal pressure and the degree of irradiation were investigated in the four-rod test. Extensive cladding deformation (ballooning) and failure occurred during blowdown. The deformation of the low and high pressure rods was similar; however, the previously irradiated test rod deformed to a greater extent than a similar fresh rod exposed to identical system conditions.

  18. Graphical and tabular summaries of decay characteristics for once-through PWR, LMFBR, and FFTF fuel cycle materials. [Spent fuel, high-level waste fuel can scrap

    SciTech Connect (OSTI)

    Croff, A.G.; Liberman, M.S.; Morrison, G.W.

    1982-01-01

    Based on the results of ORIGEN2 and a newly developed code called ORMANG, graphical and summary tabular characteristics of spent fuel, high-level waste, and fuel assembly structural material (cladding) waste are presented for a generic pressurized-water reactor (PWR), a liquid-metal fast breeder reactor (LMFBR), and the Fast Flux Test Facility (FFTF). The characteristics include radioactivity, thermal power, and toxicity (water dilution volume). Given are graphs and summary tables containing characteristic totals and the principal nuclide contributors as well as graphs comparing the three reactors for a single material and the three materials for a single reactor.

  19. Historical Shoreline Evolution as a Response to Dam Placement on the Elwha River, Washington

    E-Print Network [OSTI]

    Nagid, Bethany Marie

    2015-01-01

    of the Elwha River, Washington- Biological and physicalthe Elwha River, Washington, U.S. , Fisheries Management &on the Elwha River, Washington, USA: River channel and

  20. Upson Elec Member Corp | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page| Open Energy Information Serbia-EnhancingEt Al.,Turin, New York:Power CompanyCROSS-VALIDATIONSt.West

  1. Elec 331 -Sensors & Statistics Sensing Modes

    E-Print Network [OSTI]

    Pulfrey, David L.

    shift, etc. Example · Interfering / Modifying ­ Dirt on the lens ­ Coughing ­ Work boots ­ Bent needle

  2. ELEC 225: Lab 5 Low Pass Filters

    E-Print Network [OSTI]

    Kozick, Richard J.

    frequencies than at high frequencies is a low-pass filter. A circuit that has a larger output at high generator for sine-wave output with an amplitude of 2V peak-to-peak. Connect Channel 1 of the `scope to measure the output of the function generator. Connect Channel 2 to measure the voltage across

  3. ELEC 225, Fall 2011 Prof. Rich Kozick

    E-Print Network [OSTI]

    Kozick, Richard J.

    compared with high frequencies is a low-pass filter. A circuit that has a larger output amplitude for high frequencies. (Set the function generator for sine-wave output with an amplitude of 2V peak- to-peak.) Connect Channel 1 of the scope to measure the output of the function generator (VIN) and connect Channel 2

  4. ELEC 225, Fall 2012 Prof. Rich Kozick

    E-Print Network [OSTI]

    Kozick, Richard J.

    compared with high frequencies is a low-pass filter. A circuit that has a larger output amplitude for high frequencies. (Set the function generator for sine-wave output with an amplitude of 2V peak- to-peak.) Connect Channel 1 of the scope to measure the output of the function generator (VIN) and connect Channel 2

  5. Shenandoah Valley Elec Coop | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page| Open Energy Information Serbia-Enhancing Capacity for Low EmissionTianhongKansas:InformationZhen BicoShenandoah

  6. Intermountain Rural Elec Assn | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QAsource History View NewTexas: Energy ResourcesOrder at 8, 13Renewable Power Jump to: navigation, search Name:Assn

  7. Northern Virginia Elec Coop | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QAsource History ViewMayo, Maryland:NPI VenturesNew Hampshire:sourceNortheast

  8. Northern Virginia Elec Coop | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QAsource History ViewMayo, Maryland:NPI VenturesNew Hampshire:sourceNortheastNOVEC) Jump to: navigation, search

  9. Northwestern Wisconsin Elec Co | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop Inc Jump to:Newberg, Oregon: EnergyNongqishiClean CitiesWasco CountySEED Jump

  10. Rutherford Elec Member Corp | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop Inc Jump to:Newberg,EnergyEast JumpInformationstandards

  11. Southern Illinois Elec Coop | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop Inc JumpHeter BatterySolarfin JumpOpen EnergySoutheastern ElectricCAGen Co

  12. Stearns Cooperative Elec Assn | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION JEnvironmental Jump to:EA EIS ReportEurope GmbHSoloPageBefore the SenateHills

  13. Western Illinois Elec Coop | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION JEnvironmental Jump to:EA EISTJThinWarsaw, Poland:EnergyWeVirginiaElectric Assn Inc JumpWestern

  14. Alabama Municipal Elec Authority | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION JEnvironmental Jump to:EAand DaltonSolarOpen EnergyFebruary 2009 |

  15. Cumberland Elec Member Corp | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTIONRobertsdale, Alabama (Utility Company)|Alabama:Crofton,Developing andKentucky:Virginia:

  16. Illinois Municipal Elec Agency | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIXsource History View NewGuam:on Openei | Opensource History View NewInstitute for

  17. Western Massachusetts Elec Co | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop IncIowa (Utility Company)Idaho)VosslohWest Plains Electric CoopEnergy

  18. Eastern Illinois Elec Coop | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoopButtePower VenturesInformation9)askDoubleEERESoda Lake Geothermal

  19. Choctawhatche Elec Coop, Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoopButte County,Camilla,Thermal GradientChateau

  20. Northern Virginia Elec Coop | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIXsourceII Jump to:Information 3rd| OpenInformationConsortiumMinnesota

  1. Twin Rivers Technologies | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop IncIowa (Utility Company) Jump to:Tucson ElectricTurquoiseCounty Electric Pwr

  2. Savannah River Plant/Savannah River Laboratory radiation exposure report

    SciTech Connect (OSTI)

    Rogers, C.D.; Hyman, S.D.; Keisler, L.L. and Co., Aiken, SC . Savannah River Plant); Reeder, D.F.; Jolly, L.; Spoerner, M.T.; Schramm, G.R. and Co., Aiken, SC . Savannah River Lab.)

    1989-01-01

    The protection of worker health and safety is of paramount concern at the Savannah River Site. Since the site is one of the largest nuclear sites in the nation, radiation safety is a key element in the protection program. This report is a compendium of the results in 1988 of the programs at the Savannah River Plant and the Savannah River Laboratory to protect the radiological health of employees. By any measure, the radiation protection performance at this site in 1988 was the best since the beginning of operations. This accomplishment was made possible by the commitment and support at all levels of the organizations to reduce radiation exposures to ALARA (As Low As Reasonably Achievable). The report provides detailed information about the radiation doses received by departments and work groups within these organizations. It also includes exposure data for recent years to allow Plant and Laboratory units to track the effectiveness of their ALARA efforts. Many of the successful practices and methods that reduced radiation exposure are described. A new goal for personnel contamination cases has been established for 1989. Only through continual and innovative efforts to minimize exposures can the goals be met. The radiation protection goals for 1989 and previous years are included in the report. 27 figs., 58 tabs.

  3. Performance Spec. for Fuel Drying and Canister Inerting System for PWR Core 2 Blanket Fuel Assemblies Stored within Shipping Port Spent Fuel Canisters

    SciTech Connect (OSTI)

    JOHNSON, D.M.

    2000-03-14

    This specification establishes the performance requirements and basic design requirements imposed on the fuel drying and canister inerting system for Shippingport Pressurized Water Reactor (PWR) Core 2 blanket fuel assemblies (BFAs) stored within Shippingport spent fuel (SSFCs) canisters (fuel drying and canister inerting system). This fuel drying and canister inerting system is a component of the U.S. Department of Energy, Richland Operations Office (RL) Spent Nuclear Fuels Project at the Hanford Site. The fuel drying and canister inerting system provides for removing water and establishing an inert environment for Shippingport PWR Core 2 BFAs stored within SSFCs. A policy established by the U.S. Department of Energy (DOE) states that new SNF facilities (this is interpreted to include structures, systems and components) shall achieve nuclear safety equivalence to comparable U.S. Nuclear Regulatory Commission (NRC)-licensed facilities. This will be accomplished in part by applying appropriate NRC requirements for comparable NRC-licensed facilities to the fuel drying and canister inerting system, in addition to applicable DOE regulations and orders.

  4. Savannah River Laboratory Decontamination Program

    SciTech Connect (OSTI)

    Rankin, W.N.

    1991-01-01

    Savannah River Laboratory (SRL) has had a Decontamination and Decommissioning (D D) Technology program since 1981. The objective of this program is to provide state-of-the-art technology for use in D D operations that will enable our customers to minimize waste generated and personal exposure, increase productivity and safety, and to minimize the potential for release and uptake of radioactive material. The program identifies and evaluates existing technology, develops new technology, and provides technical assistance to implement its use onsite. This program has impacted not only the Savannah River Site (SRS), but the entire Department of Energy (DOE) complex. To document and communicate the technology generated by this program, 28 papers have been presented at National and International meetings in the United States and Foreign Countries.

  5. Savannah River Laboratory Decontamination Program

    SciTech Connect (OSTI)

    Rankin, W.N.

    1991-12-31

    Savannah River Laboratory (SRL) has had a Decontamination and Decommissioning (D&D) Technology program since 1981. The objective of this program is to provide state-of-the-art technology for use in D&D operations that will enable our customers to minimize waste generated and personal exposure, increase productivity and safety, and to minimize the potential for release and uptake of radioactive material. The program identifies and evaluates existing technology, develops new technology, and provides technical assistance to implement its use onsite. This program has impacted not only the Savannah River Site (SRS), but the entire Department of Energy (DOE) complex. To document and communicate the technology generated by this program, 28 papers have been presented at National and International meetings in the United States and Foreign Countries.

  6. Two-dimensional river modeling 

    E-Print Network [OSTI]

    Thompson, James Cameron

    1988-01-01

    heavily vegetated flood plain. It is found that the two-dimensional model can determine the flow more completely and more accurately than a corresponding one- dimensional model. Two-dimensional models are best applied where the flow conditions... committee, W. P. James, R. A. Wurbs, and R. 0. Reid, for their support and interest in this research. Dr. James, in particular, has shown great foresight in supporting broader use of two-dimensional river modeling. Dave Froehlich deserves much...

  7. Savannah River | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterestedReplacement-2-AA-1 SECTION JSTEM-ing theSummarySavannah River Site

  8. Raft River geoscience case study

    SciTech Connect (OSTI)

    Dolenc, M.R.; Hull, L.C.; Mizell, S.A.; Russell, B.F.; Skiba, P.A.; Strawn, J.A.; Tullis, J.A.

    1981-11-01

    The Raft River Geothermal Site has been evaluated over the past eight years by the United States Geological Survey and the Idaho National Engineering Laboratory as a moderate-temperature geothermal resource. The geoscience data gathered in the drilling and testing of seven geothermal wells suggest that the Raft River thermal reservoir is: (a) produced from fractures found at the contact metamorphic zone, apparently the base of detached normal faulting from the Bridge and Horse Well Fault zones of the Jim Sage Mountains; (b) anisotropic, with the major axis of hydraulic conductivity coincident to the Bridge Fault Zone; (c) hydraulically connected to the shallow thermal fluid of the Crook and BLM wells based upon both geochemistry and pressure response; (d) controlled by a mixture of diluted meteoric water recharging from the northwest and a saline sodium chloride water entering from the southwest. Although the hydrogeologic environment of the Raft River geothermal area is very complex and unique, it is typical of many Basin and Range systems.

  9. Deep drilling data, Raft River geothermal area, Idaho-Raft River...

    Open Energy Info (EERE)

    Deep drilling data, Raft River geothermal area, Idaho-Raft River geothermal exploration well sidetrack-C Jump to: navigation, search OpenEI Reference LibraryAdd to library Report:...

  10. The Columbia River System : the Inside Story.

    SciTech Connect (OSTI)

    United States. Bonneville Power Administration.

    1991-09-01

    The Columbia Ricer is one of the greatest natural resources in the western United States. The river and its tributaries touch the lives of nearly every resident of the Northwest-from providing the world-famous Pacific salmon to supplying the clean natural fuel for over 75 percent of the region's electrical generation. Since early in the century, public and private agencies have labored to capture the benefits of this dynamic river. Today, dozens of major water resource projects throughout the region are fed by the waters of the Columbia Basin river system. And through cooperative efforts, the floods that periodically threaten developments near the river can be controlled. This publication presents a detailed explanation of the planning and operation of the multiple-use dams and reservoirs of the Columbia River system. It describes the river system, those who operate and use it, the agreements and policies that guide system operation, and annual planning for multiple-use operation.

  11. Green River Locks and Dams 3, 4, 5, 6 and Barren River Lock and Dam 1 Disposition, Kentucky

    E-Print Network [OSTI]

    US Army Corps of Engineers

    Green River Locks and Dams 3, 4, 5, 6 and Barren River Lock and Dam 1 Disposition, Kentucky 16 September 2014 ABSTRACT: Green River Locks and Dams 3 through 6 and Barren River Lock and Dam 1 were. The Green River Locks and Dams 5 and 6 ceased operations in 1951 due to a marked decline in navigation

  12. North University Dr. Indian River Street

    E-Print Network [OSTI]

    Marques, Oge

    ) around campus and running path on Indian River Street. Participants MUST run WITH tra c on all roads 39 4 31B 31A 7636 8W 6 80 46 89 92 31E 31 31D 31C 81 49 North University Dr. Indian River Street B-04.LucieAve.South Indian River St. BrevardCt. BrevardCt. Lot 23 Lot 22 Lot 11 Lot 7 Lot 6 Lot 21 LakeFPL Substation Lot 9

  13. The Columbia River System Inside Story

    SciTech Connect (OSTI)

    none,

    2001-04-01

    The Columbia River is one of the greatest natural resources in the western United States. The river and its tributaries touch the lives of nearly every resident of the Pacific Northwest—from fostering world-famous Pacific salmon to supplying clean natural fuel for 50 to 65 percent of the region’s electrical generation. Since early in the 20th century, public and private agencies have labored to capture the benefits of this dynamic river. Today, dozens of major water resource projects throughout the region are fed by the waters of the Columbia Basin river system.

  14. New Columbia River Estuary purchases benefit salmon

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

    the mouth of the Columbia River to permanently protect riverside habitat for Northwest fish and wildlife, including threatened and endangered salmon and steelhead. The...

  15. Microsoft Word - CROOKED RIVER VALLEY REHABILITATION PROJECT...

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

    Power Act). Among other things, this Act directs BPA to protect, mitigate, and enhance fish and wildlife affected by the development and operation of the Federal Columbia River...

  16. River Falls Municipal Utilities - Residential Energy Efficiency...

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

    Name Utility Administrator River Falls Municipal Utilities Website http:www.rfmu.orgindex.aspx?nid681 Funding Source Wisconsin Focus on Energy State Wisconsin Program Type...

  17. Lumbee River EMC- Residential Energy Efficiency Program

    Broader source: Energy.gov [DOE]

    Lumbee River EMC (LREMC) offers rebates to its residential customers who purchase and install qualified energy efficient products or services. Rebates are available for water heaters, refrigerator...

  18. Voluntary Protection Program Onsite Review, Washington River...

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

    February 13, 2014 Evaluation to determine whether Washington River Protection Solutions, LLC, Hanford is performing at a level deserving DOE-VPP Star recognition. Voluntary...

  19. Cuivre River Electric- Energy Efficiency Rebate Programs

    Broader source: Energy.gov [DOE]

    Cuivre River Electric Cooperative, through the Take Control & Save program, offers rebates for cooperative members who purchase efficient geothermal and dual fuel heat pumps, and electric water...

  20. Savannah River Laboratory monthly report, October 1991

    SciTech Connect (OSTI)

    Ferrell, J.M.

    1991-01-01

    This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation, tritium facilities and production; separations operations; environmental concerns; and waste management. (FI)

  1. Savannah River Laboratory monthly report, October 1991

    SciTech Connect (OSTI)

    Ferrell, J.M.

    1991-12-31

    This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation, tritium facilities and production; separations operations; environmental concerns; and waste management. (FI)

  2. Savannah River National Laboratory (SRNL) Environmental Sciences...

    Office of Environmental Management (EM)

    (SRNL) Environmental Sciences and Biotechnology Support of Waste Isolation Pilot Plant (WIPP) Savannah River National Laboratory (SRNL) Environmental Sciences and Biotechnology...

  3. Gila River Indian Community- 2012 Project

    Broader source: Energy.gov [DOE]

    The Gila River Indian Community (GRIC) will conduct feasibility studies of potential renewable energy projects on its lands in south central Arizona.

  4. ENVIRONMENTAL SCIENCES; SAVANNAH RIVER PLANT; ENVIRONMENTAL EFFECTS...

    Office of Scientific and Technical Information (OSTI)

    5 audit of SRP radioactive waste Ashley, C. 05 NUCLEAR FUELS; 54 ENVIRONMENTAL SCIENCES; SAVANNAH RIVER PLANT; ENVIRONMENTAL EFFECTS; RADIOACTIVE EFFLUENTS; EMISSION; HIGH-LEVEL...

  5. Savannah River Laboratory monthly report, November 1991

    SciTech Connect (OSTI)

    Ferrell, J.M.

    1991-12-31

    This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation; tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

  6. Savannah River Laboratory monthly report, November 1991

    SciTech Connect (OSTI)

    Ferrell, J.M.

    1991-01-01

    This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation; tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

  7. Savannah River Laboratory monthly report, September 1991

    SciTech Connect (OSTI)

    Ferrell, J.M.

    1991-01-01

    This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation, tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

  8. Savannah River Laboratory monthly report, September 1991

    SciTech Connect (OSTI)

    Ferrell, J.M.

    1991-12-31

    This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation, tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

  9. Savannah River Laboratory monthly report, July 1991

    SciTech Connect (OSTI)

    Ferrell, J.M.

    1991-01-01

    This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation; tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

  10. Savannah River Laboratory monthly report, July 1991

    SciTech Connect (OSTI)

    Ferrell, J.M.

    1991-12-31

    This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation; tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

  11. Savannah River Laboratory monthly report, August 1991

    SciTech Connect (OSTI)

    Ferrell, J.M.

    1991-12-31

    This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation, tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

  12. Savannah River Laboratory monthly report, August 1991

    SciTech Connect (OSTI)

    Ferrell, J.M.

    1991-01-01

    This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation, tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

  13. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Kolan FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Forecasting · Local Classifications · Other Links Flood Risk The Kolan River catchment is located in south east Queensland and coversBureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Kolan FLOOD

  14. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Bulloo FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    in this document is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Bulletins · Flood Classifications · Other Links Flood Risk The Bulloo River catchment is located in southBureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Bulloo FLOOD

  15. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Noosa FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Forecasting · Local Height Bulletins · Flood Classifications · Other Links Flood Risk The Noosa River has a catchment areaBureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Noosa FLOOD

  16. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Burrum and Cherwell

    E-Print Network [OSTI]

    Greenslade, Diana

    River at Howard Contained in this document is information about: (Last updated June 2015) · Flood Risk · Other Links Flood Risk The Burrum River catchment covers an area of about 935 square kilometres which and Cherwell FLOOD WARNING SYSTEM for the BURRUM AND CHERWELL RIVERS This brochure describes the flood warning

  17. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    Contained in this document is information about: (Last updated June 2015) · Flood Risk · Previous Flooding and River Height Bulletins · Flood Classifications · Other Links Flood Risk The Leichhardt River catchment FLOOD WARNING SYSTEM for the LEICHHARDT RIVER This brochure describes the flood warning system operated

  18. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Paroo FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    is information about : (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Forecasting · Local Classifications · Other Links Flood Risk The Paroo River catchment is located in south west Queensland and coversBureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Paroo FLOOD

  19. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Lower FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    2015) · Flood Risk · Previous Flooding · Flood Forecasting · Local Information · Brisbane River ALERT Classifications · Other Links Flood Risk The Brisbane River catchment covers an area of approximately 15 Brisbane FLOOD WARNING SYSTEM for the BRISBANE RIVER BELOW WIVENHOE DAM TO BRISBANE CITY This brochure

  20. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Moonie FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    is information about : (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Forecasting · Local Classifications · Other Links Flood Risk The Moonie River basin is located in southwest Queensland and drainsBureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Moonie FLOOD

  1. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Daintree FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    Post Contained in this document is information about: (Last updated June 2015) · Flood Risk · Previous Warnings and River Height Bulletins · Flood Classifications · Other Links Flood Risk The Daintree River FLOOD WARNING SYSTEM for the DAINTREE RIVER This brochure describes the flood warning system operated

  2. Bureau Home > Australia> Queensland> Rainfall& River Conditions > River Brochures> Gilbert FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    in this document is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Bulletins · Flood Classifications · Other Links Flood Risk The Gilbert River catchment is located in northBureau Home > Australia> Queensland> Rainfall& River Conditions > River Brochures> Gilbert FLOOD

  3. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Haughton FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    in this document is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Warnings and River Height Bulletins · Flood Classifications · Other Links Flood Risk The Haughton River FLOOD WARNING SYSTEM for the HAUGHTON RIVER This brochure describes the flood warning system operated

  4. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Bremer FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    Contained in this document is information about: (Last updated June 2015) · Flood Risk · Previous Flooding Flood Warnings and River Height Bulletins · Flood Classifications · Other Links Flood Risk The BremerBureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Bremer FLOOD

  5. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Pine and FLOOD SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    and Caboolture FLOOD SYSTEM for the PINE & CABOOLTURE RIVERS This brochure describes the flood system operated information which will be useful for understanding River Height Bulletins issued by the Bureau's Flood Warning Centre during periods of high rainfall and flooding. Pine River at Murrumba Downs Contained

  6. Microbial risk assessment for recreational use of the Malden River

    E-Print Network [OSTI]

    Jacques, Margaret (Margaret Rose)

    2015-01-01

    The Malden River is located in the Greater Boston area of Massachusetts. The River has a long history of abuse and neglect stemming from urbanization and industrial activity along the River and in the surrounding areas. ...

  7. Lesson Learned by Savannah River Site Activity-level Work Planning and Control

    Broader source: Energy.gov [DOE]

    Slide Presentation by Bonnie Barnes, Savannah River Remediation. Work Planning and Control at Savannah River Remediation.

  8. CRAD, Emergency Management - Office of River Protection K Basin...

    Energy Savers [EERE]

    CRAD, Emergency Management - Office of River Protection K Basin Sludge Waste System CRAD, Emergency Management - Office of River Protection K Basin Sludge Waste System May 2004 A...

  9. Letter from Commonwealth to Mirant Potomac River Concerning Serious...

    Office of Environmental Management (EM)

    to Mirant Potomac River Concerning Serious Violations of the National Ambient Air Quality Standards for Sulfur Dioxide Letter from Commonwealth to Mirant Potomac River Concerning...

  10. Savannah River Site - Mixed Waste Management Facility Northwest...

    Energy Savers [EERE]

    state determination for entire site. Addthis Related Articles Savannah River Site - Mixed Waste Management Facility Northeast Plume Savannah River Site - D-Area Oil Seepage Basin...

  11. Savannah River Site - Mixed Waste Management Facility Northeast...

    Energy Savers [EERE]

    state determination for entire site. Addthis Related Articles Savannah River Site - Mixed Waste Management Facility Northwest Plume Savannah River Site - D-Area Oil Seepage Basin...

  12. Columbia River Treaty Review #2 - April 2009.indd

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

    the Columbia River Treaty has provided signifi cant benefi ts to the United States and Canada through coordinated river management by the two countries. It remains the standard...

  13. Lessons Learned and Best Practices in Savannah River Site Saltstone...

    Office of Environmental Management (EM)

    Lessons Learned and Best Practices in Savannah River Site Saltstone and Tank Farm Performance Assessments Lessons Learned and Best Practices in Savannah River Site Saltstone and...

  14. Trona Injection Tests: Mirant Potomac River Station, Unit 1,...

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

    Trona Injection Tests: Mirant Potomac River Station, Unit 1, November 12 to December 23, 2005, Summary Report Trona Injection Tests: Mirant Potomac River Station, Unit 1, November...

  15. Exhibit D: Mirant Potomac River Schedule of Unit Operations:...

    Office of Environmental Management (EM)

    Exhibit D: Mirant Potomac River Schedule of Unit Operations: Supplement 4, January - March 2006 Exhibit D: Mirant Potomac River Schedule of Unit Operations: Supplement 4, January -...

  16. CRAD, Engineering - Office of River Protection K Basin Sludge...

    Energy Savers [EERE]

    CRAD, Engineering - Office of River Protection K Basin Sludge Waste System CRAD, Engineering - Office of River Protection K Basin Sludge Waste System May 2004 A section of Appendix...

  17. Savannah River Field Office | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Us Our Operations Management and Budget Office of Civil Rights Workforce Statistics Savannah River Field Office Savannah River Field Office FY15 Semi Annual Report...

  18. 2013 Annual Planning Summary for the Office of River Protection...

    Energy Savers [EERE]

    River Protection and Richland Operations Office 2013 Annual Planning Summary for the Office of River Protection and Richland Operations Office The ongoing and projected...

  19. LiT Electrolysis Research at Savannah River National Laboratory...

    Office of Environmental Management (EM)

    LiT Electrolysis Research at Savannah River National Laboratory (SRNL) LiT Electrolysis Research at Savannah River National Laboratory (SRNL) Presentation from the 35th Tritium...

  20. PIA - Savannah River Nuclear Solutions (SRNS) Human Resource...

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

    (SRNS) Human Resource Management System (HRMS) PIA - Savannah River Nuclear Solutions (SRNS) Human Resource Management System (HRMS) PIA - Savannah River Nuclear Solutions (SRNS)...

  1. PIA - Savannah River Nuclear Solutions Training Records and Informatio...

    Energy Savers [EERE]

    Nuclear Solutions Training Records and Information Network (TRAIN) PIA - Savannah River Nuclear Solutions Training Records and Information Network (TRAIN) PIA - Savannah River...

  2. PIA - Savannah River Nuclear Solutions Badge Request and Site...

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

    Badge Request and Site Personnel Roster Systems PIA - Savannah River Nuclear Solutions Badge Request and Site Personnel Roster Systems PIA - Savannah River Nuclear Solutions Badge...

  3. PIA - Savannah River Nuclear Solution SRNS ProRad Environment...

    Energy Savers [EERE]

    SRNS ProRad Environment Management PIA - Savannah River Nuclear Solution SRNS ProRad Environment Management PIA - Savannah River Nuclear Solution SRNS ProRad Environment Management...

  4. Independent Oversight Review, Savannah River Site Tritium Facilities...

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

    June 2012 Independent Oversight Review, Savannah River Site Tritium Facilities - June 2012 June 2012 Review of the Savannah River Site Tritium Facilities Implementation...

  5. EA-1973: Kootenai River Restoration at Bonners Ferry, Boundary...

    Energy Savers [EERE]

    73: Kootenai River Restoration at Bonners Ferry, Boundary County, Idaho EA-1973: Kootenai River Restoration at Bonners Ferry, Boundary County, Idaho Summary Bonneville Power...

  6. Independent Oversight Activity Report, Savannah River Site Waste...

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

    Report, Savannah River Site Waste Solidification Building May 2013 Savannah River Site Waste Solidification Building Corrective Actions from the January 2013 Report on...

  7. Raft River Geothermal Area Data Models - Conceptual, Logical...

    Open Energy Info (EERE)

    Tables, Figures and other Content in Reports from the Raft River Geothermal Project: "Technical Report on the Raft River Geothermal Resource, Cassia County, Idaho," GeothermEx,...

  8. UVA Hydraulic and Transport Engineering Lab for Sustainable River Resources

    E-Print Network [OSTI]

    Zhigilei, Leonid V.

    #12;UVA Hydraulic and Transport Engineering Lab for Sustainable River Resources Some Applications: Small and Large Dam Removal River Restoration / Rehabilitation In Stream Flow Calculation Stormwater

  9. Employee of Savannah River Site Contractor Recognized as Exemplary...

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

    Employee of Savannah River Site Contractor Recognized as Exemplary in Safety and Health Employee of Savannah River Site Contractor Recognized as Exemplary in Safety and Health...

  10. Hood River Passive House, Hood River, Oregon (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2014-02-01

    The Hood River Passive Project was developed by Root Design Build of Hood River Oregon using the Passive House Planning Package (PHPP) to meet all of the requirements for certification under the European Passive House standards. The Passive House design approach has been gaining momentum among residential designers for custom homes and BEopt modeling indicates that these designs may actually exceed the goal of the U.S. Department of Energy's (DOE) Building America program to "reduce home energy use by 30%-50%" (compared to 2009 energy codes for new homes). This report documents the short term test results of the Shift House and compares the results of PHPP and BEopt modeling of the project. The design includes high R-Value assemblies, extremely tight construction, high performance doors and windows, solar thermal DHW, heat recovery ventilation, moveable external shutters and a high performance ductless mini-split heat pump. Cost analysis indicates that many of the measures implemented in this project did not meet the BA standard for cost neutrality. The ductless mini-split heat pump, lighting and advanced air leakage control were the most cost effective measures. The future challenge will be to value engineer the performance levels indicated here in modeling using production based practices at a significantly lower cost.

  11. Savannah River Site dose control

    SciTech Connect (OSTI)

    Smith, L.S.

    1992-06-01

    Health physicists from the Brookhaven National Laboratory (BNL) visited the Savannah River Site (SRS) as one of 12 facilities operated by the Department of Energy (DOE) contractors with annual collective dose equivalents greater than 100 person-rem (100 person-cSv). Their charter was to review, evaluate and summarize as low as reasonably achievable (ALARA) techniques, methods and practices as implemented. This presentation gives an overview of the two selected ALARA practices implemented at the SRS: Administrative Exposure Limits and Goal Setting. These dose control methods are used to assure that individual and collective occupational doses are ALARA and within regulatory limits.

  12. Decay Heat Calculations for PWR and BWR Assemblies Fueled with Uranium and Plutonium Mixed Oxide Fuel using SCALE

    SciTech Connect (OSTI)

    Ade, Brian J; Gauld, Ian C

    2011-10-01

    In currently operating commercial nuclear power plants (NPP), there are two main types of nuclear fuel, low enriched uranium (LEU) fuel, and mixed-oxide uranium-plutonium (MOX) fuel. The LEU fuel is made of pure uranium dioxide (UO{sub 2} or UOX) and has been the fuel of choice in commercial light water reactors (LWRs) for a number of years. Naturally occurring uranium contains a mixture of different uranium isotopes, primarily, {sup 235}U and {sup 238}U. {sup 235}U is a fissile isotope, and will readily undergo a fission reaction upon interaction with a thermal neutron. {sup 235}U has an isotopic concentration of 0.71% in naturally occurring uranium. For most reactors to maintain a fission chain reaction, the natural isotopic concentration of {sup 235}U must be increased (enriched) to a level greater than 0.71%. Modern nuclear reactor fuel assemblies contain a number of fuel pins potentially having different {sup 235}U enrichments varying from {approx}2.0% to {approx}5% enriched in {sup 235}U. Currently in the United States (US), all commercial nuclear power plants use UO{sub 2} fuel. In the rest of the world, UO{sub 2} fuel is still commonly used, but MOX fuel is also used in a number of reactors. MOX fuel contains a mixture of both UO{sub 2} and PuO{sub 2}. Because the plutonium provides the fissile content of the fuel, the uranium used in MOX is either natural or depleted uranium. PuO{sub 2} is added to effectively replace the fissile content of {sup 235}U so that the level of fissile content is sufficiently high to maintain the chain reaction in an LWR. Both reactor-grade and weapons-grade plutonium contains a number of fissile and non-fissile plutonium isotopes, with the fraction of fissile and non-fissile plutonium isotopes being dependent on the source of the plutonium. While only RG plutonium is currently used in MOX, there is the possibility that WG plutonium from dismantled weapons will be used to make MOX for use in US reactors. Reactor-grade plutonium in MOX fuel is generally obtained from reprocessed irradiated nuclear fuel, whereas weapons-grade plutonium is obtained from decommissioned nuclear weapons material and thus has a different plutonium (and other actinides) concentration. Using MOX fuel instead of UOX fuel has potential impacts on the neutronic performance of the nuclear fuel and the design of the nuclear fuel must take these differences into account. Each of the plutonium sources (RG and WG) has different implications on the neutronic behavior of the fuel because each contains a different blend of plutonium nuclides. The amount of heat and the number of neutrons produced from fission of plutonium nuclides is different from fission of {sup 235}U. These differences in UOX and MOX do not end at discharge of the fuel from the reactor core - the short- and long-term storage of MOX fuel may have different requirements than UOX fuel because of the different discharged fuel decay heat characteristics. The research documented in this report compares MOX and UOX fuel during storage and disposal of the fuel by comparing decay heat rates for typical pressurized water reactor (PWR) and boiling water reactor (BWR) fuel assemblies with and without weapons-grade (WG) and reactor-grade (RG) MOX fuel.

  13. FLOOD RESPONSE PLAN River Flood Guide

    E-Print Network [OSTI]

    Lennard, William N.

    1 FLOOD RESPONSE PLAN River Flood Guide Effective Date: January 2013 Updated: February 2014 #12 Thames River basin have the potential to cause flooding on Western properties. PURPOSE To establish areas) closing of parking lots and clearing of parked vehicles and other Western property in flood

  14. The State of the Columbia River Basin

    E-Print Network [OSTI]

    1 The State of the Columbia River Basin Draft Fiscal Year 2009 ANNUAL REPORT To Congress and fish and wildlife policy in the Columbia River Basin and to inform the public about energy and fish Basin, and a synopsis of the major activities of the Council during the fiscal year ending September 30

  15. BLUE RIVER BASIN (Dodson Industrial District)

    E-Print Network [OSTI]

    US Army Corps of Engineers

    BLUE RIVER BASIN (Dodson Industrial District) Kansas City, Missouri MODIFICATION REQUEST capability to support this request. PROJECT PURPOSE Dodson Industrial District is located along the Blue of a 6,800 foot long levee- floodwall along the north bank of the Blue River from the Bannister Road

  16. 2010 Expenditures Report Columbia River Basin Fish

    E-Print Network [OSTI]

    tables 27 Table 1A: Total Cost of BPA Fish & Wildlife Actions 29 Table 1B: Cumulative Expenditures 1978 and habitat, of the Columbia River Basin that have been affected by hydroelectric development. This program fish and wildlife affected by hydropower dams in the Columbia River Basin. The Power Act requires

  17. Fast Facts About the Columbia River Basin

    E-Print Network [OSTI]

    cost and availability, and the effect of the hydropower system on fish and wildlife. columbia River, and fish and wildlife affected by, the columbia River Basin hydropower dams. the council is a unique of the Council under the Act are to: 1. Develop a regional power plan to assure the Northwest an adequate

  18. Prospective Climate Change Impact on Large Rivers

    E-Print Network [OSTI]

    Julien, Pierre Y.

    1 Prospective Climate Change Impact on Large Rivers in the US and South Korea Pierre Y. Julien Dept. of Civil and Environ. Eng. Colorado State University Seoul, South Korea August 11, 2009 Climate Change and Large Rivers 1. Climatic changes have been on-going for some time; 2. Climate changes usually predict

  19. Savannah River Site Environmental Report for 1998

    SciTech Connect (OSTI)

    Arnett, M.

    1999-06-09

    The mission at the Savannah River Site (SRS) is focused primarily on support of the national defense, nonproliferation, and environmental cleanup. SRS-through its prime operating contractor, Westinghouse Savannah River Company-continues to maintain a comprehensive environmental monitoring program.

  20. Financial Sustainability of International River Basin Organizations

    E-Print Network [OSTI]

    Wolf, Aaron

    Financial Sustainability of International River Basin Organizations Final Report #12;Published by financing of a sample of African, Asian and European River Basin Organizations (RBOs). Its focus contributions to cov- er their regular run-ning costs. To a degree, the financial challenges some African RBOs

  1. WAMweisman art museum 333 east river road

    E-Print Network [OSTI]

    Thomas, David D.

    WAMweisman art museum press release 333 east river road minneapolis, MN 55455 www per person (current Individual and Dual level members) FREE for members at the Sustainer level: The Weisman is located at 333 E. River Road in Minneapolis. There is no admission fee to the Weisman

  2. Interannual variations of river water storage from a multiple satellite approach: A case study for the Rio Negro River basin

    E-Print Network [OSTI]

    Frappart, Frédéric; Papa, Fabrice; Famiglietti, James S; Prigent, Catherine; Rossow, William B; Seyler, Frédérique

    2008-01-01

    satellite track runs along the river. As T/P cross track (orthe T/P tracks run parallel to the river. In these cases,

  3. Corrosion and hydriding performance evaluation of three zircaloy-2 clad fuel assemblies after continuous exposure in PWR cores 1 and 2, at Shippingport, PA

    SciTech Connect (OSTI)

    Hillner, E.

    1980-01-01

    Three original Zircaloy-2 clad blanket fuel bundles from the pressurized water reactor (PWR) at the Shippingport Atomic Power Station were discharged after continuous exposure during Cores 1 and 2. Detailed visual examination of these components after approx. 6300 calendar days of operation (51,140 EFPH) revealed only the anticipated uniform light gray (post-transition) corrosion products with no evidence of unexpected corrosion deterioration, fuel rod warpage, or other damage. All corrosion films were found to be tightly adherent to the underlying cladding. An extensive destructive examination of a selected fuel rod from each of three fuel bundles produced appreciably greater end-of-life rod average oxide film thickness when compared with corresponding values produced from a set of empirical equations generated from the out-of-pile (autoclave) testing of Zircaloy coupons.

  4. PWR FLECHT SEASET 21-rod bundle flow blockage task data and analysis report. NRC/EPRI/Westinghouse Report No. 11. Appendices K-P

    SciTech Connect (OSTI)

    Loftus, M.J.; Hochreiter, L.E.; Lee, N.; McGuire, M.F.; Wenzel, A.H.; Valkovic, M.M.

    1982-09-01

    This report presents data and limited analysis from the 21-Rod Bundle Flow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Separate Effects and Systems Effects Test Program (FLECHT SEASET). The tests consisted of forced and gravity reflooding tests utilizing electrical heater rods with a cosine axial power profile to simulate PWR nuclear core fuel rod arrays. Steam cooling and hydraulic characteristics tests were also conducted. These tests were utilized to determine effects of various flow blockage configurations (shapes and distributions) on reflooding behavior, to aid in development/assessment of computational models in predicting reflooding behavior of flow blockage configurations, and to screen flow blockage configurations for future 163-rod flow blockage bundle tests.

  5. Yellow River Water and Hydropower Development Corp | Open Energy

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX ECoop IncIowa (UtilityMichigan) Jump to: Name:XinjiangPupingYanyuanValley Elec

  6. Crack growth rates and metallographic examinations of Alloy 600 and Alloy 82/182 from field components and laboratory materials tested in PWR environments.

    SciTech Connect (OSTI)

    Alexandreanu, B.; Chopra, O. K.; Shack, W. J.

    2008-05-05

    In light water reactors, components made of nickel-base alloys are susceptible to environmentally assisted cracking. This report summarizes the crack growth rate results and related metallography for field and laboratory-procured Alloy 600 and its weld alloys tested in pressurized water reactor (PWR) environments. The report also presents crack growth rate (CGR) results for a shielded-metal-arc weld of Alloy 182 in a simulated PWR environment as a function of temperature between 290 C and 350 C. These data were used to determine the activation energy for crack growth in Alloy 182 welds. The tests were performed by measuring the changes in the stress corrosion CGR as the temperatures were varied during the test. The difference in electrochemical potential between the specimen and the Ni/NiO line was maintained constant at each temperature by adjusting the hydrogen overpressure on the water supply tank. The CGR data as a function of temperature yielded activation energies of 252 kJ/mol for a double-J weld and 189 kJ/mol for a deep-groove weld. These values are in good agreement with the data reported in the literature. The data reported here and those in the literature suggest that the average activation energy for Alloy 182 welds is on the order of 220-230 kJ/mol, higher than the 130 kJ/mol commonly used for Alloy 600. The consequences of using a larger value of activation energy for SCC CGR data analysis are discussed.

  7. The impact of fuel cladding failure events on occupational radiation exposures at nuclear power plants: Case study, PWR (pressurized-water reactor) during an outage

    SciTech Connect (OSTI)

    Moeller, M.P.; Martin, G.F.; Kenoyer, J.L.

    1987-08-01

    This report is the second in a series of case studies designed to evaluate the magnitude of increase in occupational radiation exposures at commercial US nuclear power plants resulting from small incidents or abnormal events. The event evaluated is fuel cladding failure, which can result in elevated primary coolant activity and increased radiation exposure rates within a plant. For this case study, radiation measurements were made at a pressurized-water reactor (PWR) during a maintenance and refueling outage. The PWR had been operating for 22 months with fuel cladding failure characterized as 105 pin-hole leakers, the equivalent of 0.21% failed fuel. Gamma spectroscopy measurements, radiation exposure rate determinations, thermoluminescent dosimeter (TLD) assessments, and air sample analyses were made in the plant's radwaste, pipe penetration, and containment buildings. Based on the data collected, evaluations indicate that the relative contributions of activation products and fission products to the total exposure rates were constant over the duration of the outage. This constancy is due to the significant contribution from the longer-lived isotopes of cesium (a fission product) and cobalt (an activation product). For this reason, fuel cladding failure events remain as significant to occupational radiation exposure during an outage as during routine operations. As documented in the previous case study (NUREG/CR-4485 Vol. 1), fuel cladding failure events increased radiation exposure rates an estimated 540% at some locations of the plant during routine operations. Consequently, such events can result in significantly greater radiation exposure rates in many areas of the plant during the maintenance and refueling outages than would have been present under normal fuel conditions.

  8. River 

    E-Print Network [OSTI]

    Unknown

    2011-09-05

    ............................................................ 29 14 Alluvial fans along the Guadalupe Mountains in Big Dog Canyon........ 31 15 Alluvial fans along the Brokeoff Mountains in Big Dog Canyon........... 35 16 View of alluvial fans from their drainage basins.................................. 75 27 Salt Basin-Brokeoff Mountains alluvial fan group ................................. 76 28 Big Dog Canyon-Brokeoff Mountains alluvial fan group....................... 77 29 Big Dog Canyon-Guadalupe Mountains alluvial fan group...

  9. Neuse River Basin, North Carolina Ecosystem Restoration Project

    E-Print Network [OSTI]

    US Army Corps of Engineers

    Neuse River Basin, North Carolina Ecosystem Restoration Project 5 October 2012 ABSTRACT: The study area encompasses the Neuse River Basin, the third-largest river basin in North Carolina. The Basin, upstream of the city of New Bern, North Carolina. At New Bern the river broadens dramatically and changes

  10. Willamette River Transit Bridge PSU CTS Seminar January 16, 2009

    E-Print Network [OSTI]

    Bertini, Robert L.

    Willamette River Transit Bridge PSU CTS Seminar January 16, 2009 Dave Unsworth, TriMet Guenevere River Transit Bridge · Portland-Milwaukie Light Rail Project · Plans for a new Willamette River Bridge · Public Process Today's Agenda #12;Willamette River Transit BridgePortland-Milwaukie Light Rail Project

  11. Independent Oversight Inspection, Savannah River Site- December 2009

    Office of Energy Efficiency and Renewable Energy (EERE)

    Inspection of Reinforced Concrete Construction at the Savannah River Site Mixed Oxide Fuel Fabrication Facility

  12. Independent Oversight Inspection, Savannah River Site, Summary Report- February 2004

    Broader source: Energy.gov [DOE]

    Inspection of Environment, Safety, and Health Management and Emergency Management at the Savannah River Site

  13. River Data Package for Hanford Assessments

    SciTech Connect (OSTI)

    Rakowski, Cynthia L.; Guensch, Gregory R.; Patton, Gregory W.

    2006-08-01

    This data package documents the technical basis for selecting physical and hydraulic parameters and input values that will be used in river modeling for Hanford assessments. This work was originally conducted as part of the Characterization of Systems Task of the Groundwater Remediation Project managed by Fluor Hanford, Inc. and revised as part of the Characterization of Systems Project managed by PNNL for DOE. The river data package provides calculations of flow and transport in the Columbia River system. The module is based on the legacy code for the Modular Aquatic Simulation System II (MASS2), which is a two-dimensional, depth-averaged model that provides the capability to simulate the lateral (bank-to-bank) variation of flow and contaminants. It simulates river hydrodynamics (water velocities and surface elevations), sediment transport, contaminant transport, biotic transport, and sediment-contaminant interaction, including both suspended sediments and bed sediments. This document presents the data assembled to run the river module components for the section of the Columbia River from Vernita Bridge to the confluence with the Yakima River. MASS2 requires data on the river flow rate, downstream water surface elevation, groundwater influx and contaminants flux, background concentrations of contaminants, channel bathymetry, and the bed and suspended sediment properties. Stochastic variability for some input parameters such as partition coefficient (kd) values and background radionuclide concentrations is generated by the Environmental Stochastic Preprocessor. River flow is randomized on a yearly basis. At this time, the conceptual model does not incorporate extreme flooding (for example, 50 to 100 years) or dam removal scenarios.

  14. Modeling the influence of river rehabilitation scenarios on bed material sediment flux in a large river over decadal timescales

    E-Print Network [OSTI]

    Singer, Michael

    Modeling the influence of river rehabilitation scenarios on bed material sediment flux in a large and calibrated sediment transport formulae were used to assess the decadal impact of major river rehabilitation the implementation of three major river rehabilitation strategies being considered in the Sacramento River Valley

  15. The influence of sediment cover variability on longterm river incision rates: An example from the Peikang River,

    E-Print Network [OSTI]

    Mueller, Karl

    The influence of sediment cover variability on longterm river incision rates: An example from reach of the Peikang River. Sediment from these landslides produced widespread aggradation the spatial and temporal variability of sediment cover for the Peikang River. Because the river is undergoing

  16. EA-1981: Bonneville-Hood River Transmission Line Rebuild, Multnomah and Hood River Counties, Oregon

    Office of Energy Efficiency and Renewable Energy (EERE)

    Bonneville Power Administration (BPA) is preparing an EA to assess potential environmental impacts of a proposal to rebuild its 24-mile long, 115 kilovolt Bonneville-Hood River transmission line. The existing line runs between the Bonneville Powerhouse at Bonneville Dam in Multnomah County, Oregon, and BPA's existing Hood River Substation in Hood River County, Oregon. The project would include replacing structures and conductor wires, improving access roads, and constructing new access roads or trails where needed.

  17. River Data Package for the 2004 Composite Analysis

    SciTech Connect (OSTI)

    Rakowski, Cynthia L.; Guensch, Gregory R.; Patton, Gregory W.

    2004-08-01

    Beginning in fiscal year 2003, the DOE Richland Operations Office initiated activities, including the development of data packages, to support the 2004 Composite Analysis. The river data package provides calculations of flow and transport in the Columbia River system. This document presents the data assembled to run the river module components for the section of the Columbia River from Vernita Bridge to the confluence with the Yakima River.

  18. BITTERROOT RIVER SUBBASIN ASSESSMENT FOR FISH AND

    E-Print Network [OSTI]

    that respond to impacts from the development and operation of the Columbia River hydropower system. Nothing hydropower system. Nothing in this Plan or the participation in its development is intended to, and shall

  19. Think water : reconditioning the Malden River

    E-Print Network [OSTI]

    Oda, Kazuyo, 1969-

    2003-01-01

    The purpose of this thesis is to link water, history and culture through architectural and urban design by researching the potential for the rejuvenation of a neglected industrial site at the edge of a river. The Malden ...

  20. Lumbee River EMC- Residential Weatherization Loan Program

    Broader source: Energy.gov [DOE]

    Lumbee River Electric Membership Corporation (LREMC) offers low interest loans to help residential members increase the energy efficiency of homes. Loans up to $17,000 are available for the...

  1. BPA research aids Columbia River white sturgeon

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

    research aids Columbia River white sturgeon 8142015 12:00 AM Tweet Page Content BPA fish biologist Scott Bettin (left) and Brad Cady of the Washington Dept. of Fish and...

  2. Savannah River Site Environmental Report for 1997

    SciTech Connect (OSTI)

    Arnett, M.W.; Mamatey, A.R.

    1998-08-01

    The mission at the Savannah River Site has changed from the production of nuclear weapons materials for national defense to the management of waste, restoration of the environment, and the development of industry in and around the site.

  3. Savannah River Site Achieves Waste Transfer First

    Broader source: Energy.gov [DOE]

    AIKEN, S.C. – The EM program and its liquid waste contractor at the Savannah River Site (SRS) made history recently by safely transferring radioactive liquid waste from F Tank Farm to H Tank Farm using a central control room.

  4. EIS-0241: Hood River Fisheries Program

    Broader source: Energy.gov [DOE]

    This EIS evaluates a BPA proposal to protect and improve anadromous salmonid populations in the Hood River Basin. These actions are proposed in an attempt to mitigate the losses of fish and...

  5. Delaware River Basin Commission (Multiple States)

    Broader source: Energy.gov [DOE]

    The Delaware River Basin Commission (DRBC) is a federal-interstate compact government agency that was formed by concurrent legislation enacted in 1961 by the United States and the four basin states...

  6. River Basins Advisory Commissions (South Carolina)

    Broader source: Energy.gov [DOE]

    The Catawba/Wateree and Yadkin/Pee Dee River Basins Advisory Commissions are permanent public bodies jointly established by North and South Carolina. The commissions are responsible for assessing...

  7. Addressing Stakeholder Concerns: Pests and Pest Control in the Sacramento River Conservation Area

    E-Print Network [OSTI]

    Langridge, Suzanne

    2010-01-01

    scale restoration on the Sacramento River. Chapter 17 inriverside forests along the Sacramento River, the source ofand levee construction. The Sacramento River CONTACT Suzanne

  8. Observations on the Review of Archaeological Investigations in the Sacramento River Canyon

    E-Print Network [OSTI]

    Raven, Christopher

    1985-01-01

    decision to excavate the Sacramento River Canyon sites wasInvestigations in the Sacramento River Canyon, Vol. I:Investigations in the Sacramento River Canyon CHRISTOPHER

  9. Local diffusion networks act as pathways?to sustainable agriculture in the Sacramento River Valley

    E-Print Network [OSTI]

    Lubell, Mark; Fulton, Allan

    2007-01-01

    agriculture in the Sacramento River Valley by Mark Lubellquality management in the Sacramento River Valley. Data fromencourage growers in the Sacramento River Valley to

  10. Historic and Present Distribution of Chinook Salmon and Steelhead in the Calaveras River

    E-Print Network [OSTI]

    Marsh, Glenda

    2007-01-01

    2001). Presently, fall run Tuolumne River still occurs inof Calaveras River King Salmon run and proposed contingencyJune and Stanislaus Rivers Fall Run 8 June – December Late

  11. Salmon River Habitat Enhancement, 1990 Annual Report.

    SciTech Connect (OSTI)

    Rowe, Mike

    1991-12-01

    The annual report contains three individual subproject sections detailing tribal fisheries work completed during the summer and fall of 1990. Subproject I contains summaries of evaluation/monitoring efforts associated with the Bear Valley Creek, Idaho enhancement project. Subproject II contains an evaluation of the Yankee Fork of the Salmon River habitat enhancement project. Subproject III concerns the East Fork of the Salmon River, Idaho.

  12. RIVER PROTECTION PROJECT SYSTEM PLAN

    SciTech Connect (OSTI)

    CERTA PJ

    2008-07-10

    The U.S. Department of Energy (DOE), Office of River Protection (ORP) manages the River Protection Project (RPP). The RPP mission is to retrieve and treat Hanford's tank waste and close the tank farms to protect the Columbia River. As a result, the ORP is responsible for the retrieval, treatment, and disposal of the approximately 57 million gallons of radioactive waste contained in the Hanford Site waste tanks and closure of all the tanks and associated facilities. The previous revision of the System Plan was issued in September 2003. ORP has approved a number of changes to the tank waste treatment strategy and plans since the last revision of this document, and additional changes are under consideration. The ORP has established contracts to implement this strategy to establish a basic capability to complete the overall mission. The current strategy for completion of the mission uses a number of interrelated activities. The ORP will reduce risk to the environment posed by tank wastes by: (1) Retrieving the waste from the single-shell tanks (SST) to double-shell tanks (DST) for treatment and disposal; (2) Constructing and operating the WTP, which will safely treat all of the high-level waste (HLW) and about half of the low-activity waste (LAW) contained in the tank farms, and maximizing its capability and capacity; (3) Developing and deploying supplemental treatment capability or a second WTP LAW Facility that can safely treat about half of the LAW contained in the tank farms; (4) Developing and deploying treatment and packaging capability for transuranic (TRU) tank waste for shipment to and disposal at the Waste Isolation Pilot Plant (WIPP); (5) Deploying interim storage capacity for the immobilized HLW and shipping that waste to Yucca Mountain for disposal; (6) Operating the Integrated Disposal Facility for the disposal of immobilized LAW, along with the associated secondary waste, (7) Closing the SST and DST tank farms, ancillary facilities, and al1 waste management and treatment facilities, (8) Developing and implementing technical solutions to mitigate the impact from substantial1y increased estimates of Na added during the pretreatment of the tank waste solids, This involves a combination of: (1) refining or modifying the flowsheet to reduce the required amount of additional sodium, (2) increasing the overall LAW vitrification capacity, (3) increasing the incorporation of sodium into the LAW glass, or (4) accepting an increase in mission duration, ORP has made and continues to make modifications to the WTP contract as needed to improve projected plant performance and address known or emerging risks, Key elements of the implementation of this strategy are included within the scope of the Tank Operations Contract, currently in procurement Since 2003, the ORP has conducted over 30 design oversight assessments of the Waste Treatment and Immobilization Plant (WTP). The estimated cost at completion has increased and the schedule for construction and commissioning of the WTP has extended, The DOE, Office of Environmental Management (EM), sanctioned a comprehensive review of the WTP flowsheet, focusing on throughput. In 2005, the TFC completed interim stabilization of the SSTs and as of March 2007, has completed the retrieval of seven selected SSTs. Demonstration of supplemental treatment technologies continues. The ongoing tank waste retrieval experience, progress with supplemental treatment technologies, and changes in WTP schedule led to the FY 2007 TFC baseline submittal in November 2006. The TFC baseline submittal was developed before the WTP schedule was fully understood and approved by ORP, and therefore reflects an earlier start date for the WTP facilities. This System Plan is aligned with the current WTP schedule with hot commissioning beginning in 2018 and full operations beginning in 2019. Major decisions regarding the use of supplemental treatment and the associated technology, the ultimate needed capacity, and its relationship to the WTP have not yet been finalized. This System Plan assumes that the outcome of

  13. RIVER PROTECTION PROJECT SYSTEM PLAN

    SciTech Connect (OSTI)

    CERTA PJ; KIRKBRIDE RA; HOHL TM; EMPEY PA; WELLS MN

    2009-09-15

    The U.S. Department of Energy (DOE), Office of River Protection (ORP) manages the River Protection Project (RPP). The RPP mission is to retrieve and treat Hanford's tank waste and close the tank farms to protect the Columbia River. As a result, ORP is responsible for the retrieval, treatment, and disposal of approximately 57 million gallons 1 of radioactive waste contained in the Hanford Site waste tanks and closure2 of all the tanks and associated facilities. The previous revision of the System Plan was issued in May 2008. ORP has made a number of changes to the tank waste treatment strategy and plans since the last revision of this document, and additional changes are under consideration. ORP has contracts in place to implement the strategy for completion of the mission and establish the capability to complete the overall mission. The current strategl involves a number of interrelated activities. ORP will reduce risk to the environment posed by tank wastes by the following: (1) Retrieving the waste from the single-shell tanks (SST) to double-shell tanks (DST) and delivering the waste to the Waste Treatment and Immobilization Plant (WTP). (2) Constructing and operating the WTP, which will safely treat all of the high-level waste (HLW) fraction contained in the tank farms. About one-third of the low-activity waste (LAW) fraction separated from the HLW fraction in the WTP will be immobilized in the WTP LAW Vitrification Facility. (3) Developing and deploying supplemental treatment capability assumed to be a second LAW vitrification facility that can safely treat about two-thirds of the LAW contained in the tank farms. (4) Developing and deploying supplemental pretreatment capability currently assumed to be an Aluminum Removal Facility (ARF) using a lithium hydrotalcite process to mitigate sodium management issues. (5) Developing and deploying treatment and packaging capability for contact-handled transuranic (CH-TRU) tank waste for possible shipment to and disposal at the Waste Isolation Pilot Plant (WIPP) in New Mexico. (6) Deploying interim storage capacity for the immobilized high-level waste (IHLW) pending determination of the final disposal pathway. (7) Closing the SST and DST tank farms, ancillary facilities, and all associated waste management and treatment facilities. (8) Optimizing the overall mission by resolution of technical and programmatic uncertainties, configuring the tank farms to provide a steady, well-balanced feed to the WTP, and performing trade-offs of the required amount and type of supplemental treatment and of the amount of HLW glass versus LAW glass. ORP has made and continues to make modifications to the WTP contract as needed to improve projected plant performance and address known or emerging risks. Key elements needed to implement the strategy described above are included within the scope of the Tank Operations Contract (TOC). Interim stabilization of the SSTs was completed in March 2004. As of April 2009, retrieval of seven SSTs has been completed and retrieval of four additional SSTs has been completed to the limits of technology. Demonstration of supplemental LAW treatment technologies has stopped temporarily pending revision of mission need requirements. Award of a new contract for tank operations (TOC), the ongoing tank waste retrieval experience, HLW disposal issues, and uncertainties in waste feed delivery and waste treatment led to the revision of the Performance Measurement Baseline (PM B), which is currently under review prior to approval. 6 This System Plan is aligned with the current WTP schedule, with hot commissioning beginning in 2018, and full operations beginning in late 2019. Major decisions regarding the use of supplemental treatment and the associated technology, the ultimate needed capacity, and its relationship to the WTP have not yet been finalized. This System Plan assumes that the outcome of these decisions will be to provide a second LAW vitrification facility. No final implementation decisions regarding supplemental technology can be made until the Tank Closure and

  14. Experimental Investigation on the Effects of Coolant Concentration on Sub-Cooled Boiling and Crud Deposition on Reactor Cladding at Prototypical PWR Operating Conditions

    SciTech Connect (OSTI)

    Schultis, J., Kenneth; Fenton, Donald, L.

    2006-10-20

    Increasing demand for energy necessitates nuclear power units to increase power limits. This implies significant changes in the design of the core of the nuclear power units, therefore providing better performance and safety in operations. A major hindrance to the increase of nuclear reactor performance especially in Pressurized Deionized water Reactors (PWR) is Axial Offset Anomaly (AOA)--the unexpected change in the core axial power distribution during operation from the predicted distribution. This problem is thought to be occur because of precipitation and deposition of lithiated compounds like boric acid (H{sub 2}BO{sub 3}) and lithium metaborate (LiBO{sub 2}) on the fuel rod cladding. Deposited boron absorbs neutrons thereby affecting the total power distribution inside the reactor. AOA is thought to occur when there is sufficient build-up of crud deposits on the cladding during subcooled nucleate boiling. Predicting AOA is difficult as there is very little information regarding the heat and mass transfer during subcooled nucleate boiling. An experimental investigation was conducted to study the heat transfer characteristics during subcooled nucleate boiling at prototypical PWR conditions. Pool boiling tests were conducted with varying concentrations of lithium metaborate (LiBO{sub 2}) and boric acid (H{sub 2}BO{sub 3}) solutions in deionized water. The experimental data collected includes the effect of coolant concentration, subcooling, system pressure and heat flux on pool the boiling heat transfer coefficient. The analysis of particulate deposits formed on the fuel cladding surface during subcooled nucleate boiling was also performed. The results indicate that the pool boiling heat transfer coefficient degrades in the presence of boric acid and lithium metaborate compared to pure deionized water due to lesser nucleation. The pool boiling heat transfer coefficients decreased by about 24% for 5000 ppm concentrated boric acid solution and by 27% for 5000 ppm lithium metaborate solution respectively at the saturation temperature for 1000 psi (68.9 bar) coolant pressure. Boiling tests also revealed the formation of fine deposits of boron and lithium on the cladding surface which degraded the heat transfer rates. The boron and lithium metaborate precipitates after a 5 day test at 5000 ppm concentration and 1000 psi (68.9 bar) operating pressure reduced the heat transfer rate 21% and 30%, respectively for the two solutions.

  15. Application of MELCOR Code to a French PWR 900 MWe Severe Accident Sequence and Evaluation of Models Performance Focusing on In-Vessel Thermal Hydraulic Results

    SciTech Connect (OSTI)

    De Rosa, Felice [ENEA, Italian National Agency for New Technologies, Energy and the Environment (Italy)

    2006-07-01

    In the ambit of the Severe Accident Network of Excellence Project (SARNET), funded by the European Union, 6. FISA (Fission Safety) Programme, one of the main tasks is the development and validation of the European Accident Source Term Evaluation Code (ASTEC Code). One of the reference codes used to compare ASTEC results, coming from experimental and Reactor Plant applications, is MELCOR. ENEA is a SARNET member and also an ASTEC and MELCOR user. During the first 18 months of this project, we performed a series of MELCOR and ASTEC calculations referring to a French PWR 900 MWe and to the accident sequence of 'Loss of Steam Generator (SG) Feedwater' (known as H2 sequence in the French classification). H2 is an accident sequence substantially equivalent to a Station Blackout scenario, like a TMLB accident, with the only difference that in H2 sequence the scram is forced to occur with a delay of 28 seconds. The main events during the accident sequence are a loss of normal and auxiliary SG feedwater (0 s), followed by a scram when the water level in SG is equal or less than 0.7 m (after 28 seconds). There is also a main coolant pumps trip when {delta}Tsat < 10 deg. C, a total opening of the three relief valves when Tric (core maximal outlet temperature) is above 603 K (330 deg. C) and accumulators isolation when primary pressure goes below 1.5 MPa (15 bar). Among many other points, it is worth noting that this was the first time that a MELCOR 1.8.5 input deck was available for a French PWR 900. The main ENEA effort in this period was devoted to prepare the MELCOR input deck using the code version v.1.8.5 (build QZ Oct 2000 with the latest patch 185003 Oct 2001). The input deck, completely new, was prepared taking into account structure, data and same conditions as those found inside ASTEC input decks. The main goal of the work presented in this paper is to put in evidence where and when MELCOR provides good enough results and why, in some cases mainly referring to its specific models (candling, corium pool behaviour, etc.) they were less good. A future work will be the preparation of an input deck for the new MELCOR 1.8.6. and to perform a code-to-code comparison with ASTEC v1.2 rev. 1. (author)

  16. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Georgina and Eyre FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    and Eyre FLOOD WARNING SYSTEM for the GEORGINA RIVER & EYRE CREEK This brochure describes the flood warning. It includes reference information which will be useful for understanding Flood Warnings and River Height Bulletins issued by the Bureau's Flood Warning Centre during periods of high rainfall and flooding. Eyre

  17. E.2. Electronic Appendix -Food Web Elements of the Fraser River Upper River (above rkm 210)

    E-Print Network [OSTI]

    1 E.2. Electronic Appendix - Food Web Elements of the Fraser River Basin Upper River (above rkm 210) Food webs: Microbenthic algae (periphyton), detritus from riparian vegetation and littoral insects). Stressors: Water quality and habitat conditions have changed food webs in specific locations in the upper

  18. Developing a broader scientific foundation for river restoration: Columbia River food webs

    E-Print Network [OSTI]

    Developing a broader scientific foundation for river restoration: Columbia River food webs Robert J 31, 2012 (received for review August 6, 2012) Well-functioning food webs are fundamental emphasis on restoring habitat structure--without explicitly considering food webs--has been less successful

  19. Bureau Home > Australia> Queensland> Rainfall& River Conditions > River Brochures> Norman FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    Range) 200 kilometres southeast of Croydon and flows in a northwesterly direction. It is joined by its. #12;The record major flood of January 1974 and the floods of February 1991 and early February 2009 The Carpentaria Shire Council for the lower Norman River and the Croydon Shire Council for the upper Norman River

  20. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    in this document is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Bulletins · Flood Classifications · Other Links Flood Risk The Proserpine River has a total catchment area FLOOD WARNING SYSTEM for the PROSERPINE RIVER This brochure describes the flood warning system operated

  1. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Warrego FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    is information about : (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Forecasting · Local Classifications · Other Links Flood Risk The Warrego River catchment is located in south west Queensland and north FLOOD WARNING SYSTEM for the WARREGO RIVER This brochure describes the flood warning system operated

  2. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Burnett FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Forecasting · Local Classifications · Other Links Flood Risk The Burnett River is located on the southern Queensland coast FLOOD WARNING SYSTEM for the BURNETT RIVER This brochure describes the flood warning system operated

  3. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Tully and FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    at Kareeya Contained in this document is information about: (Last updated June 2015) · Flood Risk · Previous · Interpreting Flood Warnings and River Height Bulletins · Flood Classifications · Other Links Flood Risk and Murray FLOOD WARNING SYSTEM for the TULLY-MURRAY RIVERS This brochure describes the flood warning system

  4. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Pioneer FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    at Mirani Contained in this document is information about: (Last updated June 2015) · Flood Risk · Previous · Interpreting Flood Warnings and River Height Bulletins · Flood Classifications · Other Links Flood Risk FLOOD WARNING SYSTEM for the PIONEER RIVER This brochure describes the flood warning system operated

  5. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Don FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    in this document is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Warnings and River Height Bulletins · Flood Classifications · Other Links Flood Risk The Don River drains occurs in the Queens Beach and Bowen delta areas and dwellings are at risk. Previous Flooding Since

  6. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Nicholson FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    in this document is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Bulletins · Flood Classifications · Other Links Flood Risk The Nicholson River catchment is located in north FLOOD WARNING SYSTEM for the NICHOLSON RIVER This brochure describes the flood warning system operated

  7. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Herbert FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    Risk · Previous Flooding · Flood Forecasting · Local Information · Flood ALERT System · Flood Warnings Flood Risk The Ross, Bohle and Black River catchments covers an area of 750 square kilometres. Two main FLOOD WARNING SYSTEM for the ROSS, BOHLE & BLACK RIVERS This brochure describes the flood warning system

  8. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Logan and Albert FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    June 2015) · Flood Risk · Previous Flooding · Flood Forecasting · Local Information · Flood Warnings Flood Risk The Logan River has a catchment area of about 3850 square kilometres and lies in the south and Albert FLOOD WARNING SYSTEM for the LOGAN & ALBERT RIVERS This brochure describes the flood warning

  9. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Mooloolah FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    in this document is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Warnings and River Height Bulletins · Flood Classifications · Other Links Flood Risk The Mooloolah River. Continuing increases in population have accentuated this potential flood risk to life and property. Previous

  10. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Flinders FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    in this document is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Bulletins · Flood Classifications · Other Links Flood Risk The Flinders River catchment is located in north FLOOD WARNING SYSTEM for the FLINDERS RIVER This brochure describes the flood warning system operated

  11. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    ) · Flood Risk · Previous Flooding · Flood Forecasting · Local Information · Johnstone ALERT System · Flood · Other Links Flood Risk The North and South Johnstone Rivers rise in the tablelands of the north tropical FLOOD WARNING SYSTEM for the JOHNSTONE RIVER This brochure describes the flood warning system operated

  12. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Balonne and FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    Pty Ltd Contained in this document is information about: (Last updated June 2015) · The Flood Risk Flood Warnings and River Height Bulletins · Flood Classifications · Other Links The Flood Risk and Maranoa FLOOD WARNING SYSTEM for the BALONNE AND MARANOA RIVERS This brochure describes the flood warning

  13. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Mulgrave/Russell

    E-Print Network [OSTI]

    Greenslade, Diana

    ) · Flood Risk · Previous Flooding · Flood Warning · Local Information · Mulgrave/Russell ALERT System Classifications · Other Links Flood Risk The Mulgrave and Russell Rivers drain the mountain country dominated/Russell FLOOD WARNING SYSTEM for the MULGRAVE AND RUSSELL RIVERS This brochure describes the flood warning

  14. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    in this document is information about: (Last updated June 2015) · Flood Risk · Previous Flooding · Flood Bulletins · Flood Classifications · Other Links Flood Risk The vast Diamantina River catchment is located FLOOD WARNING SYSTEM for the DIAMANTINA RIVER This brochure describes the flood warning system operated

  15. Bureau Home > Australia> Queensland> Rainfall& River Conditions > River Brochures> Macintyre FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    ) · Flood Risk · Previous Flooding · Flood Warning · Local Information · Flood Warnings and Bulletins · Interpreting Flood Warnings and River Height Bulletins · Flood Classifications · Other Links Flood Risk and Weir FLOOD WARNING SYSTEM for the MACINTYRE AND WEIR RIVERS This brochure describes the flood warning

  16. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Condamine to Warwick

    E-Print Network [OSTI]

    Greenslade, Diana

    ) · Flood Risk · Previous Flooding · Flood Forecasting · Local Information · Warwick ALERT System · Flood · Other Links Flood Risk The Condamine River catchment to Warwick covers an area of approximately 1300 to Warwick FLOOD WARNING SYSTEM for the CONDAMINE RIVER TO WARWICK This brochure describes the flood warning

  17. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Condamine Warwick to Cotswold

    E-Print Network [OSTI]

    Greenslade, Diana

    Ltd Contained in this document is information about: (Last updated June 2015) · The Flood Risk Flood Warnings and River Height Bulletins · Flood Classifications · Other Links The Flood Risk Warwick to Cotswold FLOOD WARNING SYSTEM for the CONDAMINE RIVER WARWICK TO COTSWOLD This brochure

  18. THE MIDDLE SACRAMENTO RIVER: HUMAN IMPACTS ON PHYSICAL AND ECOLOGICAL PROCESSES ALONG A MEANDERING RIVER1

    E-Print Network [OSTI]

    THE MIDDLE SACRAMENTO RIVER: HUMAN IMPACTS ON PHYSICAL AND ECOLOGICAL PROCESSES ALONG A MEANDERING, California. Abstract: Native plant and wildlife communities along Northern California's middle Sacramento and eroding terraces. Human-induced changes to the Sacramento River, in- cluding bank protection, gravel

  19. Indian River Hydroelectric Project Grant

    SciTech Connect (OSTI)

    Rebecca Garrett

    2005-04-29

    This Final Technical Report provides a concise retrospective and summary of all facets of the Sheldon Jackson College electrical Infrastructure Renovation portion of the Indian River Hydroelectric Project Grant of the City and Borough of Sitka, Alaska. The Project Overview describes the origins of the project, the original conditions that provided the impetus for the grant funding, how the grant amendment was developed, the conceptual design development, and the actual parameters of the final project as it went out to bid. The Project Overview also describes the ''before and after'' conditions of the project. The Objectives division of this Final Technical Report describes the amendment-funded goals of the project. It also describes the milestones of project development and implementation, as well as, the rationale behind the milestone array. The Description of Activities Performed division of this report provides an in-depth chronological analysis of progressive project implementation. Photographs will provide further illustration of particular functional aspects of the renovation project within project parameters. The Conclusions and Recommendations division of this report provides a comprehensive retrospective analysis of the project.

  20. Spent fuel dry storage technology development: fuel temperature measurements under imposed dry storage conditions (I kW PWR spent fuel assembly)

    SciTech Connect (OSTI)

    Unterzuber, R.; Wright, J.B.

    1980-09-01

    A spent fuel assembly temperature test under imposed dry storage conditions was conducted at the Engine Maintenance Assembly and Disassembly (E-MAD) facility on the Nevada Test Site in support of spent fuel dry storage technology development. This document presents the test data and results obtained from an approximately 1.0 kW decay heat level PWR spent fuel assembly. A spent fuel test apparatus was designed to utilize a representative stainless steel spent fuel canister, a canister lid containing internal temperature instrumentation to measure fuel cladding temperatures, and a carbon steel liner that encloses the canister and lid. Electrical heaters along the liner length, on the lid, and below the canister are used to impose dry storage canister temperature profiles. Temperature instrumentation is provided on the liner and canister. The liner and canister are supported by a test stand in one of the large hot cells (West Process Cell) inside E-MAD. Fuel temperature measurements have been performed using imposed canister temperature profiles from the electrically heated and spent fuel drywell tests being conducted at E-MAD as well as for four constant canister temperature profiles, each with a vacuum, helium and air backfill. Computer models have been utilized in conjunction with the test to predict the thermal response of the fuel cladding. Computer predictions are presented, and they show good agreement with the test data.

  1. Spent fuel dry storage technology development: fuel temperature measurements under imposed dry storage conditions (1.4 kW PWR spent fuel assembly)

    SciTech Connect (OSTI)

    Unterzuber, R.

    1981-09-01

    A spent fuel assembly temperature test under imposed dry storage conditions was conducted at the Engine Maintenance Assembly and Disassembly (E-MAD) facility on the Nevada Test Site in support of spent fuel dry storage technology development. This document presents the test data and results obtained from an approximately 1.4 kW decay heat level PWR spent fuel assembly. A spent fuel test apparatus was designed to utilize a stainless steel canister representative of actual fuel canisters, a canister lid containing internal temperature instrumentation to measure fuel cladding temperatures, and a carbon steel liner that encloses the canister and lid. Electrical heaters along the liner length, on the lid, and below the canister are used to impose dry storage canister temperature profiles. Temperature instrumentation is provided on the liner and canister. The liner and canister are supported by a test stand in one of the large hot cells (West Process Cell) inside E-MAD. Fuel temperature measurements have been performed using imposed canister temperature profiles from the electrically heated and spent fuel near-surface drywell tests being conducted at E-MAD, the spent fuel deep geologic storage test being conducted in Climax granite on the Nevada Test Site, and for five constant canister temperature profiles, each with a vacuum, helium and air backfill. Computer models have been utilized in conjunction with the test to predict the thermal response of the fuel cladding. Computer predictions are presented, and they show good agreement with the test data.

  2. Coho Salmon Master Plan, Clearwater River Basin.

    SciTech Connect (OSTI)

    Nez Perce Tribe; FishPro

    2004-10-01

    The Nez Perce Tribe has a desire and a goal to reintroduce and restore coho salmon to the Clearwater River Subbasin at levels of abundance and productivity sufficient to support sustainable runs and annual harvest. Consistent with the Clearwater Subbasin Plan (EcoVista 2003), the Nez Perce Tribe envisions developing an annual escapement of 14,000 coho salmon to the Clearwater River Subbasin. In 1994, the Nez Perce Tribe began coho reintroduction by securing eggs through U.S. v. Oregon; by 1998 this agreement provided an annual transfer of 550,000 coho salmon smolts from lower Columbia River hatchery facilities for release in the Clearwater River Subbasin. In 1998, the Northwest Power and Conservation Council authorized the Bonneville Power Administration to fund the development of a Master Plan to guide this reintroduction effort. This Master Plan describes the results of experimental releases of coho salmon in the Clearwater River Subbasin, which have been ongoing since 1995. These data are combined with results of recent coho reintroduction efforts by the Yakama Nation, general coho life history information, and historical information regarding the distribution and life history of Snake River coho salmon. This information is used to assess a number of alternative strategies aimed at restoring coho salmon to historical habitats in the Clearwater River subbasin. These data suggest that there is a high probability that coho salmon can be restored to the Clearwater River subbasin. In addition, the data also suggest that the re-establishment of coho salmon could be substantially aided by: (1) the construction of low-tech acclimation facilities; (2) the establishment of a 'localized' stock of coho salmon; and (3) the construction of hatchery facilities to provide a source of juvenile coho salmon for future supplementation activities. The Nez Perce Tribe recognizes that there are factors which may limit the success of coho reintroduction. As a result of these uncertainties, the Nez Perce Tribe proposes to utilize a phased approach for coho reintroductions. This Master Plan seeks authorization and funding to move forward to Step 2 in the Northwest Power and Conservation Council 3-Step review process to further evaluate Phase I of the coho reintroduction program, which would focus on the establishment of a localized coho salmon stock capable of enduring the migration to the Clearwater River subbasin. To achieve this goal, the Nez Perce Tribe proposes to utilize space at existing Clearwater River subbasin hatchery facilities in concert with the construction of two low-tech acclimation facilities, to capitalize on the higher survival observed for acclimated versus direct stream released coho. In addition, Phase I would document the natural productivity of localized coho salmon released in two targeted tributaries within the Clearwater River subbasin. If Phase I is successful at establishing a localized coho salmon stock in an abundance capable of filling existing hatchery space, the rates of natural productivity are promising, and the interspecific interactions between coho and sympatric resident and anadromous salmonids are deemed acceptable, then Phase II would be triggered. Phase II of the coho reintroduction plan would focus on establishing natural production in a number of Clearwater River subbasin tributaries. To accomplish this goal, Phase II would utilize existing Clearwater River subbasin hatchery facilities, and expand facilities at the Nez Perce Tribal Hatchery Site 1705 facility to rear approximately 687,700 smolts annually for use in a rotating supplementation schedule. In short, this document identifies a proposed alternative (Phase I), complete with estimates of capital, operations and maintenance, monitoring and evaluation, and permitting that is anticipated to raise average smolt replacement rates from 0.73 (current) to 1.14 using primarily existing facilities, with a limited capital investment for low-tech acclimation facilities. This increase in survival is expected to provide the opportunity for the establishm

  3. New River Geothermal Exploration (Ram Power Inc.)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Miller, Clay

    2013-11-15

    The New River Geothermal Exploration (DOE Award No. EE0002843) is located approximately 25km south of the Salton Sea, near town of Brawley in Imperial County and approximately 150km east of San Diego, California. A total of 182 MT Logger sites were completed covering the two separate Mesquite and New River grids. The data was collected over a frequency range of 320Hz to 0.001Hz with variable site spacing. A number of different inversion algorithms in 1D, 2D and 3D were used to produce resistivity-depth profiles and maps of subsurface resistivity variations over the survey area. For 2D inversions, a total of eighteen lines were constructed in east-west and north-south orientations crossing the entire survey area. For MT 3D inversion, the New River property was divided in two sub-grids, Mesquite and New River areas. The report comprises of two parts. For the first part, inversions and geophysical interpretation results are presented with some recommendations of the potential targets for future follow up on the property. The second part of the report describes logistics of the survey, survey parameters, methodology and the survey results (data) in digital documents. The report reviews a Spartan MT survey carried out by Quantec Geoscience Limited over the New River Project in California, USA on behalf of Ram Power Inc. Data was acquired over a period of 29 days from 2010/06/26 to 2010/07/24.

  4. Savannah River Site (SRS) environmental overview

    SciTech Connect (OSTI)

    O'Rear, M.G. ); Steele, J.L.; Kitchen, B.G. )

    1990-01-01

    The environmental surveillance activities at and in the vicinity of the Savannah River Site (SRS) (formerly the Savannah River Plant (SRP)) comprise one of the most comprehensive and extensive environmental monitoring programs in the United States. This overview contains monitoring data from routine and nonroutine radiological and nonradiological environmental surveillance activities, summaries of environmental protection programs in progress, a summary of National Environmental Policy Act (NEPA) activities, and a listing of environmental permits (Appendix A) issued by regulatory agencies. This overview provides information about the impact of SRS operations on the public and the environment. The SRS occupies a large area of approximately 300 square miles along the Savannah River, principally in Aiken and Barnwell counties of South Carolina. SRS's primary function is the production of tritium, plutonium, and other special nuclear materials for national defense, for other governmental uses, and for some civilian purposes. From August 1950 to March 31, 1989, SRS was operated for the Department of Energy (DOE) by E. I. du Pont de Nemours Co. On April 1, 1989 the Westinghouse Savannah River Company assumed responsibility as the prime contractor for the Savannah River Site.

  5. New River Geothermal Exploration (Ram Power Inc.)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Miller, Clay

    The New River Geothermal Exploration (DOE Award No. EE0002843) is located approximately 25km south of the Salton Sea, near town of Brawley in Imperial County and approximately 150km east of San Diego, California. A total of 182 MT Logger sites were completed covering the two separate Mesquite and New River grids. The data was collected over a frequency range of 320Hz to 0.001Hz with variable site spacing. A number of different inversion algorithms in 1D, 2D and 3D were used to produce resistivity-depth profiles and maps of subsurface resistivity variations over the survey area. For 2D inversions, a total of eighteen lines were constructed in east-west and north-south orientations crossing the entire survey area. For MT 3D inversion, the New River property was divided in two sub-grids, Mesquite and New River areas. The report comprises of two parts. For the first part, inversions and geophysical interpretation results are presented with some recommendations of the potential targets for future follow up on the property. The second part of the report describes logistics of the survey, survey parameters, methodology and the survey results (data) in digital documents. The report reviews a Spartan MT survey carried out by Quantec Geoscience Limited over the New River Project in California, USA on behalf of Ram Power Inc. Data was acquired over a period of 29 days from 2010/06/26 to 2010/07/24.

  6. High Resolution River Hydraulic and Water Quality Characterization Using Rapidly Deployable Networked Infomechanical Systems (NIMS RD)

    E-Print Network [OSTI]

    Thomas C. Harmon; Richard F. Ambrose; Robert M. Gilbert; Jason C. Fisher; Michael Stealey; William J. Kaiser

    2006-01-01

    High Resolution River Hydraulic and Water Quality1594. High Resolution River Hydraulic and Water Qualityobserving spatiotemporal hydraulic and chemical properties

  7. Snake River Steelhead Straying Risk To Oregon Mid-C Steelhead Populations and

    E-Print Network [OSTI]

    ). · Snake River hatchery strays are considered a primary threat to Deschutes River and John Day River Migration In-River Transport Year # Adults Failed # Adults Failed 1999 51 25% 46 43% 2000 1098-River 22% Migration In-River Transport Year # Adults Failed # Adults Failed 1999 188 27% 187 38% 2000 426

  8. Evaluate Status of Pacific Lamprey in the Clearwater River and Salmon River Drainages, Idaho, 2009 Technical Report.

    SciTech Connect (OSTI)

    Cochnauer, Tim; Claire, Christopher [Idaho Department of Fish and Game

    2009-05-07

    Pacific lamprey Lampetra tridentata have received little attention in fishery science until recently, even though abundance has declined significantly along with other anadromous fish species in Idaho. Pacific lamprey in Idaho have to navigate over eight lower Snake River and Columbia River hydroelectric facilities for migration downstream as juveniles to the Pacific Ocean and again as adults migrating upstream to their freshwater spawning grounds in Idaho. The number of adult Pacific lamprey annually entering the Snake River basin at Ice Harbor Dam has declined from an average of over 18,000 during 1962-1969 to fewer than 600 during 1998-2006. Based on potential accessible streams and adult escapement over Lower Granite Dam on the lower Snake River, we estimate that no more than 200 Pacific lamprey adult spawners annually utilize the Clearwater River drainage in Idaho for spawning. We utilized electrofishing in 2000-2006 to capture, enumerate, and obtain biological information regarding rearing Pacific lamprey ammocoetes and macropthalmia to determine the distribution and status of the species in the Clearwater River drainage, Idaho. Present distribution in the Clearwater River drainage is limited to the lower sections of the Lochsa and Selway rivers, the Middle Fork Clearwater River, the mainstem Clearwater River, the South Fork Clearwater River, and the lower 7.5 km of the Red River. In 2006, younger age classes were absent from the Red River.

  9. Environmental Assessment of the Lower Cape Fear River System, 2010

    E-Print Network [OSTI]

    Mallin, Michael

    along Cape Fear Estuary Persistent blue-green Microcystis algal bloom in Cape Fear River, fall 2009 UNCW. These rivers are classified as blackwater systems because of their tea colored water. The Northeast Cape Fear

  10. Environmental Assessment of the Lower Cape Fear River System, 2011

    E-Print Network [OSTI]

    Mallin, Michael

    along Cape Fear Estuary Persistent blue-green Microcystis algal bloom in Cape Fear River, fall 2009 UNCW because of their tea colored water. The Northeast Cape Fear River often seems to be more oxygen stressed

  11. ISE 2012, Vienna USING RIVER RESTORATION OPERATIONS TO TEST

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    and hydroelectricity since the 19th century. A restoration program of the river started officially in 1998. It has, the Rhône River has been regulated for navigation, irrigation and hydroelectricity since the 19th century

  12. Savannah River Ecology Laboratory 2004 Annual Technical Progress Report

    SciTech Connect (OSTI)

    Paul M. Bertsch

    2004-07-29

    2004 annual report of research conducted by the Savannah River Ecology Laboratory, a research unit of The University of Georgia operating on the Savannah River Site in Aiken, South Carolina

  13. RETURN OF THE RIVER -2000 Chapter 5 Freshwater Habitats131

    E-Print Network [OSTI]

    rivers of the world and also one of the most developed with ten major hydroelectric dams on the main the major hydroelectric projects and the owner-operator of each project. #12;RETURN OF THE RIVER - 2000

  14. BITTERROOT RIVER SUBBASIN PLAN FOR FISH AND WILDLIFE

    E-Print Network [OSTI]

    from the development and operation of the Columbia River hydropower system. Nothing in this Plan and exclusively resulting from, or related to, the development and operation of the Columbia River hydropower

  15. Type B Accident Investigation Board Report of the Savannah River...

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

    Savannah River Site Hand Injury at the Salt Waste Processing Facility on October 6, 2009 Type B Accident Investigation Board Report of the Savannah River Site Hand Injury at the...

  16. SAVANNAH RIVER TECHNOLOGY CENTER MONTHLY REPORT AUGUST 1992

    SciTech Connect (OSTI)

    Ferrell, J.M.

    1999-06-21

    'This monthly report summarizes Programs and Accomplishments of the Savannah River Technology Center in support of activities at the Savannah River Site. The following categories are addressed: Reactor, Tritium, Separations, Environmental, Waste Management, General, and Items of Interest.'

  17. Re: Potomac River Generating Station Department of Energy, Case...

    Office of Environmental Management (EM)

    2005 ("DOE Potomac River Order") Pepco hereby files this revised notice of the planned outage of the 230 kV circuits serving the Potomac River Substation, and through that station,...

  18. Comparative Evaluation of Generalized River/Reservoir System Models 

    E-Print Network [OSTI]

    Wurbs, Ralph A.

    2005-01-01

    modeling systems that simulate the storage, flow, and diversion of water in a system of reservoirs and river reaches. Generalized means that a computer modeling system is designed for application to a range of concerns dealing with river basin systems...

  19. Voluntary Protection Program Onsite Review, Savannah River Remediation...

    Energy Savers [EERE]

    the evaluation of Savannah River Remediation, LLC (SRR), at the Savannah River Site in South Carolina during the period of November 4-13, 2014, and provides the Associate Under...

  20. Savannah River Remediation Intern Sees Nuclear Industry as Job Opportunity

    Broader source: Energy.gov [DOE]

    College intern Spencer Isom recently began her second summer with Savannah River Remediation (SRR), and her fourth year at Savannah River Site (SRS), where she continues a 31-year family legacy on site.

  1. Savannah River Ecology Laboratory FY2006 Annual Technical Progress Report

    SciTech Connect (OSTI)

    Paul M. Bertsch

    2006-10-23

    FY2006 annual report of research conducted by the Savannah River Ecology Laboratory, a research unit of the University of Georgia operating on the Savannah River Site in Aiken, County, SC.

  2. Savannah River Ecology Laboratory 2005 Annual Technical Progress Report

    SciTech Connect (OSTI)

    Paul M. Bertsch

    2005-07-19

    2005 annual report of research conducted by the Savannah River Ecology Laboratory, a research unit of The University of Georgia operating on the Savannah River Site, Aiken, South Carolina

  3. Preliminary Notice of Violation, Savannah River Nuclear Solutions...

    Energy Savers [EERE]

    to Savannah River Nuclear Solutions, LLC related to a Nitric Acid Spill Event and an Electrical Arc Flash Injury Event at the Savannah River Site On October 7, 2010, the U.S....

  4. Supplemental Recovery Plan Module for Snake River Salmon and Steelhead

    E-Print Network [OSTI]

    River Hydropower Projects June 2014 Prepared by the: National Marine Fisheries Service West Coast Region............................................................................................................................... 3 2. Hydropower System Overview Hydropower Projects (Hydro Module, dated September 24, 2008) for Snake River anadromous fish species listed

  5. Columbia River Salmon and Steelhead Returns 1999 -2008

    E-Print Network [OSTI]

    Columbia River Salmon and Steelhead Returns 1999 - 2008 Peter Hassemer Idaho Department of Fish Upper Columbia Summer Chinook Salmon Coho Salmon Shad Columbia River Salmon and Steelhead Returns 1999

  6. New Hydropower Turbines to Save Snake River Steelhead | Department...

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

    Hydropower Turbines to Save Snake River Steelhead May 24, 2010 - 1:23pm Addthis Voith Hydro installed machines at the Bonneville Dam on the Columbia River, located about 40 miles...

  7. Mirant Potomac River, LLC, Monthly Model Evaluation Study Report...

    Office of Environmental Management (EM)

    December 2006 Mirant Potomac River, LLC, Monthly Model Evaluation Study Report, December 2006 Docket No. EO-05-01. Order No. 202-07-02: As you are aware, Mirant Potomac River,...

  8. Interstate Commission on the Potomac River Basin (Multiple States)

    Broader source: Energy.gov [DOE]

    The Interstate Commission on the Potomac River Basin's (ICPRB) mission is to enhance, protect, and conserve the water and associated land resources of the Potomac River and its tributaries through...

  9. Snake and Columbia Rivers Sediment Sampling Project

    SciTech Connect (OSTI)

    Pinza, M.R.; Word, J.Q; Barrows, E.S.; Mayhew, H.L.; Clark, D.R. (Battelle/Marine Sciences Lab., Sequim, WA (United States))

    1992-12-01

    The disposal of dredged material in water is defined as a discharge under Section 404 of the Clean Water Act and must be evaluated in accordance with US Environmental Protection Agency regulation 40 CFR 230. Because contaminant loads in the dredged sediment or resuspended sediment may affect water quality or contaminant loading, the US Army Corps of Engineers (USACE), Walla Walla District, has requested Battelle/Marine Sciences Laboratory to collect and chemically analyze sediment samples from areas that may be dredged near the Port Authority piers on the Snake and Columbia rivers. Sediment samples were also collected at River Mile (RM) stations along the Snake River that may undergo resuspension of sediment as a result of the drawdown. Chemical analysis included grain size, total organic carbon, total volatile solids, ammonia, phosphorus, sulfides, oil and grease, total petroleum hydrocarbons, metals, polynuclear aromatic hydrocarbons, pesticides, polychlorinated biphenyls, and 21 congeners of polychlorinated dibenzodioxins and dibenzofurans.

  10. Columbia River Basin Research Plan Northwest Power and Conservation Council

    E-Print Network [OSTI]

    Columbia River Basin Research Plan By the Northwest Power and Conservation Council February 2006................................................................................................................. 20 (11) Human Development

  11. Deep Challenges for Foundation Performance at Savannah River Site

    Broader source: Energy.gov [DOE]

    Deep Challenges for Foundation Performance at Savannah River Site Frank H. Syms and Brent Gutierrez October 22, 2014

  12. Microearthquake surveys of Snake River plain and Northwest Basin...

    Open Energy Info (EERE)

    energy; Humboldt County Nevada; Idaho; microearthquakes; Nevada; North America; passive systems; Pershing County Nevada; Raft River; reservoir rocks; seismic methods;...

  13. Terrestrial Carbon Inventory at the Savannah River Site, 1951 – 2001.

    SciTech Connect (OSTI)

    US Forest Service - Annonymous,

    2012-02-01

    A Power Point slide presentation/report on the terestrial carbon inventory at the Savannah River Site.

  14. Exploring the Raft River geothermal area, Idaho, with the dc...

    Open Energy Info (EERE)

    the dc resistivity method (Abstract) Abstract GEOTHERMAL ENERGY; GEOTHERMAL FIELDS; ELECTRICAL SURVEYS; IDAHO; GEOTHERMAL EXPLORATION; RAFT RIVER VALLEY; ELECTRIC CONDUCTIVITY;...

  15. Independent Oversight Review, Savannah River Site- August 2011

    Broader source: Energy.gov [DOE]

    Review of Commercial Grade Dedication Plans for the Safety Instrumented System at the Savannah River Site Waste Solidification Building Project

  16. Radioiodine in the Savannah River Site environment

    SciTech Connect (OSTI)

    Kantelo, M.V.; Bauer, L.R.; Marter, W.L.; Murphy, C.E. Jr.; Zeigler, C.C.

    1993-01-15

    Radioiodine, which is the collective term for all radioactive isotopes of the element iodine, is formed at the Savannah River Site (SRS) principally as a by-product of nuclear reactor operations. Part of the radioiodine is released to the environment during reactor and reprocessing operations at the site. The purpose of this report is to provide an introduction to radioiodine production and disposition, its status in the environment, and the radiation dose and health risks as a consequence of its release to the environment around the Savannah River Plant. A rigorous dose reconstruction study is to be completed by thee Center for Disease Control during the 1990s.

  17. Ecological Responses to Hydrogeomorphic Fluctuations in a Sand Bed Prairie River: River Complexity, Habitat Availability, and Benthic Invertebrates

    E-Print Network [OSTI]

    O'Neill, Brian James

    2010-04-02

    Rivers with stochastic precipitation have fauna that overcome unique challenges. Organisms surmount these challenges by using refugia. Research was conducted on the sand bed Kansas River (Kaw). I (a) quantified how the hydrology affects the Kaw...

  18. 17. Integrating Engineered Log JamTechnology into River Rehabilitation

    E-Print Network [OSTI]

    Montgomery, David R.

    17. Integrating Engineered Log JamTechnology into River Rehabilitation Tim Abbe, George Pess, David R. Montgomery, and Kevin L. Fetherston ABSTRACT Reach-scale river rehabilitation projects using and engineering practices. The ELJ demonstration projects were developed as part of river rehabilitation efforts

  19. Diss. ETH No. 16895 River rehabilitation and fish

    E-Print Network [OSTI]

    Diss. ETH No. 16895 River rehabilitation and fish The challenge of initiating ecological recovery Christine Weber #12;Diss. ETH No. 16895 River rehabilitation and fish: The challenge of initiating Swiss river system prior to extensive rehabilitation 13 CHAPTER 3: Evaluation of the nature conservation

  20. EFFECTS OF BANK REVETMENT ON SACRAMENTO RIVER, CALIFORNIA1

    E-Print Network [OSTI]

    EFFECTS OF BANK REVETMENT ON SACRAMENTO RIVER, CALIFORNIA1 Michael D. Harvey and Chester C. Watson2 studied in the Butte Basin reach of Sacramento River, California, to determine whether bank revetment. Approximately 20 percent of the total bank length (both banks) in the Butte Basin reach of Sacramento River has

  1. MEANDERBELT DYNAMICS OF THE SACRAMENTO RIVER, CALIFORNIA1

    E-Print Network [OSTI]

    MEANDERBELT DYNAMICS OF THE SACRAMENTO RIVER, CALIFORNIA1 2 Michael D. Harvey 1 Presented: A 160km-long reach of Sacramento River was studied with the objective of predicting future changes for study reach of Sacramento River. In order to obtain an understanding of the meander dynamics

  2. Fraser River Hydro and Fisheries Research Project fonds

    E-Print Network [OSTI]

    Handy, Todd C.

    Fraser River Hydro and Fisheries Research Project fonds Revised by Erwin Wodarczak (1998 Fraser River Hydro and Fisheries Research Project fonds. ­ 19561961. 13 cm of textual records. Administrative History The Fraser River Hydro and Fisheries Research Project was established in 1956, financed

  3. CREEL CENSUS AND EXPENDITURE STUDY, NORTH FORK SUN RIVER,

    E-Print Network [OSTI]

    CREEL CENSUS AND EXPENDITURE STUDY, NORTH FORK SUN RIVER, MONTANA, 1951 Marine Biological STUDY, NORTH FORK SUN RIVER, MONTANA, 1951 Marine Biological Laboratory JUN16 1954 WOODS HOLE, MASS MAP CREEL CENSUS SUN RIVER MONTANA DRAWN i*^ ^ TRACED- _2£jLt:l SUBMITTED . 1 V N 01 1 VN ei

  4. STATUS OF COLUMBIA RIVER BLUEBACK SALMON RUNS, 1951

    E-Print Network [OSTI]

    STATUS OF COLUMBIA RIVER BLUEBACK SALMON RUNS, 1951 Marine Biological Laboratory J'JN13 1952 WOODS AND WILDLIFE SERVICE #12;#12;STATUS OF COLUMBIA RIVER BLUEBACK SALMON RUNS, 1951 Marine Biological Laboratory J blueback salmon counts over Bonneville and Rock Island Dams and total run data 1938-51 8 5. Columbia River

  5. SALMON RUNS -UPPER COLUMBIA RIVER, 1956-57

    E-Print Network [OSTI]

    364; SALMON RUNS - UPPER COLUMBIA RIVER, 1956-57 Marine Biological Laboratory WOODS HOLE, MAt L. McKernan, Director SALMON RUNS - UPPER COLUMBIA RIVER. 1956-57 by R. R. French and R. J. Wahle Dams. IV #12;SALMON RUNS - UPPER COLUMBIA RIVER, 1956-57 by R. R. French and R. J. Wahle ABSTRACT

  6. Drought Conditions Force Difficult Management Decisions For Sacramento River Temperatures

    E-Print Network [OSTI]

    temperatures in the river that could be catastrophic for endangered winter-run Chinook salmon. The Sacramento and everything. The winter-run Chinook salmon may not survive losses in the Sacramento River similar to last year of the river during the critical winter-run spawning and early rearing period. However, the equipment used

  7. Photo courtesy of the Penobscot River Restoration Trust

    E-Print Network [OSTI]

    sea-run fish species from this watershed. Improving access to habitat on this river is particularly in the U.S. Dams on the river and the decline of sea-run fish have contributed to a loss of recreational.S. Fish and Wildlife Service Maine Sea Grant Long-term Improve river flow and restore sea-run fish

  8. OXYGEN BLOCK IN THE MAIN -STEM WILLAMETTE RIVER

    E-Print Network [OSTI]

    ^hly publicized run of spring-chinook salmon. Pollution of the Willamette River is a problem that has receivedOXYGEN BLOCK IN THE MAIN -STEM WILLAMETTE RIVER i.iiit' I'.iological Labordtory B R A tl Y OCT 9-STEM WILIA^TETTE RIVER By Frederic F. Fish In Charge, Western Fish-Cultural Investigations and Richard A

  9. Columbia River Basin Accords -Narrative Proposal Project Number 200845800 1

    E-Print Network [OSTI]

    development of the Columbia River were largely responsible for the decline of the wild steelhead run (Mullan, lower river commercial fisheries, including tribal fisheries within Zone 6, took about 70% of the run River hydropower system, hatchery steelhead had replaced natural production in the run counts, masking

  10. The Geographic, Geological and Oceanographic Setting of the Indus River

    E-Print Network [OSTI]

    Clift, Peter

    -west monsoon of Asia that largely fill the Indus River although most of the run-off north of the Tarbela DamL1 16 The Geographic, Geological and Oceanographic Setting of the Indus River Asif Inam1 , Peter D Large Rivers: Geomorphology and Management, Edited by A. Gupta © 2007 John Wiley & Sons, Ltd 16

  11. WINTER-RUN CHINOOK SALMON IN THE SACRAMENTO RIVER, CALIFORNIA

    E-Print Network [OSTI]

    461 WINTER-RUN CHINOOK SALMON IN THE SACRAMENTO RIVER, CALIFORNIA WITH NOTES ON WATER TEMPERATURE REPORT-FISHERIES Na 461 #12;#12;WINTER-RUN CHINOOK SALMON IN THE SACRAMENTO RIVER, CALIFORNIA WITH NOTES HAMILTON CITY O Frontispiece.--Upper Sacramento River and Tributaries iv #12;WINTER-RUN CHINOOK SALMON

  12. OkanoganRiver Summer/FallChinookSalmon

    E-Print Network [OSTI]

    . Tribal Harvest Thresholds for Upper Columbia River 99 Summer/Fall Chinook (Early-Arriving Run) Table B.7. Tribal Harvest Thresholds for Upper Columbia River 99 Summer/Fall Chinook (Later-Arriving Run) Table B.8AppendixC OkanoganRiver Summer/FallChinookSalmon HatcheryGeneticManagementPlan #12;HATCHERY

  13. Columbia River Basin Accords -Narrative Proposal Project Number 200845800 1

    E-Print Network [OSTI]

    steelhead productivity in the upper Columbia River region, where the run size tripled (5,000 fish to 15Columbia River Basin Accords - Narrative Proposal Project Number 200845800 1 Narrative Table 1@easystreet.net Information transfer: A. Abstract Upper Columbia River (UCR) steelhead are listed as "Endangered" under

  14. Coal River Mountain Action Several people asked for more information about the 23 June civil disobedience near Coal River

    E-Print Network [OSTI]

    Hansen, James E.

    Coal River Mountain Action Several people asked for more information about the 23 June civil disobedience near Coal River Mountain. We need Dickens to describe the local situation, but you can glean the practice of mountaintop removal. Vernon Haltom vernoncrmw@gmail.com, head of Coal River Mountain Watch

  15. Bureau Home > Australia > Queensland > Rainfall & River Conditions > River Brochures > Burdekin FLOOD WARNING SYSTEM

    E-Print Network [OSTI]

    Greenslade, Diana

    the major rivers both upstream and downstream of the Burdekin Falls Dam. Downstream of the Dam, major from the north and the Belyando from the south, which join at the Burdekin Falls Dam. Downstream

  16. EIS-0268: Shutdown of River Water System at the Savannah River Site

    Broader source: Energy.gov [DOE]

    This EIS evaluates the potential environmental impacts of a proposal to shut down the Savannah R]ver Site River Water System in order to save money; that is, to prevent further expenditure of the...

  17. EIS-0351: Operation of Flaming Gorge Dam, Colorado River Storage Project, Colorado River, UT

    Broader source: Energy.gov [DOE]

    The Secretary of the United States Department of the Interior (Secretary), acting through the Bureau of Reclamation (Reclamation), is considering whether to implement a proposed action under which Flaming Gorge Dam would be operated to achieve the flow and temperature regimes recommended in the September 2000 report Flow and Temperature Recommendations for Endangered Fishes in the Green River Downstream of Flaming Gorge Dam (2000 Flow and Temperature Recommendations), published by the Upper Colorado River Endangered Fish Recovery Program (Recovery Program).

  18. Geoarchaeological Simulation of Meandering River Deposits

    E-Print Network [OSTI]

    is potentially fragmented and is three-dimensionally complex, especially when the system has been subjected Pleistocene and Holocene have been documented. Patterns of evolution include terrace formation in response (Vandenberghe, 1995; Tebbens et al., 1999; Macklin and Lewin, 2003). These modes of river and floodplain

  19. Geothermal features of Snake River plain, Idaho

    SciTech Connect (OSTI)

    Blackwell, D.D.

    1987-08-01

    The Snake River plain is the track of a hot spot beneath the continental lithosphere. The track has passed through southern Idaho as the continental plate has moved over the hot spot at a rate of about 3.5 cm/yr. The present site of the hot spot is Yellowstone Park. As a consequence of the passage, a systematic sequence of geologic and tectonic events illustrates the response of the continental lithosphere to this hotspot event. The three areas that represent various time slices in the evolution are the Yellowstone Plateau, the Eastern Snake River plain downwarp, and the Western Snake River plain basin/Owhyee Plateau. In addition to the age of silicic volcanic activity, the topographic profile of the Snake River plain shows a systematic variation from the high elevations in the east to lowest elevations on the west. The change in elevation follows the form of an oceanic lithosphere cooling curve, suggesting that temperature change is the dominant effect on the elevation.

  20. Savannah River Laboratory monthly report, February 1992

    SciTech Connect (OSTI)

    Ferrell, J.M.; Ice, L.W.

    1992-02-01

    This report is a progress report for the Savannah River Laboratory for the month of February 1992. The progress and activities in six categories were described in the report. The categories are reactor, tritium, separations, environmental, waste management, and general. Each category described numerous and varied activities. Some examples of these activities described are such things as radiation monitoring, maintenance, modifications, and remedial action.

  1. Savannah River Technology Center. Monthly report

    SciTech Connect (OSTI)

    Not Available

    1993-01-01

    This is a monthly progress report from the Savannah River Laboratory for the month of January 1993. It has sections with work in the areas of reactor safety, tritium processes and absorption, separations programs and wastes, environmental concerns and responses, waste management practices, and general concerns.

  2. Metal pollution of river Msimbazi, Tanzania

    SciTech Connect (OSTI)

    Ak'habuhaya, J.; Lodenius, M. )

    1988-01-01

    The Misimbazi River in Dar es Salaam is polluted with industrial, urban and agricultural waste waters. A preliminary investigation on the extent of metal pollution (Hg, Cr, Cu, Zn, Fe, Ni, Cd, Mn, Al) was made from samples of sediments and biological indicators. The metal concentrations were in general low, but some of our results indicated industrial pollution.

  3. Weisman Art Museum 333 East River Road

    E-Print Network [OSTI]

    Thomas, David D.

    Weisman Art Museum 333 East River Road Minneapolis, MN 55455 Contact: Erin Lauderman (612) 625 TREASURES: HIGHLIGHTS FROM THE MINNESOTA MUSEUM OF AMERICAN ART Exhibition dates: February 2 ­ May 12, 2013 MINNEAPOLIS ­ The Weisman Art Museum at the University of Minnesota, will feature the Minnesota Museum

  4. WAMweisman art museum 333 east river road

    E-Print Network [OSTI]

    Thomas, David D.

    WAMweisman art museum press release 333 east river road minneapolis, mn 55455 www through May 24, 2009 at the Weisman Art Museum. Changing Identity is the first-ever major U.S. exhibition the country opened itself to the West twenty years ago. Contempo- rary Vietnamese art has seen newfound

  5. WAMweisman art museum 333 east river road

    E-Print Network [OSTI]

    Thomas, David D.

    WAMweisman art museum press release 333 east river road minneapolis, MN 55455 www available upon request (continued) Changing Hands: Art Without Reservation Contemporary Native North American Art from the West, Northwest, and Pacific Exhibition dates: October 26, 2007­January 13, 2008

  6. weisman art museum 333 east river road

    E-Print Network [OSTI]

    Thomas, David D.

    weisman art museum press release 333 east river road minneapolis, mn 55455 www through January 10, 2010 Opening reception: October 23, 2009, 5­8 p.m. Minneapolis, MN--The Weisman Art from 5 to 8 p.m.. The exhibition showcases a gift to the Weisman of fifty works of art from New York

  7. WAMweisman art museum 333 east river road

    E-Print Network [OSTI]

    Thomas, David D.

    WAMweisman art museum press release 333 east river road minneapolis, mn 55455 www images available upon request (see last page of release) WEISMAN ART MUSEUM 2009­2010 EXHIBITION SEASON REFLECTS "ART AND THE EVERYDAY" Minneapolis, MN--Home videos posted on YouTube. Personal photos shared

  8. The Savannah River Site's Groundwater Monitoring Program

    SciTech Connect (OSTI)

    Not Available

    1992-08-03

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted during the first quarter of 1992. It includes the analytical data, field data, data review, quality control, and other documentation for this program; provides a record of the program's activities; and serves as an official document of the analytical results.

  9. River Lagan Lagan Bridge (M3)

    E-Print Network [OSTI]

    Gribakin, Gleb

    River Lagan Stew art Street Pakenham St. Ormeau Road PSNI Odyssey/W5 Lagan Bridge (M3) Royal Avenue Church Lane BridgeSt. HillStreet Skipper Street Ann Street Gordon Street Talbot Street DunbarStreet Gt. Glengall Street Divis Street Castle Street Durham Street BoyneBridge BarrackStreet BedfordStreet Linenhall

  10. The Savannah River Site's groundwater monitoring program

    SciTech Connect (OSTI)

    Not Available

    1991-10-18

    This report summarizes the Savannah River Site (SRS) groundwater monitoring program conducted by EPD/EMS in the first quarter of 1991. In includes the analytical data, field data, data review, quality control, and other documentation for this program, provides a record of the program's activities and rationale, and serves as an official document of the analytical results.

  11. Land Use Baseline Report Savannah River Site

    SciTech Connect (OSTI)

    Noah, J.C.

    1995-06-29

    This document is to serve as a resource for Savannah River Site managers, planners, and SRS stakeholders by providing a general description of the site and land-use factors important to future use decisions and plans. The intent of this document is to be comprehensive in its review of SRS and the surrounding area.

  12. weisman art museum 333 east river road

    E-Print Network [OSTI]

    Thomas, David D.

    and rules about what art should be. "Pop artists like Warhol were using ordinary subject matter to critiqueweisman art museum press release 333 east river road minneapolis, mn 55455 www images available (see thumbnails on final page of this document) EXHIBITION COMMON SENSE: ART

  13. El Nino signature in Alaskan river breakups

    E-Print Network [OSTI]

    Boffetta, G

    2011-01-01

    A signature of El Nino-Southern Oscillation is found in the historical dataset of the Alaskan Tanana river breakups where the average ice breaking day is found to anticipate of about 3.4 days when conditioned over El Nino years. This results represents a statistically significant example of ENSO teleconnection on regions remote from tropical Pacific.

  14. Salmon River Habitat Enhancement, 1989 Annual Report.

    SciTech Connect (OSTI)

    Rowe, Mike

    1989-04-01

    This project was funded by the Bonneville Power Administration (BPA). The annual report contains three individual subproject papers detailing tribal fisheries work completed during the summer and fall of 1989. Subproject 1 contains summaries of evaluation/monitoring efforts associated with the Bear Valley Creek, Idaho enhancement project. Subproject 2 contains an evaluation of the Yankee Fork of the Salmon River habitat enhancement project. This report has been sub-divided into two parts: Part 1; stream evaluation and Part 2; pond series evaluation. Subproject 3 concerns the East Fork of the Salmon River, Idaho. This report summarizes the evaluation of the project to date including the 1989 pre-construction evaluation conducted within the East Fork drainage. Dredge mining has degraded spawning and rearing habitat for chinook salmon and steelhead trout in the Yankee Fork drainage of the Salmon River and in Bear Valley Creek. Mining, agricultural, and grazing practices degraded habitat in the East Fork of the Salmon River. Biological monitoring of the success of habitat enhancement for Bear Valley Creek and Yankee Fork are presented in this report. Physical and biological inventories prior to habitat enhancement in East Fork were also conducted. Four series of off-channel ponds of the Yankee Fork are shown to provide effective rearing habitat for chinook salmon. 45 refs., 49 figs., 24 tabs.

  15. Savannah River Technology Center. Monthly report

    SciTech Connect (OSTI)

    Not Available

    1994-02-01

    This document contains information about the research programs being conducted at the Savannah River Plant. Topics of discussion include: thermal cycling absorption process, development of new alloys, ion exchange, oxalate precipitation, calcination, environmental research, remedial action, ecological risk assessments, chemical analysis of salt cakes, natural phenomena hazards assessment, and sampling of soils and groundwater.

  16. Wind River Watershed Restoration: 1999 Annual Report.

    SciTech Connect (OSTI)

    Connolly, Patrick J.

    2001-09-01

    This document represents work conducted as part of the Wind River Watershed Restoration Project during its first year of funding through the Bonneville Power Administration (BPA). The project is a comprehensive effort involving public and private entities seeking to restore water quality and fishery resources in the basin through cooperative actions. Project elements include coordination, watershed assessment, restoration, monitoring, and education. Entities involved with implementing project components are the Underwood Conservation District (UCD), USDA Forest Service (USFS), U.S. Geological Survey--Columbia River Research Lab (USGS-CRRL), and WA Department of Fish & Wildlife (WDFW). Following categories given in the FY1999 Statement of Work, the broad categories, the related objectives, and the entities associated with each objective (lead entity in boldface) were as follows: Coordination--Objective 1: Coordinate the Wind River watershed Action Committee (AC) and Technical Advisory Committee (TAC) to develop a prioritized list of watershed enhancement projects. Monitoring--Objective 2: Monitor natural production of juvenile, smolt, and adult steelhead in the Wind River subbasin. Objective 3: Evaluate physical habitat conditions in the Wind River subbasin. Assessment--Objective 4: Assess watershed health using an ecosystem-based diagnostic model that will provide the technical basis to prioritize out-year restoration projects. Restoration--Objective 5: Reduce road related sediment sources by reducing road densities to less than 2 miles per square mile. Objective 6: Rehabilitate riparian corridors, flood plains, and channel morphology to reduce maximum water temperatures to less than 61 F, to increase bank stability to greater than 90%, to reduce bankfull width to depth ratios to less than 30, and to provide natural levels of pools and cover for fish. Objective 7: Maintain and evaluate passage for adult and juvenile steelhead at artificial barriers. Education--Objective 8: Promote watershed stewardship among students, the community, private landowners, and local governments. Progress towards six of eight of these objectives is described within nine separate reports included in a four-volume document.

  17. Observing Short-Term Geomorphic Change in a Human-Modified River Using Terrestrial Repeat Photographs and Traditional Surveys: Uncompahgre River, Colorado, USA 

    E-Print Network [OSTI]

    Depke, Tyler J.

    2012-07-16

    The Uncompahgre River in Ouray, CO, was modified in 1996 from a braided river system to a meandering river channel. Large boulders of riprap were placed along designed meanders to prevent erosion and enable the development ...

  18. Strategies for Restoring Native Riparian Understory Plants Along the Sacramento River: Timing, Shade, Non-Native Control, and Planting Method

    E-Print Network [OSTI]

    Moore, Prairie L.; Holl, Karen D.; Wood, David M.

    2011-01-01

    riparian restoration on the Sacramento River. San Franciscoforest on the middle Sacramento River [Masters]. Chico (CA):Understory Plants Along the Sacramento River: Timing, Shade,

  19. Characterization of Savannah River Plant waste glass

    SciTech Connect (OSTI)

    Plodinec, M J

    1985-01-01

    The objective of the glass characterization programs at the Savannah River Laboratory (SRL) is to ensure that glass containing Savannah River Plant high-level waste can be permanently stored in a federal repository, in an environmentally acceptable manner. To accomplish this objective, SRL is carrying out several experimental programs, including: fundamental studies of the reactions between waste glass and water, particularly repository groundwater; experiments in which candidate repository environments are simulated as accurately as possible; burial tests of simulated waste glass in candidate repository geologies; large-scale tests of glass durability; and determination of the effects of process conditions on glass quality. In this paper, the strategy and current status of each of these programs is discussed. The results indicate that waste packages containing SRP waste glass will satisfy emerging regulatory criteria.

  20. The Savannah River Site's Groundwater Monitoring Program

    SciTech Connect (OSTI)

    Not Available

    1989-01-01

    The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site's Groundwater Monitoring Program. During fourth quarter 1989 (October--December), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. An explanation of flagging criteria for the fourth quarter is presented in the Flagging Criteria section of this document. All analytical results from fourth quarter 1989 are listed in this report, which is distributed to all waste-site custodians.