National Library of Energy BETA

Sample records for rural pub pwr

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

    OpenEI (Open Energy Information) [EERE & EIA]

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

  2. Northwest Rural Pub Pwr Dist | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Data Utility Id 13805 Utility Location Yes Ownership P NERC Location WECC NERC MRO Yes RTO SPP Yes Activity Distribution Yes This article is a stub. You can help OpenEI by...

  3. Seward County Rrl Pub Pwr Dist | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Data Utility Id 16954 Utility Location Yes Ownership P NERC Location SPP NERC SPP Yes RTO SPP Yes Activity Distribution Yes This article is a stub. You can help OpenEI by...

  4. Keosauqua Municipal Light & Pwr | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

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

  5. MICROBOONE-NOTE-1017-PUB

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

    7-PUB v1.0 A Method to Extract the Charge Distribution Arriving at the TPC Wire Planes in MicroBooNE The MicroBooNE Collaboration (Dated: June 29, 2016) In this technote, we describe the concept and general strategy of LArTPC drifted-charge extraction, which converts the raw digitized TPC waveform to the number of ionized electrons passing through the wire plane at a given time. The proper recovery of the number of ionized electrons from all wire planes is important to the success of the

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

    Office of Scientific and Technical Information (OSTI)

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

  7. PWR AXIAL BURNUP PROFILE ANALYSIS

    SciTech Connect

    J.M. Acaglione

    2003-09-17

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

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

    Office of Scientific and Technical Information (OSTI)

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

  9. Cal. Pub. Res. Code 30330 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Pub. Res. Code 30330Legal Abstract Cal. Pub. Res. Code 30330, current through August 5, 2014. Published NA Year Signed or Took Effect 1976 Legal Citation Cal. Pub. Res....

  10. Cal. Pub. Res. Code 30600 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Pub. Res. Code 30600Legal Abstract Cal. Pub. Res. Code 30600, current through August 5, 2014. Published NA Year Signed or Took Effect 1976 Legal Citation Cal. Pub. Res....

  11. Cal. Pub. Res. Code 30413 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Pub. Res. Code 30413Legal Abstract Cal. Pub. Res. Code 30413, current through August 5, 2014. Published NA Year Signed or Took Effect 1991 Legal Citation Cal. Pub. Res....

  12. Cal. Pub. Res. Code 30264 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Pub. Res. Code 30264Legal Abstract Cal. Pub. Res. Code 30264, current through August 5, 2014. Published NA Year Signed or Took Effect 1976 Legal Citation Cal. Pub. Res....

  13. Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales...

    OpenEI (Open Energy Information) [EERE & EIA]

    Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales - June 2008 Jump to: navigation, search EIA Monthly Electric Utility Sales and Revenue Data for Central Illinois Pub...

  14. MICROBOONE-NOTE-1016-PUB Noise Characterization

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

    6-PUB Noise Characterization and Filtering in the MicroBooNE TPC The MicroBooNE Collaboration (Dated: July 5, 2016) In large liquid argon time projection chambers (LArTPCs), TPC signal processing, which recovers the number of ionized electrons arriving at the anode plane from the raw digitized wire signals, is a crucial step towards automated event reconstruction. The first stage of signal processing is the identification and removal of any excess TPC noise with minimal impact on the true

  15. Cal. Pub. Res. Code 30103 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. Pub. Res. Code 30103Legal Abstract Cal. Pub. Res. Code 30103, current through...

  16. Cal. Pub. Util. Code 1001 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. Pub. Util. Code 1001Legal Abstract Cal. Pub. Util. Code 1001, current through...

  17. Cal. Pub. Res. Code 6370 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Cal. Pub. Res. Code 6370 Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. Pub. Res. Code 6370Legal Abstract Statutory...

  18. Cal. Pub. Util. Code 1001 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Util. Code 1001 (Redirected from Cal. Pub. Res. Code 1001) Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. Pub. Util....

  19. Cal. Pub. Res. Code 25309 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. Pub. Res. Code 25309Legal Abstract Cal. Pub. Res. Code 25309, current through...

  20. Cal. Pub. Res. Code 6826 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. Pub. Res. Code 6826Legal Abstract Cal. Pub. Res. Code 6826, current through...

  1. Cal. Pub. Res. Code 25541 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. Pub. Res. Code 25541Legal Abstract Cal. Pub. Res. Code 25541, current through...

  2. Cal. Pub. Res. Code 25120 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. Pub. Res. Code 25120Legal Abstract Cal. Pub. Res. Code 25120, current through...

  3. Cal. Pub. Res. 25500 et seq | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. Pub. Res. 25500 et seqLegal Abstract Cal. Pub. Res. Code 25531, current through...

  4. Central Nebraska Pub P&I Dist | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Pub P&I Dist Jump to: navigation, search Name: Central Nebraska Pub P&I Dist Place: Nebraska Phone Number: 308.995.8601 Website: www.nppd.com Twitter: @nppdnews Facebook: https:...

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

    OpenEI (Open Energy Information) [EERE & EIA]

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

  6. Northeast Missouri El Pwr Coop | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

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

  7. Sam Rayburn Municipal Pwr Agny | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

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

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

    OpenEI (Open Energy Information) [EERE & EIA]

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

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

    OpenEI (Open Energy Information) [EERE & EIA]

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

  10. Cal. Pub. Res. Code 21067 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. Pub. Res. Code 21067Legal Abstract Definitions section for California's...

  11. Cal. Pub. Res. Code 21001 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Cal. Pub. Res. Code 21001Legal Abstract Sets forth California's policy on maintenance of environmental quality. Published NA Year Signed or Took Effect 1970 Legal...

  12. Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales...

    OpenEI (Open Energy Information) [EERE & EIA]

    March 2008 Jump to: navigation, search EIA Monthly Electric Utility Sales and Revenue Data for Central Illinois Pub Serv Co for March 2008. Monthly Electric Utility Sales and...

  13. Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales...

    OpenEI (Open Energy Information) [EERE & EIA]

    Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales - November 2008 Jump to: navigation, search EIA Monthly Electric Utility Sales and Revenue Data for Central Illinois...

  14. Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales...

    OpenEI (Open Energy Information) [EERE & EIA]

    Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales - September 2008 Jump to: navigation, search EIA Monthly Electric Utility Sales and Revenue Data for Central Illinois...

  15. Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales...

    OpenEI (Open Energy Information) [EERE & EIA]

    April 2008 Jump to: navigation, search EIA Monthly Electric Utility Sales and Revenue Data for Central Illinois Pub Serv Co for April 2008. Monthly Electric Utility Sales and...

  16. Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales...

    OpenEI (Open Energy Information) [EERE & EIA]

    Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales - January 2009 Jump to: navigation, search EIA Monthly Electric Utility Sales and Revenue Data for Central Illinois...

  17. Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales...

    OpenEI (Open Energy Information) [EERE & EIA]

    January 2008 Jump to: navigation, search EIA Monthly Electric Utility Sales and Revenue Data for Central Illinois Pub Serv Co for January 2008. Monthly Electric Utility Sales and...

  18. Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales...

    OpenEI (Open Energy Information) [EERE & EIA]

    October 2008 Jump to: navigation, search EIA Monthly Electric Utility Sales and Revenue Data for Central Illinois Pub Serv Co for October 2008. Monthly Electric Utility Sales and...

  19. Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales...

    OpenEI (Open Energy Information) [EERE & EIA]

    Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales - December 2008 Jump to: navigation, search EIA Monthly Electric Utility Sales and Revenue Data for Central Illinois...

  20. Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales...

    OpenEI (Open Energy Information) [EERE & EIA]

    9 Jump to: navigation, search EIA Monthly Electric Utility Sales and Revenue Data for Central Illinois Pub Serv Co for February 2009. Monthly Electric Utility Sales and Revenue...

  1. Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales...

    OpenEI (Open Energy Information) [EERE & EIA]

    8 Jump to: navigation, search EIA Monthly Electric Utility Sales and Revenue Data for Central Illinois Pub Serv Co for February 2008. Monthly Electric Utility Sales and Revenue...

  2. Cal. Pub. Res. Code 21080 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    library Legal Document- StatuteStatute: Cal. Pub. Res. Code 21080Legal Abstract Sets forth general statutory provisions for California's environmental quality programs....

  3. Cal. Pub. Res. Code 6301 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. Pub. Res. Code 6301Legal Abstract This section grants the California State Lands...

  4. Cal. Pub. Res. Code 6502 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. Pub. Res. Code 6502Legal Abstract Statutory chapter providing for leasing of public...

  5. Cal. Pub. Res. Code 5020 et seq.: Historical Resources | Open...

    OpenEI (Open Energy Information) [EERE & EIA]

    search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. Pub. Res. Code 5020 et seq.: Historical ResourcesLegal Abstract This section...

  6. Cal. Pub. Res. Code 30603 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    navigation, search OpenEI Reference LibraryAdd to library Legal Document- OtherOther: Cal. Pub. Res. Code 30603Legal Abstract Delegation of local authority for Coastal Zone...

  7. Central Illinois Pub Serv Co (Illinois) EIA Revenue and Sales...

    OpenEI (Open Energy Information) [EERE & EIA]

    May 2008 Jump to: navigation, search EIA Monthly Electric Utility Sales and Revenue Data for Central Illinois Pub Serv Co for May 2008. Monthly Electric Utility Sales and Revenue...

  8. PUB-3000 | BERKELEY LAB HEALTH AND SAFETY MANUAL

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

    ES&H MANUAL (PUB-3000) Berkeley Lab Table of Contents Guide to Using the ES&H Manual Responsible Authors Log of ES&H Manual Changes Requesting a Change to the ES&H Manual Search...

  9. Spring Valley Pub Utils Comm | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Name: Spring Valley Pub Utils Comm Place: Minnesota Website: www.smmpa.orgmembersspring-v Outage Hotline: 507.346.7622 References: EIA Form EIA-861 Final Data File for 2010 -...

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

    SciTech Connect

    Ocken, H.; Knott, S.

    1981-03-01

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

  11. South Mississippi El Pwr Assn | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

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

  12. East Mississippi Elec Pwr Assn | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

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

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

    Office of Energy Efficiency and Renewable Energy (EERE)

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

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

    OpenEI (Open Energy Information) [EERE & EIA]

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

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

    Office of Scientific and Technical Information (OSTI)

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

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

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

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

  17. PWR representative behavior during a LOCA

    SciTech Connect

    Allison, C.M.

    1981-01-01

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

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

    SciTech Connect

    Gastelum, Jason A.

    2011-03-28

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

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

    Office of Scientific and Technical Information (OSTI)

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

  20. Swing-Down of 21-PWR Waste Package

    SciTech Connect

    A.K. Scheider

    2001-05-04

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

  1. MICROBOONE-NOTE-1008-PUB Michel Electron Reconstruction Using

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

    8-PUB Michel Electron Reconstruction Using the MicroBooNE LArTPC Cosmic Data The MicroBooNE Collaboration August 25, 2016 Abstract MicroBooNE is a Liquid Argon Time Projection Chamber (LArTPC) neutrino detector located in the Booster Neutrino Beamline at Fermilab which began collecting neutrino data in October 2015. MicroBooNE aims to explore the low-energy excess in the ν e spectrum reported by MiniBooNE as well as perform ν-Ar cross-section measurements. In this note, we present the current

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

    SciTech Connect

    Faidy, C.

    1997-04-01

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

  3. Analysis of PWR RCS Injection Strategy During Severe Accident

    SciTech Connect

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

    2004-05-15

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

  4. Robotic inspection of PWR coolant pump casing welds

    SciTech Connect

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

    1997-12-01

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

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

    SciTech Connect

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

    1983-01-01

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

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

    SciTech Connect

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

    2012-06-06

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

  7. Cal. Pub. Util. Code 201-248 - Public Utilities Act | Open...

    OpenEI (Open Energy Information) [EERE & EIA]

    from "http:en.openei.orgwindex.php?titleCal.Pub.Util.Code201-248-PublicUtilitiesAct&oldid801671" Feedback Contact needs updating Image needs updating...

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

    SciTech Connect

    2013-11-01

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

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

    Energy Science and Technology Software Center

    2013-11-01

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

  10. 21-PWR WASTE PACKAGE WITH ABSORBER PLATES LOADING CURVE EVALUATION

    SciTech Connect

    J.M. Scaglione

    2004-12-17

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

  11. Comparison of PWR-IMF and FR fuel cycles

    SciTech Connect

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

    2007-07-01

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

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

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

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

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

    SciTech Connect

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

    1982-12-01

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

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

    SciTech Connect

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

    1988-01-01

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

  15. 21-PWR Waste Package Side and End Impacts

    SciTech Connect

    V. Delabrosse

    2003-02-27

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

  16. 21-PWR Waste Package Side and End Impacts

    SciTech Connect

    T. Schmitt

    2005-08-29

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

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

    SciTech Connect

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

    2004-07-01

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

  18. VERA Core Simulator Methodology for PWR Cycle Depletion

    SciTech Connect

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

    2015-01-01

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

  19. Microsoft Word - aac2012_Li_1_WG4-SLAC-PUB-15212.doc

    Office of Scientific and Technical Information (OSTI)

    et al., "Results from Plasma Wakefield Experiments at FACET", IPAC'11, San Sebastian, Spain, 2011, SLAC-PUB-14560. 5. E. Adli et al., to be published. 6. S.Z. Li and M.J. Hogan,...

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

    SciTech Connect

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

    1997-04-01

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

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

    SciTech Connect

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

    1983-01-01

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

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

    Office of Scientific and Technical Information (OSTI)

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

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

    Office of Scientific and Technical Information (OSTI)

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

  4. PWR and BWR spent fuel assembly gamma spectra measurements

    DOE PAGES [OSTI]

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

    2016-07-17

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

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

    SciTech Connect

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

    2002-07-01

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

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

    SciTech Connect

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

    1992-03-01

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

  7. Integrated rural energy planning

    SciTech Connect

    El Mahgary, Y.; Biswas, A.K.

    1985-01-01

    This book presents papers on integrated community energy systems in developing countries. Topics considered include an integrated rural energy system in Sri Lanka, rural energy systems in Indonesia, integrated rural food-energy systems and technology diffusion in India, bringing energy to the rural sector in the Philippines, the development of a new energy village in China, the Niaga Wolof experimental rural energy center, designing a model rural energy system for Nigeria, the Basaisa village integrated field project, a rural energy project in Tanzania, rural energy development in Columbia, and guidelines for the planning, development and operation of integrated rural energy projects.

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

    SciTech Connect

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

    2015-09-01

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

  9. WINDExchange: Rural Communities

    WindExchange

    Rural Communities Printable Version Bookmark and Share Wind for Homeowners, Farmers, & Businesses Resources & Tools Rural Communities Agricultural lands in the United States are...

  10. Analysis of Potential Hydrogen Risk in the PWR Containment

    SciTech Connect

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

    2006-07-01

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

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

    SciTech Connect

    Cox, B.

    1985-10-01

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

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

    SciTech Connect

    Van Der Sluys, W.A.

    1982-12-01

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

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

    SciTech Connect

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

    2014-01-01

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

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

    SciTech Connect

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

    2010-06-22

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

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

    SciTech Connect

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

    1993-06-01

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

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

    SciTech Connect

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

    1985-01-01

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

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

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

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

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

    SciTech Connect

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

    1984-03-01

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

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

    SciTech Connect

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

    1984-03-01

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

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

    SciTech Connect

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

    2013-07-01

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

  1. MicroBooNE Detector Stability MICROBOONE-NOTE-1013-PUB The MicroBooNE

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

    MicroBooNE Detector Stability MICROBOONE-NOTE-1013-PUB The MicroBooNE Collaboration June 30, 2016 Abstract The Micro Booster Neutrino Experiment (MicroBooNE) is designed to explore the low- energy excess in the ν e event spectrum reported by the MiniBooNE experiment [1] and to measure ν-Ar cross sections in the 1 GeV energy range. The detector is a liquid argon time projection chamber with wire readout, supplemented with a light detection system based on photo-multiplier tubes (PMTs). The

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

    SciTech Connect

    1986-03-01

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

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

    SciTech Connect

    T.L. Lotz

    1997-01-29

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

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

    SciTech Connect

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

    2014-09-30

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

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

    SciTech Connect

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

    2015-09-30

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

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

    SciTech Connect

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

    1993-07-01

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

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

    SciTech Connect

    Cardoni, Jeffrey

    2010-11-01

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

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

    SciTech Connect

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

    1984-05-01

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

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

    SciTech Connect

    Kwi Lim Lee; Soon Heung Chang

    2004-07-01

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

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

    SciTech Connect

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

    1982-09-01

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

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

    SciTech Connect

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

    2000-10-03

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

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

    SciTech Connect

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

    1993-12-31

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

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

    SciTech Connect

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

    2010-03-01

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

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

    SciTech Connect

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

    1995-12-01

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

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

    SciTech Connect

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

    1983-04-01

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

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

    SciTech Connect

    Schneidmiller, D.; Stiteler, D.

    1983-04-01

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

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

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

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

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

    SciTech Connect

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

    1997-04-01

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

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

    SciTech Connect

    Shaver, Mark W.; Lanning, Donald D.

    2010-02-01

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

  20. USDA Rural Development Energy Program

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

    Development Energy Programs Tedd Buelow Native American Coordinator DOE Tribal Energy Program Review November 16, 2009 USDA Rural Development 4 Types of Program Delivery - Guaranteed Loans - Direct Loans - Grants - Payments 3 Program Areas - Rural Business and Cooperative - Rural Housing and Community Facilities - Rural Utilities DOE Tribal Energy Program Review November 16, 2009 USDA Rural Development Organizational Structure National Office State Directors Area Directors Program Directors

  1. Alaska Rural Energy Conference

    Energy.gov [DOE]

    The Rural Energy Conference is a three-day event offering a large variety of technical sessions covering new and ongoing energy projects in Alaska, as well as new technologies and needs for Alaska's remote communities.

  2. Rural Energy Savings Program

    Office of Energy Efficiency and Renewable Energy (EERE)

    This program helps rural families and small businesses achieve cost savings by providing loans to qualified consumers to implement durable, cost-effective energy efficiency measures, including on- or off-grid renewable energy.

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

    SciTech Connect

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

    2009-05-01

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

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

    SciTech Connect

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

    1996-08-01

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

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

    SciTech Connect

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

    2013-07-01

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

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

    SciTech Connect

    Wagner, J.C.

    2002-10-23

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

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

    Energy Science and Technology Software Center

    1999-06-02

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

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

    SciTech Connect

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

    1995-12-31

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

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

    SciTech Connect

    V. DeLa Brosse

    2003-03-27

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

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

    SciTech Connect

    T. Schmitt

    2005-08-17

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

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

    SciTech Connect

    Garud, Y.S.

    1985-01-01

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

  12. Alaska Rural Small Business Conference

    Energy.gov [DOE]

    Hosted by the Alaska Village Initiatives, the Alaska Rural Small Business Conference is a three-day conference to bring together rural businesses and leaders and provide them with networking opportunities, training, and technical information.

  13. Rural Development: Rural Energy for America Program

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

    Development Rural Energy for America (REAP) Program 1 Deadlines and ESTIMATED Funding and for Colorado in FY 2015 April 30 Deadline: * $152,000 is "set aside" for grant requests of $20,000 or less; * $503,000 is deemed "unrestricted funds" June 30 Deadline: * $503,000 is deemed "unrestricted funds" Guarantee Loan applications are accepted year round unless combined with a grant request. Then they are due at the time of the grant application. 2 Important Definitions:

  14. Rural energy and development

    SciTech Connect

    Stern, R.

    1997-12-01

    The author discusses the worldwide problem and need for rural electrification to support development. He points out that rural areas will pay high rates to receive such services, but cannot afford the capital cost for conventional services. The author looks at this problem from the point of energy choices, subsides, initial costs, financing, investors, local involvement, and governmental actions. In particular he is concerned with ways to make better use of biofuels, to promote sustainable harvesting, and to encourage development of more modern fuels.

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

    DOE PAGES [OSTI]

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

    2016-06-10

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

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

    SciTech Connect

    J.S. Tang

    2001-12-20

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

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

    SciTech Connect

    Herer, C.

    1995-09-01

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

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

    SciTech Connect

    Rodriguez, S.E.

    1985-01-01

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

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

    SciTech Connect

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

    1986-05-01

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

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

    SciTech Connect

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

    1981-01-01

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

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

    SciTech Connect

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

    1983-03-01

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

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

    SciTech Connect

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

    1987-05-21

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

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

    SciTech Connect

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

    1985-02-01

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

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

    SciTech Connect

    Gilles Youinou; Andrea Alfonsi

    2012-03-01

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

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

    SciTech Connect

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

    1995-11-01

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

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

    SciTech Connect

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

    1986-11-01

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

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

    SciTech Connect

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

    2007-07-01

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

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

    SciTech Connect

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

    1985-04-01

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

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

    SciTech Connect

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

    1983-01-01

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

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

    SciTech Connect

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

    1983-01-01

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

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

    SciTech Connect

    J.W. Davis

    1996-08-29

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

  12. Rural Development's Rural Utilities Service (RUS) Electric Programs

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

    Development's Rural Utilities Service (RUS) Electric Programs Jonathan P. Claffey | Senior Policy Advisor Office of the Assistant Administrator Electric Program | Rural Utilities Service USDA Rural Development Washington, DC 20250 Cell: (202)251-3771 | Office: (202) 720-9545 | Fax: (202) 690-0717 jon.claffey@wdc.usda.gov United States Department of Agriculture (USDA) Seven Mission Areas Secretary Tom Vilsack Farm & Foreign Agriculture Services Food Safety Natural Resources and Environment

  13. Rural Energy Conference Project

    SciTech Connect

    Dennis Witmer; Shannon Watson

    2008-12-31

    Alaska remains, even at the beginning of the 21st century, a place with many widely scattered, small, remote communities, well beyond the end of both the road system and the power grid. These communities have the highest energy costs of any place in the United States, despite the best efforts of the utilities that service them. This is due to the widespread dependence on diesel electric generators, which require small capital investments, but recent increases in crude oil prices have resulted in dramatic increases in the cost of power. In the enabling legislation for the Arctic Energy Office in 2001, specific inclusion was made for the study of ways of reducing the cost of electrical power in these remote communities. As part of this mandate, the University of Alaska has, in conjunction with the US Department of Energy, the Denali Commission and the Alaska Energy Authority, organized a series of rural energy conferences, held approximately every 18 months. The goal of these meeting was to bring together rural utility operators, rural community leaders, government agency representatives, equipment suppliers, and researchers from universities and national laboratories to discuss the current state of the art in rural power generation, to discuss current projects, including successes as well as near successes. Many of the conference presenters were from industry and not accustomed to writing technical papers, so the typical method of organizing a conference by requesting abstracts and publishing proceedings was not considered viable. Instead, the organizing committee solicited presentations from appropriate individuals, and requested that (if they were comfortable with computers) prepare Power point presentations that were collected and posted on the web. This has become a repository of many presentations, and may be the best single source of information about current projects in the state of Alaska.

  14. Rural health clinics infrastructure

    SciTech Connect

    Olson, K.

    1997-12-01

    The author discusses programs which were directed at the installation of photovoltaic power systems in rural health clinics. The objectives included: vaccine refrigeration; ice pack freezing; lighting; communications; medical appliances; sterilization; water purification; and income generation. The paper discusses two case histories, one in the Dominican Republic and one in Colombia. The author summarizes the results of the programs, both successes and failures, and offers an array of conclusions with regard to the implementation of future programs of this general nature.

  15. Development and Application of Laser Peening System for PWR Power Plants

    SciTech Connect

    Masaki Yoda; Itaru Chida; Satoshi Okada; Makoto Ochiai; Yuji Sano; Naruhiko Mukai; Gaku Komotori; Ryoichi Saeki; Toshimitsu Takagi; Masanori Sugihara; Hirokata Yoriki

    2006-07-01

    Laser peening is a process to improve residual stress from tensile to compressive in surface layer of materials by irradiating high-power laser pulses on the material in water. Toshiba has developed a laser peening system composed of Q-switched Nd:YAG laser oscillators, laser delivery equipment and underwater remote handling equipment. We have applied the system for Japanese operating BWR power plants as a preventive maintenance measure for stress corrosion cracking (SCC) on reactor internals like core shrouds or control rod drive (CRD) penetrations since 1999. As for PWRs, alloy 600 or 182 can be susceptible to primary water stress corrosion cracking (PWSCC), and some cracks or leakages caused by the PWSCC have been discovered on penetrations of reactor vessel heads (RVHs), reactor bottom-mounted instrumentation (BMI) nozzles, and others. Taking measures to meet the unconformity of the RVH penetrations, RVHs themselves have been replaced in many PWRs. On the other hand, it's too time-consuming and expensive to replace BMI nozzles, therefore, any other convenient and less expensive measures are required instead of the replacement. In Toshiba, we carried out various tests for laser-peened nickel base alloys and confirmed the effectiveness of laser peening as a preventive maintenance measure for PWSCC. We have developed a laser peening system for PWRs as well after the one for BWRs, and applied it for BMI nozzles, core deluge line nozzles and primary water inlet nozzles of Ikata Unit 1 and 2 of Shikoku Electric Power Company since 2004, which are Japanese operating PWR power plants. In this system, laser oscillators and control devices were packed into two containers placed on the operating floor inside the reactor containment vessel. Laser pulses were delivered through twin optical fibers and irradiated on two portions in parallel to reduce operation time. For BMI nozzles, we developed a tiny irradiation head for small tubes and we peened the inner surface around J

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

    SciTech Connect

    Einziger, R.E.; Tsai, H.C.; Billone, M.C.; Hilton, B.A.

    2002-02-11

    Virginia Power Surry Nuclear Station Pressurized Water Reactor (PWR) fuel was stored in a dry inert atmosphere Castor V/21 cask at the Idaho National Environmental and Engineering Laboratory (INEEL) for 15 years at peak cladding temperatures decreasing from about 350 to 150 C. Prior to the storage, the loaded cask was subjected to extensive thermal benchmark tests. The cask was opened to examine the fuel for degradation and to determine if it was suitable for extended storage. No rod breaches had occurred and no visible degradation or crud/oxide spallation were observed. Twelve rods were removed from the center of the T11 assembly and shipped from INEEL to the Argonne-West HFEF for profilometric scans. Four of these rods were punctured to determine the fission gas release from the fuel matrix and internal pressure in the rods. Three of the four rods were cut into five segments each, then shipped to the Argonne-East AGHCF for detailed examination. The test plan calls for metallographic examination of six samples from two of the rods, microhardness and hydrogen content measurements at or near the six metallographic sample locations, tensile testing of six samples from the two rods, and thermal creep testing of eight samples from the two rods to determine the extent of residual creep life. The results from the profilometry (12 rods), gas release measurements (4 rods), metallographic examinations (2 samples from 1 rod), and microhardness and hydrogen content characterization (2 samples from 1 rod) are reported here. The tensile and creep studies are just starting and will be reported at a later date, along with the additional characterization work to be performed. Although only limited prestorage characterization is available, a number of preliminary conclusions can be drawn based on comparison with characterization of Florida Power Turkey Point rods of a similar vintage. Based on this comparison, it appears that little or no cladding thermal creep and fission gas

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

    SciTech Connect

    Einziger, R.E.; Tsai, H.C.; Billone, M.C.; Hilton, B.A.

    2002-07-01

    Virginia Power Surry Nuclear Station Pressurized Water Reactor (PWR) fuel was stored in a dry inert atmosphere Castor V/21 cask at the Idaho National Environmental and Engineering Laboratory (INEEL) for 15 years at peak cladding temperatures decreasing from about 350 to 150 deg. C. Prior to the storage, the loaded cask was subjected to extensive thermal benchmark tests. The cask was opened to examine the fuel for degradation and to determine if it was suitable for extended storage. No rod breaches had occurred and no visible degradation or crud/oxide spallation were observed. Twelve rods were removed from the center of the T11 assembly and shipped from INEEL to the Argonne-West HFEF for profilometric scans. Four of these rods were punctured to determine the fission gas release from the fuel matrix and internal pressure in the rods. Three of the four rods were cut into five segments each, then shipped to the Argonne-East AGHCF for detailed examination. The test plan calls for metallographic examination of six samples from two of the rods, microhardness and hydrogen content measurements at or near the six metallographic sample locations, tensile testing of six samples from the two rods, and thermal creep testing of eight samples from the two rods to determine the extent of residual creep life. The results from the profilometry (12 rods), gas release measurements (4 rods), metallographic examinations (2 samples from 1 rod), and microhardness and hydrogen content characterization (2 samples from 1 rod) are reported here. The tensile and creep studies are just starting and will be reported at a later date, along with the additional characterization work to be performed. Although only limited pre-storage characterization is available, a number of preliminary conclusions can be drawn based on comparison with characterization of Florida Power Turkey Point rods of a similar vintage. Based on this comparison, it appears that little or no cladding thermal creep and fission

  18. ARM - SGP Rural Driving Hazards

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

    Rural Driving Hazards SGP Related Links Virtual Tour Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site Summer Training SGP Fact Sheet Images Information for Guest Scientists Contacts SGP Rural Driving Hazards The rural location of the Southern Great Plains (SGP) site facilities requires that visitors travel on

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

    SciTech Connect

    Simms, R.; Baker, L. Jr.; Blomquist, C.A.; Ritzman, R.L.

    1986-01-01

    In a hypothetical pressurized water reactor (PWR) large-break loss-of-coolant accident (LOCA) in which the emergency core cooling system fails, fission product decay heating causes water boil-off and reduced heat removal. Zircaloy cladding is oxidized by the steam. The noble gases and volatile fission products such as cesium and iodine that constitute a principal part of the source term will be released from the damaged fuel at or shortly after the time of cladding failure. TREAT test STEP-1 simulated the LOCA environment when the volatile fission products would be released using four fuel elements from the Belgonucleaire BR3 reactor. The principal objective was to collect a portion of the releases carried by the flow stream in a region as close as possible to the test zone. In this paper, the test is described and the results of an analysis of the thermal and steam/hydrogen environment are compared with the test measurements in order to provide a characterization for analysis of fission product releases and aerosol formation. The results of extensive sample examinations are reported separately.

  20. The stress corrosion cracking behavior of alloys 690 and 152 WELD in a PWR environment.

    SciTech Connect

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

    2009-01-01

    Alloys 690 and 152 are the replacement materials of choice for Alloys 600 and 182, respectively. The latter two alloys are used as structural materials in pressurized water reactors (PWRs) and have been found to undergo stress corrosion cracking (SCC). The objective of this work is to determine the crack growth rates (CGRs) in a simulated PWR water environment for the replacement alloys. The study involved Alloy 690 cold-rolled by 26% and a laboratory-prepared Alloy 152 double-J weld in the as-welded condition. The experimental approach involved pre-cracking in a primary water environment and monitoring the cyclic CGRs to determine the optimum conditions for transitioning from the fatigue transgranular to intergranular SCC fracture mode. The cyclic CGRs of cold-rolled Alloy 690 showed significant environmental enhancement, while those for Alloy 152 were minimal. Both materials exhibited SCC of 10{sup -11} m/s under constant loading at moderate stress intensity factors. The paper also presents tensile property data for Alloy 690TT and Alloy 152 weld in the temperature range 25--870 C.

  1. Pressure vessel fracture studies pertaining to the PWR thermal-shock issue: experiment TSE-7

    SciTech Connect

    Cheverton, R.D.; Ball, D.G.; Bolt, S.E.; Iskander, S.K.; Nanstad, R.K.

    1985-08-01

    Thermal-shock experiment TSE-7 was conducted for the purpose of investigating the behavior of surface flaws under pressurized-water reactor (PWR) overcooling-accident conditions. This experiment was the eighth in a series of thermal-shock experiments conducted for this purpose with large steel cylinders (A 508, class-2 chemistry; 991-mm OD x 152-mm wall x 1.2-m length) as a part of the Heavy-Section Steel Technology (HSST) Program. The initial flaw for TSE-7 was a shallow, semielliptical, inner-surface, axially oriented, sharp crack located at midlength of the test cylinder. The thermal shock was applied to the inner surface only, and this was accomplished by effectively dunking the test cylinder, initially at approx.93/sup 0/C, into a large volume of liquid nitrogen. The specific purpose of TSE-7 was to determine whether, in agreement with analysis, a short and shallow surface flaw, in the absence of cladding, would extend on the surface to effectively become a very long flaw as a result of severe thermal-shock loading. During the experiment, there were three major initiation-arrest events. The first event consisted of some radial propagation and very extensive surface extension, with many bifurcations taking place. The second and third events consisted primarily of radial propagation. A fourth initiation event was prevented by warm prestressing. These results were in good agreement with predictions. 50 refs., 77 figs., 13 tabs.

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

    SciTech Connect

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

    1997-04-01

    The regulatory requirements for postulated pipe ruptures have changed significantly since the first nuclear plants were designed. The Leak-Before-Break (LBB) methodology is now accepted as a technically justifiable approach for eliminating postulation of double-ended guillotine breaks (DEGB) in high energy piping systems. The previous pipe rupture design requirements for nuclear power plant applications are responsible for all the numerous and massive pipe whip restraints and jet shields installed for each plant. This results in significant plant congestion, increased labor costs and radiation dosage for normal maintenance and inspection. Also the restraints increase the probability of interference between the piping and supporting structures during plant heatup, thereby potentially impacting overall plant reliability. The LBB approach to eliminate postulating ruptures in high energy piping systems is a significant improvement to former regulatory methodologies, and therefore, the LBB approach to design is gaining worldwide acceptance. However, the methods and criteria for LBB evaluation depend upon the policy of individual country and significant effort continues towards accomplishing uniformity on a global basis. In this paper the historical development of the U.S. LBB criteria will be traced and the results of an LBB evaluation for a typical Japanese PWR primary loop applying U.S. NRC approved methods will be presented. In addition, another approach using the Japanese LBB criteria will be shown and compared with the U.S. criteria. The comparison will be highlighted in this paper with detailed discussion.

  3. Alliance for Rural Electrification | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Alliance for Rural Electrification1 The Alliance for Rural Electrification is the only international business association in the world focusing on the promotion and the...

  4. WINDExchange: Agricultural and Rural Resources and Tools

    WindExchange

    Rural Communities Printable Version Bookmark and Share Wind for Homeowners, Farmers, & Businesses Resources & Tools Agricultural and Rural Resources and Tools This page lists...

  5. Alaska Village Initiatives Rural Small Business Conference

    Energy.gov [DOE]

    The Alaska Rural Business Conference brings together rural businesses and leaders to provide them with networking opportunities, trainings, and technical information.

  6. Whitewater Valley Rural EMC | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Valley Rural EMC Jump to: navigation, search Name: Whitewater Valley Rural EMC Address: P.O. Box 349 Place: Liberty, Indiana Zip: 47353 Sector: Transmission Phone Number: (765)...

  7. Chile rural electrification cooperation

    SciTech Connect

    Flowers, L.

    1997-12-01

    The author describes a joint program to use renewables for rural electrification projects in Chile. The initial focus was in a limited part of the country, involving wind mapping, pilot project planning, training, and development of methodologies for comparative evaluations of resources. To this point three wind hybrid systems have been installed in one region, as a part of the regional private utility, and three additional projects are being designed. Additional resource assessment and training is ongoing. The author points out the difficulties in working with utilities, the importance of signed documentation, and the need to look at these programs as long term because of the time involved in introducing such new technologies.

  8. CEPAN method of analyzing creep collapse of oval cladding. Volume 5. Evaluation of interpellet gap formation and clad collapse in modern PWR fuel rods

    SciTech Connect

    Adams, W.M.; Fisher, H.D.; Litke, H.J.; Mordarski, W.J.

    1985-04-01

    This report presents the results from a review of interpellet-gap formation, ovality, creepdown and clad collapse data in modern PWR fuel rods. Conclusions are reached regarding the propensity of modern PWR fuel to form such gaps and to undergo clad collapse. CEPAN, a creep-collapse predictor approved by the NRC in 1976, has been reformulated to include the creep analysis of cladding with finite interpellet gaps. The basis for this reformulation is discussed in detail. The model previously used in the calculation of the augmentation factor, a peak linear heat rate penalty due to the presence of interpellet gaps within the fuel rod, has been modified to incorporate gap-formation statistics from modern fuel. Finnally, the benefits of the limited gap formation and the CEPAN reformulation for the licensing of modern PWR fuel rods are evaluated.

  9. IG-0573.pub

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

    ... at the INEEL reservation, the Office of Nuclear Energy, Science and Technology (Nuclear Energy) is responsible for waste generated by past and on-going operations at Argonne West. ...

  10. IG-0572.pub

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

    ... Details of Finding Strategic Approach Page 3 Details of ... for monitoring BMIS implementation status or ensuring development ... areas were not present; and performance results ...

  11. Pub-3000: CH45

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

    C. Transporting Hazardous Materials Work Process D. Berkeley Lab Chemical Management System (Chemical Inventory) Work Process E. Chemical Hazard Descriptions Work Process F....

  12. IG-0566.pub

    Office of Environmental Management (EM)

    ... assets; incorporate technology advances; and, update Nuclear Explosive Safety Studies. ... safety program for nuclear explosive operations and associated activities and facilities. ...

  13. SLAC-PUB-8640

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

    ... of the time as a proton and part of the time as a neutron surrounded by a positive meson cloud." and also: "...it is to be expected that the magnetic field associated with the ...

  14. IG-0550.PUB

    Energy Saver

    were not prioritized to balance mission requirements, reduce risks, and minimize life-cycle costs. In some cases, disposition plans were in conflict with requirements for new...

  15. IG-0568.pub

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

    ... simultaneously connected to his personal Internet Service Provider (ISP) at his residence. ... Among other things, the report identified information technology, performance management, ...

  16. Physical Uncertainty Bounds (PUB)

    SciTech Connect

    Vaughan, Diane Elizabeth; Preston, Dean L.

    2015-03-19

    This paper introduces and motivates the need for a new methodology for determining upper bounds on the uncertainties in simulations of engineered systems due to limited fidelity in the composite continuum-level physics models needed to simulate the systems. We show that traditional uncertainty quantification methods provide, at best, a lower bound on this uncertainty. We propose to obtain bounds on the simulation uncertainties by first determining bounds on the physical quantities or processes relevant to system performance. By bounding these physics processes, as opposed to carrying out statistical analyses of the parameter sets of specific physics models or simply switching out the available physics models, one can obtain upper bounds on the uncertainties in simulated quantities of interest.

  17. IG-0564.pub

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

    Washington, DC 20585 August 20, 2002 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman (Signed) Inspector General SUBJECT: INFORMATION: Audit Report on "Advanced ...

  18. IG-0565.pub

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

    AT THE SAVANNAH RIVER SITE AUGUST 2002 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman (Signed) Inspector General SUBJECT: INFORMATION: Audit Report on "Salt Processing ...

  19. IG-0570.pub

    Office of Environmental Management (EM)

    OFFICE OF AUDIT SERVICES DEPLETED URANIUM OPERATIONS AT THE Y-12 NATIONAL SECURITY ... INFORMATION: Audit Report on "Depleted Uranium Operations at the Y-12 National Security ...

  20. SCANNED DARHT.pub

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

    5 Appendices 1. Objective, Scope, and Methodology ...... costs, similar to the funding methodology used for the commissioning of the first axis. ...

  1. IG-0571.pub

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

    1 AUDIT REPORT U.S. DEPARTMENT OF ENERGY OFFICE OF INSPECTOR GENERAL OFFICE OF AUDIT SERVICES IDAHO SETTLEMENT AGREEMENT ACTIVITIES OCTOBER 2002 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman (Signed) Inspector General SUBJECT: INFORMATION: Audit Report on "Idaho Settlement Agreement Activities" BACKGROUND The task of cleaning up contaminated sites and disposing of radioactive waste, as reported in the Department of Energy's recent Performance and Accountability Report, is one

  2. IG-0574.pub

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

    Calutron Isotope Production Capabilities DOE/IG-0574 November 2002 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman (Signed) Inspector General SUBJECT: INFORMATION: Audit Report on the "Calutron Isotope Production Capabilities" BACKGROUND In August 2002, the Department of Energy (Department) formalized its plan to permanently disable the only domestic facility capable of producing electromagnetically enriched stable isotopes. The Department intended to dismantle the equipment in

  3. IG-0569.pub

    Office of Environmental Management (EM)

    the transmission and sale of electric power, natural gas, oil, and hydroelectric power. ... We satisfied our evaluation objective by reviewing applicable laws and regulations ...

  4. IG-0549.pub

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

    ... DOE preferred vitrification because it is assumed that borosilicate glass, or vitrified waste, would be the only waste form acceptable in the high-level waste repository. ...

  5. SLAC-PUB-16075

    Office of Scientific and Technical Information (OSTI)

    Contract No. DE-AC02-76SF00515 and HEP. 1 Introduction The linear optics in ... For high-energy physics, a circular Higgs factory 14 re- quires an extremely large momentum ...

  6. scanned pma.pub

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

    Infrastructure Series Power Marketing Administration Infrastructure Protection ... INFORMATION: Audit Report on "Power Marketing Administration Infrastructure ...

  7. ASCI Pub (Scott)

    National Nuclear Security Administration (NNSA)

    ACADEMIC STRATEGIC ALLIANCES PROGRAM NA-ASC-107R-05-Vol.1-Rev.0 STANFORD UNIVERSITY Center for Integrated Turbulence Simulations CALIFORNIA INSTITUTE OF TECHNOLOGY Center for Simulating the Dynamic Response of Materials PAGE 4 UNIVERSITY OF UTAH Center for the Simulation of Accidental Fires & Explosions PAGE 20 PAGE 8 UNIVERSITY OF CHICAGO Center for Astrophysical Thermonuclear Flashes PAGE 12 UNIVERSITY OF ILLINOIS at Urbana-Champaign Center for Simulation of Advanced Rockets PAGE 16

  8. On-line PWR RHR pump performance testing following motor and impeller replacement

    SciTech Connect

    DiMarzo, J.T.

    1996-12-01

    On-line maintenance and replacement of safety-related pumps requires the performance of an inservice test to determine and confirm the operational readiness of the pumps. In 1995, major maintenance was performed on two Pressurized Water Reactor (PWR) Residual Heat Removal (RHR) Pumps. A refurbished spare motor was overhauled with a new mechanical seal, new motor bearings and equipped with pump`s `B` impeller. The spare was installed into the `B` train. The motor had never been run in the system before. A pump performance test was developed to verify it`s operational readiness and determine the in-situ pump performance curve. Since the unit was operating, emphasis was placed on conducting a highly accurate pump performance test that would ensure that it satisfied the NSSS vendors accident analysis minimum acceptance curve. The design of the RHR System allowed testing of one train while the other was aligned for normal operation. A test flow path was established from the Refueling Water Storage Tank (RWST) through the pump (under test) and back to the RWST. This allowed staff to conduct a full flow range pump performance test. Each train was analyzed and an expression developed that included an error vector term for the TDH (ft), pressure (psig), and flow rate (gpm) using the variance error vector methodology. This method allowed the engineers to select a test instrumentation system that would yield accurate readings and minimal measurement errors, for data taken in the measurement of TDH (P,Q) versus Pump Flow Rate (Q). Test results for the `B` Train showed performance well in excess of the minimum required. The motor that was originally in the `B` train was similarly overhauled and equipped with `A` pump`s original impeller, re-installed in the `A` train, and tested. Analysis of the `A` train results indicate that the RHR pump`s performance was also well in excess of the vendors requirements.

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

    SciTech Connect

    Osamu KAawabata; Mitsuhiro Kajimoto [Japan Nuclear Energy Safety Organization (Japan)

    2006-07-01

    In such severe core damage accident, as small LOCAs with no ECCS injection or station blackout, in which the primary reactor system remains pressurized during core melt down, certain modes of vessel failure would lead to a high pressure ejection of molten core material. In case of a local failure of the lower head, the molten materials would initially be ejected into the cavity beneath the pressure vessel may subsequently be swept out from the cavity to the containment atmosphere and it might cause the early containment failure by direct contact of containment steel liner with core debris. When the contribution of a high-pressure scenario in a core damage frequency increases, early conditional containment failure probability may become large. In the present study, the verification analysis of PHOENICS code and the combining analysis with MELCOR and PHOENICS codes were performed to examine the debris dispersion behavior during high pressure melt ejection. The PHOENICS code which can treat thermal hydraulic phenomena, was applied to the verification analysis for melt dispersion experiments conducted by the Purdue university in the United States. A low pressure melt dispersion experiment at initial pressure 1.4 MPas used metal woods as a molten material was simulated. The analytical results with molten debris dispersion mostly from the model reactor cavity compartment showed an agreement with the experimental result, but the analysis result of a volumetric median diameter of the airborne debris droplets was estimated about 1.5 times of the experimental result. The injection rates of molten debris and steam after reactor vessel failure for a typical PWR plant were analyzed using the MELCOR code. In addition, PHOENICS was applied to a 3D analysis for debris dispersion with low primary pressure at the reactor vessel failure. The analysis result showed that almost all the molten debris were dispersed from the reactor vessel cavity compartment by about 45 seconds after the

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

    SciTech Connect

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

    1985-03-01

    The Nevada Nuclear Waste Storage Investigations Project (NNWSI) is studying the suitability of the welded devitrified Topopah Spring tuff at Yucca Mountain, Nye County, Nevada, for potential use as a high-level nuclear waste repository. In support of the Waste Package task of NNWSI, tests have been conducted under ambient air environment to measure radionuclide release from two pressurized water reactor (PWR) spent fuels in water obtained from the J-13 well near the Yucca Mountain site. Four specimen types, representing a range of fuel physical conditions that may exist in a failed waste canister containing a limited amount of water were tested. The specimen types were: fuel rod sections split open to expose bare fuel particles; rod sections with water-tight end fittings with a 2.5-cm long by 150-{mu}m wide slit through the cladding; rod sections with water-tight end fittings and two 200-{mu}m-diameter holes through the cladding; and undefected rod segments with water-tight end fittings. Radionuclide release results from the first 223-day test runs on H.B. Robinson spent fuel specimens in J-13 water are reported and compared to results from a previous test series in which similar Turkey Point reactor spent fuel specimens were tested on deionized water. Selected initial results are also given for Turkey Point fuel specimens tested on J-13 water. Results suggest that the actinides Pu, Am, Cm and Np are released congruently with U as the UO{sub 2} spent fuel matrix dissolves. Fractional release of {sup 137}Cs and {sup 99}Tc was greater than that measured for the actinides. Generally, lower radionuclide releases were measured for the H.B. Robinson fuel in J-13 water than for Turkey Point Fuel in deionized water. 8 references, 7 figures, 9 tables.

  11. Severe accident modeling of a PWR core with different cladding materials

    SciTech Connect

    Johnson, S. C.; Henry, R. E.; Paik, C. Y.

    2012-07-01

    The MAAP v.4 software has been used to model two severe accident scenarios in nuclear power reactors with three different materials as fuel cladding. The TMI-2 severe accident was modeled with Zircaloy-2 and SiC as clad material and a SBO accident in a Zion-like, 4-loop, Westinghouse PWR was modeled with Zircaloy-2, SiC, and 304 stainless steel as clad material. TMI-2 modeling results indicate that lower peak core temperatures, less H 2 (g) produced, and a smaller mass of molten material would result if SiC was substituted for Zircaloy-2 as cladding. SBO modeling results indicate that the calculated time to RCS rupture would increase by approximately 20 minutes if SiC was substituted for Zircaloy-2. Additionally, when an extended SBO accident (RCS creep rupture failure disabled) was modeled, significantly lower peak core temperatures, less H 2 (g) produced, and a smaller mass of molten material would be generated by substituting SiC for Zircaloy-2 or stainless steel cladding. Because the rate of SiC oxidation reaction with elevated temperature H{sub 2}O (g) was set to 0 for this work, these results should be considered preliminary. However, the benefits of SiC as a more accident tolerant clad material have been shown and additional investigation of SiC as an LWR core material are warranted, specifically investigations of the oxidation kinetics of SiC in H{sub 2}O (g) over the range of temperatures and pressures relevant to severe accidents in LWR 's. (authors)

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

    SciTech Connect

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

    1997-08-01

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

  13. In-pile post-DNB behavior of a nine-rod PWR-type fuel bundle

    SciTech Connect

    Gunnerson, F.S.; MacDonald, P.E.

    1980-01-01

    The results of an in-pile power-cooling-mismatch (PCM) test designed to investigate the behavior of a nine-rod, PWR-type fuel bundle under intermittent and sustained periods of high temperature film boiling operation are presented. Primary emphasis is placed on the DNB and post-DNB events including rod-to-rod interactions, return to nucleate boiling (RNB), and fuel rod failure. A comparison of the DNB behavior of the individual bundle rods with single-rod data obtained from previous PCM tests is also made.

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

    SciTech Connect

    Lee, M.; Fan, C.T. (National Tsing-Hua Univ., Dept. of Nuclear Engineering, Hsinchu (TW))

    1992-07-01

    In this paper, responses of a large, dry pressurized water reactor (PWR) containment in a station blackout sequence are analyzed with the CONTAIN, MARCH3, and MAAP codes. Results show that the predicted containment responses in a station blackout sequence of these three codes are substantially different. Among these predictions, the MAAP code predicts the highest containment pressure because of the large amount of water made available to quench the debris upon vessel failure. The gradual water boiloff by debris pressurizes the containment. The combustible gas burning models in these codes are briefly described and compared.

  15. Implementation of Division F, Title I, Title II, and Title III and Division G, Consolidated and Further Continuing Appropriations Act, 2013, Pub. L. No.113-6

    Energy.gov [DOE]

    Acquisition Letter (AL) 2013-06 and Financial Assistance Letter (FAL) 2013-04 provides implementing instructions and guidance for Division F, Title I, Title II, and Title III and Division G, Consolidated and Further Continuing Appropriations Act, 2013, Pub. L. No.113-6.

  16. Implementation of Division B, Title III, Title V and Division C Title VII, Consolidated Appropriations Act, 2012, Pub. L. No.112-74 and Related Conference Report

    Energy.gov [DOE]

    Acquisition Letter (AL) 2012-08 and Financial Assistance Letter (FAL) 2012-01 provides implementing instructions and guidance for Division B, Title III, Title V and Division C Title VII, Consolidated Appropriations Act, 2012, Pub. L. No.112-74 and Related Conference Report.

  17. USDA- Rural Energy for America Program (REAP) Loan Guarantees

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Rural Energy for America Program (REAP) provides financial assistance to agricultural producers and rural small businesses in rural America to purchase, install, and construct renewable energ...

  18. Korea Rural Community Corp KRC | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

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

  19. China-NREL Rural Electrification Projects | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Rural Electrification Projects Jump to: navigation, search Logo: China Rural Electrification Name China Rural Electrification AgencyCompany Organization National Renewable Energy...

  20. 2016 Alaska Rural Energy Conference

    Energy.gov [DOE]

    The 2016 Alaska Rural Energy Conference is a three-day event that offers a large variety of technical sessions covering new and ongoing energy projects in Alaska, as well as new technologies and needs for Alaska's remote communities.

  1. USDA Rural Development Energy Programs

    Office of Environmental Management (EM)

    rural small businesses in purchasing renewable energy systems and making energy efficiency ... New Farm Bill was passed and signed into law on 2- 7- 14. Changes to funding levels ...

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

    SciTech Connect

    Einziger, R.E.; Cook, J.A.

    1983-01-01

    A five-year whole rod test was initiated to investigate the long-term stability of spent fuel rods under a variety of possible dry storage conditions. Both PWR and BWR rods were included in the test. The first interim examination was conducted after three months of testing to determine if there was any degradation in those defected rods stored in an unlimited air atmosphere. Visual observations, diametral measurements and radiographic smears were used to assess the degree of cladding deformation and particulate dispersal. The PWR rod showed no measurable change from the pre-test condition. The two original artificial defects had not changed in appearance and there was no diametral growth of the cladding. One of the defects in BWR rod showed significant deformation. There was approximately 10% cladding strain at the defect site and a small axial crack had formed. The fuel in the defect did not appear to be friable. The second defect showed no visible change and no cladding strain. Following examination, the test was continued at 230/sup 0/C. Another interim examination is planned during the summer of 1983. This paper discusses the details and meaning of the data from the first interim examination.

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

    SciTech Connect

    Bayless, P.D.; Divine, J.M.

    1982-08-01

    Selected pertinent and uninterpreted data from the third nuclear large break loss-of-coolant experiment (Experiment L2-5) conducted in the Loss-of-Fluid Test (LOFT) facility are presented. The LOFT facility is a 50-MW(t) pressurized water reactor (PWR) system with instruments that measure and provide data on the system thermal-hydraulic and nuclear conditions. The operation of the LOFT system is typical of large (approx. 1000 MW(e)) commercial PWR operations. Experiment L2-5 simulated a double-ended offset shear of a cold leg in the primary coolant system. The primary coolant pumps were tripped within 1 s after the break initiation, simulating a loss of site power. Consistent with the loss of power, the starting of the high- and low-pressure injection systems was delayed. The peak fuel rod cladding temperature achieved was 1078 +- 13 K. The emergency core cooling system re-covered the core and quenched the cladding. No evidence of core damage was detected.

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

    SciTech Connect

    Moeller, M.P.; Martin, G.F.; Haggard, D.L.

    1986-01-01

    The purpose of this report is to present data in support of evaluating the impact of fuel cladding failure events on occupational radiation exposure. To determine quantitatively whether fuel cladding failure contributes significantly to occupational radiation exposure, radiation exposure measurements were taken at comparable locations in two mirror-image pressurized-water reactors (PWRs) and their common auxiliary building. One reactor, Unit B, was experiencing degraded fuel characterized as 0.125% fuel pin-hole leakers and was operating at approximately 55% of the reactor's licensed maximum core power, while the other reactor, Unit A, was operating under normal conditions with less than 0.01% fuel pin-hole leakers at 100% of the reactor's licensed maximum core power. Measurements consisted of gamma spectral analyses, radiation exposure rates and airborne radionuclide concentrations. In addition, data from primary coolant sample results for the previous 20 months on both reactor coolant systems were analyzed. The results of the measurements and coolant sample analyses suggest that a 3560-megawatt-thermal (1100 MWe) PWR operating at full power with 0.125% failed fuel can experience an increase of 540% in radiation exposure rates as compared to a PWR operating with normal fuel. In specific plant areas, the degraded fuel may elevate radiation exposure rates even more.

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

    SciTech Connect

    Papez, K.L.; Risher, D.H.

    1983-05-01

    The loss-of-main-feedwater transient without reactor trip (scram) has received particular attention in pressurized water reactor (PWR) anticipated transient without scram (ATWS) analysis primarily due to the potential for reactor coolant system over pressurization. To assist in the licensing of the U.K. PWR, Sizewell 'B', comparative calculations of a loss-of-feedwater ATWS have been performed using the Westinghouse-developed LOFTRAN loop analysis code and the Electric Power Research Institute/ Energy Incorporated-developed RETRAN-01 code. The calculations were performed with and without the emergency boration system (EBS), which is included in the Sizewell reference design. Initial results showed good agreement between the codes for the major features of the transient, but also a time shift in the transient profiles at the time of the pressurizer pressure peak. This was found to be due to differences in the steam generator modeling, which resulted in a difference in the onset of the very rapid degradation in heat transfer as the steam generators approach dryout. When the same model was used in both codes, very good agreement was obtained. Remaining differences in the results are attributed primarily to differences in the boron injection models, which resulted in an over-prediction of the core boron concentration in the RETRAN calculation. The results with an EBS indicate that the peak pressurizer pressure is relatively insensitive to variations in modeling.

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

    SciTech Connect

    Scobel, James H.; Conway, L.E.; Theofanous, T.G.

    2002-07-01

    In-vessel retention (IVR) of molten core debris via external reactor vessel cooling is the hallmark of the severe accident management strategies in the AP600 passive PWR. The vessel is submerged in water to cool its external surface via nucleate boiling heat transfer. An engineered flow path through the reactor vessel insulation provides cooling water to the vessel surface and vents steam to promote IVR. For the 600 MWe passive plant, the predicted heat load from molten debris to the lower head wall has a large margin to the critical heat flux on the external surface of the vessel, which is the upper limit of the cooling capability. Up-rating the power of the passive plant from 600 to 1000 MWe (AP1000) significantly increases the heat loading from the molten debris to the reactor vessel lower head in the postulated bounding severe accident sequence. To maintain a large margin to the coolability limit for the AP1000, design features and severe accident management (SAM) strategies to increase the critical heat flux on the external surface of the vessel wall need to be implemented. A test program at the ULPU facility at University of California Santa Barbara (UCSB) has been initiated to investigate design features and SAM strategies that can enhance the critical heat flux. Results from ULPU Configuration IV demonstrate that with small changes to the ex-vessel design and SAM strategies, the peak critical heat flux in the AP1000 can be increased at least 30% over the peak critical heat flux predicted for the AP600 configuration. The design and SAM strategy changes investigated in ULPU Configuration IV can be implemented in the AP1000 design and will allow the passive plant to maintain the margin to critical heat flux for IVR, even at the higher power level. Continued testing for IVR phenomena is being performed at UCSB to optimize the AP1000 design and to ensure that vessel failure in a severe accident is physically unreasonable. (authors)

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

    Energy.gov [DOE]

    Results of testing employing surrogate instrumented rods (non-high-burnup, 17 x 17 PWR fuel assembly) to capture the response to the loadings experienced during normal conditions of transport indicate that strain- or stress-based failure of fuel rods seems unlikely; performance of high-burnup fuels continues to be assessed.

  8. Lyon Rural Electric Coop | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Lyon Rural Electric Coop Jump to: navigation, search Name: Lyon Rural Electric Coop Place: Iowa Phone Number: 712-472-2506 Website: www.lyonrec.coop Outage Hotline: 1-800-292-8989...

  9. Alaska Village Initiatives Rural Business Conference

    Energy.gov [DOE]

    Hosted by the Alaska Village Initiative, the 24th Annual Rural Small Business Conference brings together rural businesses and leaders to provide them with networking opportunities, training, and technical information.

  10. PWR core design, neutronics evaluation and fuel cycle analysis for thorium-uranium breeding recycle

    SciTech Connect

    Bi, G.; Liu, C.; Si, S.

    2012-07-01

    This paper was focused on core design, neutronics evaluation and fuel cycle analysis for Thorium-Uranium Breeding Recycle in current PWRs, without any major change to the fuel lattice and the core internals, but substituting the UOX pellet with Thorium-based pellet. The fuel cycle analysis indicates that Thorium-Uranium Breeding Recycle is technically feasible in current PWRs. A 4-loop, 193-assembly PWR core utilizing 17 x 17 fuel assemblies (FAs) was taken as the model core. Two mixed cores were investigated respectively loaded with mixed reactor grade Plutonium-Thorium (PuThOX) FAs and mixed reactor grade {sup 233}U-Thorium (U{sub 3}ThOX) FAs on the basis of reference full Uranium oxide (UOX) equilibrium-cycle core. The UOX/PuThOX mixed core consists of 121 UOX FAs and 72 PuThOX FAs. The reactor grade {sup 233}U extracted from burnt PuThOX fuel was used to fabrication of U{sub 3}ThOX for starting Thorium-. Uranium breeding recycle. In UOX/U{sub 3}ThOX mixed core, the well designed U{sub 3}ThOX FAs with 1.94 w/o fissile uranium (mainly {sup 233}U) were located on the periphery of core as a blanket region. U{sub 3}ThOX FAs remained in-core for 6 cycles with the discharged burnup achieving 28 GWD/tHM. Compared with initially loading, the fissile material inventory in U{sub 3}ThOX fuel has increased by 7% via 1-year cooling after discharge. 157 UOX fuel assemblies were located in the inner of UOX/U{sub 3}ThOX mixed core refueling with 64 FAs at each cycle. The designed UOX/PuThOX and UOX/U{sub 3}ThOX mixed core satisfied related nuclear design criteria. The full core performance analyses have shown that mixed core with PuThOX loading has similar impacts as MOX on several neutronic characteristic parameters, such as reduced differential boron worth, higher critical boron concentration, more negative moderator temperature coefficient, reduced control rod worth, reduced shutdown margin, etc.; while mixed core with U{sub 3}ThOX loading on the periphery of core has no

  11. Simulation of German PKL refill/reflood experiment K9A using RELAP4/MOD7. [PWR

    SciTech Connect

    Hsu, M.T.; Davis, C.B.; Behling, S.R.

    1981-11-01

    This paper describes a RELAP4/MOD7 simulation of West Germany's Kraftwerk Union (KWU) Primary Coolant Loop (PKL) refill/reflood experiment K9A. RELAP4/MOD7, a best-estimate computer program for the calculation of thermal and hydraulic phenomena in a nuclear reactor or related system, is the latest version in the RELAP4 code development series. This study was the first major simulation using RELAP4/MOD7 since its release by the Idaho National Engineering Laboratory (INEL). The PKL facility is a reduced scale (1:134) representation of a typical West German four-loop 1300 MW pressurized water reactor (PWR). A prototypical scale of the total volume to power ratio was maintained. The test facility was designed specifically for an experiment simulating the refill/reflood phase of a Loss-of-Coolant Accident (LOCA).

  12. Development code for sensitivity and uncertainty analysis of input on the MCNPX for neutronic calculation in PWR core

    SciTech Connect

    Hartini, Entin Andiwijayakusuma, Dinan

    2014-09-30

    This research was carried out on the development of code for uncertainty analysis is based on a statistical approach for assessing the uncertainty input parameters. In the butn-up calculation of fuel, uncertainty analysis performed for input parameters fuel density, coolant density and fuel temperature. This calculation is performed during irradiation using Monte Carlo N-Particle Transport. The Uncertainty method based on the probabilities density function. Development code is made in python script to do coupling with MCNPX for criticality and burn-up calculations. Simulation is done by modeling the geometry of PWR terrace, with MCNPX on the power 54 MW with fuel type UO2 pellets. The calculation is done by using the data library continuous energy cross-sections ENDF / B-VI. MCNPX requires nuclear data in ACE format. Development of interfaces for obtaining nuclear data in the form of ACE format of ENDF through special process NJOY calculation to temperature changes in a certain range.

  13. Impact Analysis of a Dipper-Type and Multi Spring-Type Fuel Rod Support Grid Assemblies in PWR

    SciTech Connect

    Song, K.N.; Yoon, K.H.; Park, K.J.; Park, G.J.; Kang, B.S.

    2002-07-01

    A spacer grid is one of the main structural components in a fuel assembly of a Pressurized light Water Reactor (PWR). It supports fuel rods, guides cooling water, and maintains geometry from external impact loads. A simulation is performed for the strength of a spacer grid under impact load. The critical impact load that leads to plastic deformation is identified by a free-fall test. A finite element model is established for the nonlinear simulation of the test. The simulation model is tuned based on the free-fall test. The model considers the aspects of welding and the contacts between components. Nonlinear finite element analysis is carried out by a software system called LS/DYNA3D. The results are discussed from a design viewpoint. (authors)

  14. The influence of dissolved hydrogen on primary water stress corrosion cracking of Alloy 600 at PWR steam generator operating temperatures

    SciTech Connect

    Jacko, R.J.; Economy, G.; Pement, F.W.

    1992-12-31

    PWR primary coolant chemistry uses an intentional dissolved hydrogen concentration of 20 to 50 ml (STP)/kg of water to effect a net suppression of oxygen-producing radiolysis, to minimize corrosion in primary loop materials and to maintain a low redox potential. Speculation has attended a possible influence of dissolved hydrogen on the kinetics of initiation of Primary Water Stress Corrosion Cracking (PWSCC) behavior of Alloy 600 steam generator tubing. Three series of experiments are presented for conditions in which the level of dissolved hydrogen was intentionally varied over the hydrogen and temperature ranges of interest for steam generator operation. No significant effect of dissolved hydrogen was found on PWSCC of Alloy 600.

  15. Determination of the threshold values for corrosion fatigue crack growth rate of pressure vessel steels in PWR primary water

    SciTech Connect

    Haenninen, H.E.; Arilahti, E.; Ehrnsten, U.

    1992-12-31

    Corrosion fatigue crack growth rates over a range of frequencies from 10 Hz to 0.00001 Hz in two materials that have exhibited low-rate (A508 Class 3) and high-rate (A533B) crack growth behaviour at 288{degrees}C were studied at 200{degrees}C in PWR primary water. The frequency values above which marked environmental enhancement was observed were determined. Also the threshold values in terms of {Delta}K{sub th}, above which the marked environmental enhancement was observed in the crack growth rate, were determined both for A533B steel and Soviet pressure vessel steels with certain test parameters. Based on the extensive fractography the crack growth rate results are discussed mechanistically.

  16. The toughness of irradiated pressure water reactor (PWR) vessel shell rings and the effect of segregation zones

    SciTech Connect

    Bethmont, M.; Frund, J.M.; Housin, B.; Soulat, P.

    1996-12-31

    To establish the integrity of pressure water reactor (PWR) vessels it is necessary to determine the toughness of A508Cl.3 steel at the end of its life, that is after thermal aging and irradiation embrittlement. In safety analyses the toughness can be deduced from a reference curve set forth in the code (ASME or RCC-M). The validity of the reference curve has been verified for several years for unirradiated French reactor vessels. Tests were performed on specimens taken from materials having heterogeneities in chemical composition. For most of the test results the reference curve is a lower bound. To solve te problem of determining the toughness of SA 508 Cl.3 steel after irradiation and in the presence of possible heterogeneities, the toughness results were gathered. The synthesis shows that the RCC-M code curve is conservative.

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

    SciTech Connect

    McCardell, R.K.; MacDonald, P.E.

    1980-01-01

    This paper presents an overview of the results of the experimental program being conducted in the Power Burst Facility and the relationship of these results to certain safety and licensing issues. The safety issues that were addressed by the Power-Cooling-Mismatch, Reactivity Initiated Accident, and Loss of Coolant Accident tests, which comprised the original test program in the Power Burst Facility, are discussed. The resolution of these safety issues based on the results of the thirty-six tests performed to date, is presented. The future resolution of safety issues identified in the new Power Burst Facility test program which consists of tests which simulate BWR and PWR operational transients, anticipated transients without scram, and severe fuel damage accidents, is described.

  18. USDA Rural Business Enterprise Grant (RBEG) Program

    Energy.gov [DOE]

    Request for Proposals for funding to support the development of small and emerging private business enterprises in rural Alaska

  19. Chemical System Decontamination at PWR Power Stations Biblis A and B by Advanced System Decontamination by Oxidizing Chemistry (ASDOC-D) Process Technology - 13081

    SciTech Connect

    Loeb, Andreas; Runge, Hartmut; Stanke, Dieter; Bertholdt, Horst-Otto; Adams, Andreas; Impertro, Michael; Roesch, Josef

    2013-07-01

    For chemical decontamination of PWR primary systems the so called ASDOC-D process has been developed and qualified at the German PWR power station Biblis. In comparison to other chemical decontamination processes ASDOC-D offers a number of advantages: - ASDOC-D does not require separate process equipment but is completely operated and controlled by the nuclear site installations. Feeding of chemical concentrates into the primary system is done by means of the site's dosing systems. Process control is performed by standard site instrumentation and analytics. - ASDOC-D safely prevents any formation and precipitation of insoluble constituents - Since ASDOC-D is operated without external equipment there is no need for installation of such equipment in high radioactive radiation surrounding. The radioactive exposure rate during process implementation and process performance may therefore be neglected in comparison to other chemical decontamination processes. - ASDOC-D does not require auxiliary hose connections which usually bear high leakage risk. The above mentioned technical advantages of ASDOC-D together with its cost-effectiveness gave rise to Biblis Power station to agree on testing ASDOC-D at the volume control system of PWR Biblis unit A. By involving the licensing authorities as well as expert examiners into this test ASDOC-D received the official qualification for primary system decontamination in German PWR. As a main outcome of the achieved results NIS received contracts for full primary system decontamination of both units Biblis A and B (each 1.200 MW) by end of 2012. (authors)

  20. Technical basis for the initiation and cessation of environmentally-assisted cracking of low-alloy steels in elevated temperature PWR environments

    SciTech Connect

    James, L.A.

    1997-10-01

    The Section 11 Working Group on Flaw Evaluation of the ASME B and PV Code Committee is considering a Code Case to allow the determination of the conditions under which environmentally-assisted cracking of low-alloy steels could occur in PWR primary environments. This paper provides the technical support basis for such an EAC Initiation and Cessation Criterion by reviewing the theoretical and experimental information in support of the proposed Code Case.

  1. Implementation of Division D, Titles III and V, and Division E, Title VII of the Consolidated Appropriations Act, 2014, Pub. L. No. 113-76.

    Energy.gov [DOE]

    Acquisition Letter (AL) 2014-04 and Financial Assistance Letter (FAL) 2014-01 have been revised to remove language from Section 502 that was not carried forward from previous appropriation acts. FAL 2014-01 was also revised to update the Corporate Felony Conviction and Federal Tax Liability Representations and Assurances and the Conference Spending term. As a result, AL 2014-04 (Rev 1) and FAL 2014-01 (Rev 1) provide implementing instructions and guidance for Division D, Titles III and V, and Division E, Title VII of the Consolidated Appropriations Act, 2014, Pub. L. No. 113-76.

  2. Continuing Appropriations Act, 2014-- Implementation of Division F, Title I, Title II, and Title III, and Division G, Consolidated and Further Continuing Appropriations Act, 2013, Pub. L. No. 113-6

    Energy.gov [DOE]

    Section 101(a)(6) of the Continuing Appropriations Act, 2014, Pub. L No. 113-46, makes appropriations available through January 15, 2014 for continuing projects or activities that were conducted...

  3. Rural Cooperative Geothermal Development Electric & Agriculture |

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

    Department of Energy Rural Cooperative Geothermal Development Electric & Agriculture Rural Cooperative Geothermal Development Electric & Agriculture DOE 2010 Geothermal Program Peer Review; Low Temperature Demonstration Projects low_silveria_rural_electric_coop.pdf (557.69 KB) More Documents & Publications Southwest Alaska Regional Geothermal Energy Project District Wide Geothermal Heating Conversion Blaine County School District Novel Energy Conversion Equipment for Low

  4. Rural Innovations Network | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Network Jump to: navigation, search Name: Rural Innovations Network Place: India Sector: Services Product: General Financial & Legal Services ( Charity Non-profit Association...

  5. Intermountain Rural Elec Assn | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Rural Elec Assn Place: Colorado Website: www.irea.coop Twitter: @IREAColorado Facebook: https:www.facebook.comIntermountainREA Outage Hotline: 1-800-332-9540 References:...

  6. Rural Electric Coop, Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Facebook: https:www.facebook.compagesRural-Electric-Cooperative-Inc116401145072740?refts Outage Hotline: 855-399-2683 References: EIA Form EIA-861 Final Data File for 2010 -...

  7. Modular Biomass Systems Could Boost Rural Areas

    Energy.gov [DOE]

    Increased ethanol production will help revitalize the rural economy and decrease America's dependence on foreign oil, but there are other ways to create opportunities in the farmlands.

  8. Linn County Rural Electric Cooperative - Agricultural Energy...

    Energy.gov [DOE] (indexed site)

    water heater installed, additional 25 bonus if electric dryer installed Energy Star Television: 50 Summary Linn County Rural Electric Cooperative Association (Linn County RECA)...

  9. 2016 Kawerak/Rural Providers' Conference

    Energy.gov [DOE]

    The Kawerak/Rural Providers' Conference is an annual gathering and cultural celebration featuring heads-on cultural events, moderated discussions, workshops, and keynote speakers.

  10. USDA Rural Development Washington State Workshop

    Energy.gov [DOE]

    The U.S. Department of Agriculture is hosting a Washington Rural Development Workshop. Speakers will cover local and regional broadband initiatives program and broadband success stories,...

  11. Building Energy Efficiency in Rural China

    SciTech Connect

    Evans, Meredydd; Yu, Sha; Song, Bo; Deng, Qinqin; Liu, Jing; Delgado, Alison

    2014-04-01

    Rural buildings in China now account for more than half of Chinas total building energy use. Forty percent of the floorspace in China is in rural villages and towns. Most of these buildings are very energy inefficient, and may struggle to meet basic needs. They are cold in the winter, and often experience indoor air pollution from fuel use. The Chinese government plans to adopt a voluntary building energy code, or design standard, for rural homes. The goal is to build on Chinas success with codes in urban areas to improve efficiency and comfort in rural homes. The Chinese government recognizes rural buildings represent a major opportunity for improving national building energy efficiency. The challenges of rural China are also greater than those of urban areas in many ways because of the limited local capacity and low income levels. The Chinese government wants to expand on new programs to subsidize energy efficiency improvements in rural homes to build capacity for larger-scale improvement. This article summarizes the trends and status of rural building energy use in China. It then provides an overview of the new rural building design standard, and describes options and issues to move forward with implementation.

  12. Club for Rural Electrification | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Electrification Jump to: navigation, search Name: Club for Rural Electrification Place: Freiburg, Germany Zip: 79114 Sector: Solar Product: An industry association of German...

  13. Viet Nam Rural Electrification | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Rural Electrification Location of project Vietnam Energy Services Lighting, Cooking and water heating, Space heating, Cooling Year initiated 2009 Organization Asian Development...

  14. Renewable Energy Technologies for Rural Electrification - The...

    OpenEI (Open Energy Information) [EERE & EIA]

    Sector Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Renewable Energy Technologies for Rural Electrification - The Role of the Private Sector AgencyCompany...

  15. Improvement of the thermal margins in the Swedish Ringhals-3 PWR by introducing new fuel assemblies with thorium

    SciTech Connect

    Lau, C. W.; Demaziere, C.; Nylen, H.; Sandberg, U.

    2012-07-01

    Thorium is a fertile material and most of the past research has focused on breeding thorium to fissile material. In this paper, the focus is on using thorium to improve the thermal margins by homogeneously distributing thorium in the fuel pellets. A proposed uranium-thorium-based fuel assembly is simulated for the Swedish Ringhals-3 PWR core in a realistic demonstration. All the key safety parameters, such as isothermal temperature coefficient of reactivity, Doppler temperature of reactivity, boron worth, shutdown margins and fraction of delayed neutrons are studied in this paper, and are within safety limits for the new core design using the uranium-thorium-based fuel assemblies. The calculations were performed by the two-dimensional transport code CASMO-4E and the two group steady-state three dimensional nodal code SIMULATE-3 from Studsvik Scandpower. The results showed that the uranium-thorium-based fuel assembly improves the thermal margins, both in the pin peak power and the local power (Fq). The improved thermal margins would allow more flexible core designs with less neutron leakage or could be used in power uprates to offer efficient safety margins. (authors)

  16. Presentation of the MERC work-flow for the computation of a 2D radial reflector in a PWR

    SciTech Connect

    Clerc, T.; Hebert, A.; Leroyer, H.; Argaud, J. P.; Poncot, A.; Bouriquet, B.

    2013-07-01

    This paper presents a work-flow for computing an equivalent 2D radial reflector in a pressurized water reactor (PWR) core, in adequacy with a reference power distribution, computed with the method of characteristics (MOC) of the lattice code APOLLO2. The Multi-modelling Equivalent Reflector Computation (MERC) work-flow is a coherent association of the lattice code APOLLO2 and the core code COCAGNE, structured around the ADAO (Assimilation de Donnees et Aide a l'Optimisation) module of the SALOME platform, based on the data assimilation theory. This study leads to the computation of equivalent few-groups reflectors, that can be spatially heterogeneous, which have been compared to those obtained with the OPTEX similar methodology developed with the core code DONJON, as a first validation step. Subsequently, the MERC work-flow is used to compute the most accurate reflector in consistency with all the R and D choices made at Electricite de France (EDF) for the core modelling, in terms of number of energy groups and simplified transport solvers. We observe important reductions of the power discrepancies distribution over the core when using equivalent reflectors obtained with the MERC work-flow. (authors)

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

    SciTech Connect

    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.

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

    SciTech Connect

    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.

  19. In-plant test and evaluation of the neutron collar for verification of PWR fuel assemblies at Resende, Brazil

    SciTech Connect

    Menlove, H.O.; Marzo, M.A.S.; de Almeida, S.G.; de Almeida, M.C.; Moitta, L.P.M.; Conti, L.F.; de Paiva, J.R.T.

    1985-11-01

    The neutron-coincidence collar has been evaluated for the measurement of pressurized-water reactor (PWR) fuel assemblies at the Fabrica de Elementos Combustiveis plant in Resende, Brazil. This evaluation was part of the cooperative-bilateral-safeguards technical-exchange program between the United States and Brazil. The neutron collar measures the STVU content per unit length of full fuel assemblies using neutron interrogation and coincidence counting. The STYU content is measured in the passive mode without the AmLi neutron-interrogation source. The extended evaluation took place over a period of 6 months with both scanning and single-zone measurements. The results of the tests gave a coincidence-response standard deviation of 0.7% (sigma = 1.49% for mass) for the active case and 2.5% for the passive case in 1000-s measurement times. The length measurement in the scanning mode was accurate to 0.77%. The accuracies of different calibration methods were evaluated and compared.

  20. Tests with Inconel 600 to obtain quantitative stress-corrosion cracking data for evaluating service performance. [PWR

    SciTech Connect

    Bandy, R.; van Rooyen, D.

    1982-09-01

    Inconel 600 tubes in pressurized water reactor (PWR) steam generators form a pressure boundary between radioactive primary water and secondary water which is converted to steam and used for generating electricity. Under operating conditions the performance of alloy 600 has been good, but with some occasional small leaks resulting from stress corrosion cracking (SCC), related to the presence of unusually high residual or operating stresses. The suspected high stresses can result from either the deformation of tubes during manufacture, or distortion during abnormal conditions such as denting. The present experimental program addresses two specific conditions, i.e., (1) where deformation occurs but is no longer active, such as when denting is stopped and (2) where plastic deformation of the metal continues, as would occur during denting. Laboratory media consist of pure water as well as solutions to simulate environments that would apply in service; tubing from actual production is used in carrying out these tests. The environments include both normal and off chemistries for primary and secondary water. The results reported here were obtained in several different tests. The main ones are (1) split tube reverse U-bends, (2) constant extension rate tests (CERT), and (3) constant load. The temperature range covered is 290 to 365/sup 0/C.

  1. Electric Cooperatives Channel Solar Resources to Rural American...

    Office of Environmental Management (EM)

    Electric Cooperatives Channel Solar Resources to Rural American Communities Electric Cooperatives Channel Solar Resources to Rural American Communities February 4, 2016 - 12:07pm ...

  2. Modified Microgrid Concept for Rural Electrification in Africa...

    OpenEI (Open Energy Information) [EERE & EIA]

    Modified Microgrid Concept for Rural Electrification in Africa Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Modified Microgrid Concept for Rural Electrification in...

  3. 2014 HAC Rural Housing Conference: Retool, Rebuild, Renew

    Energy.gov [DOE]

    The biennial HAC Rural Housing Conference brings together stakeholders in the field of rural affordable housing from local nonprofits, federal agencies, Congress, state and local governments, and...

  4. USDA- Rural Energy for America Program (REAP) Grants

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Rural Energy for America Program (REAP) provides financial assistance to agricultural producers and rural small businesses in America to purchase, install, and construct renewable energy syst...

  5. Climate Change: building the resilience of poor rural communities...

    OpenEI (Open Energy Information) [EERE & EIA]

    of poor rural communities Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Climate Change: building the resilience of poor rural communities AgencyCompany...

  6. Mozambique-Biofuels, Land Access and Rural Livelihoods | Open...

    OpenEI (Open Energy Information) [EERE & EIA]

    Biofuels, Land Access and Rural Livelihoods Jump to: navigation, search Name Mozambique-Biofuels, Land Access and Rural Livelihoods AgencyCompany Organization International...

  7. Tanzania-Biofuels, Land Access and Rural Livelihoods | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Tanzania-Biofuels, Land Access and Rural Livelihoods Jump to: navigation, search Name Tanzania-Biofuels, Land Access and Rural Livelihoods AgencyCompany Organization...

  8. Farmers Rural Electric Coop Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

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

  9. Jianghe Rural Electricity Development Co Ltd | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Jianghe Rural Electricity Development Co Ltd Jump to: navigation, search Name: Jianghe Rural Electricity Development Co Ltd Place: Fuzhou, Fujian Province, China Product:...

  10. The Gut Microbiota of Rural Papua New Guineans: Composition,...

    Office of Scientific and Technical Information (OSTI)

    The Gut Microbiota of Rural Papua New Guineans: Composition, Diversity Patterns, and Ecological Processes Prev Next Title: The Gut Microbiota of Rural Papua New Guineans: ...

  11. The Other 15%: Expanding Energy Efficiency to Rural Populations...

    Energy Saver

    The Other 15%: Expanding Energy Efficiency to Rural Populations The Other 15%: Expanding Energy Efficiency to Rural Populations Better Buildings Residential Network Peer Exchange ...

  12. Rural Electrification Act of 1936 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    901 et seq. DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for Rural Electrification Act of 1936 Citation Rural Electrification Act of...

  13. Alaska Rural Manager Panelists Call for Nominations

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Alaska Rural Managers are seeking nominations for city, tribal, and utility managers to participate in several Anchorage focus group/workshops this April. Selected panelists will represent their profession and will help develop guidelines for the training and education of Alaska's Rural Managers.

  14. Using Clinical Data, Hypothesis Generation Tools and PubMed Trends to Discover the Association between Diabetic Retinopathy and Antihypertensive Drugs

    SciTech Connect

    Senter, Katherine G; Sukumar, Sreenivas R; Patton, Robert M; Chaum, Ed

    2015-01-01

    Diabetic retinopathy (DR) is a leading cause of blindness and common complication of diabetes. Many diabetic patients take antihypertensive drugs to prevent cardiovascular problems, but these drugs may have unintended consequences on eyesight. Six common classes of antihypertensive drug are angiotensin converting enzyme (ACE) inhibitors, alpha blockers, angiotensin receptor blockers (ARBs), -blockers, calcium channel blockers, and diuretics. Analysis of medical history data might indicate which of these drugs provide safe blood pressure control, and a literature review is often used to guide such analyses. Beyond manual reading of relevant publications, we sought to identify quantitative trends in literature from the biomedical database PubMed to compare with quantitative trends in the clinical data. By recording and analyzing PubMed search results, we found wide variation in the prevalence of each antihypertensive drug in DR literature. Drug classes developed more recently such as ACE inhibitors and ARBs were most prevalent. We also identified instances of change-over-time in publication patterns. We then compared these literature trends to a dataset of 500 diabetic patients from the UT Hamilton Eye Institute. Data for each patient included class of antihypertensive drug, presence and severity of DR. Graphical comparison revealed that older drug classes such as diuretics, calcium channel blockers, and -blockers were much more prevalent in the clinical data than in the DR and antihypertensive literature. Finally, quantitative analysis of the dataset revealed that patients taking -blockers were statistically more likely to have DR than patients taking other medications, controlling for presence of hypertension and year of diabetes onset. This finding was concerning given the prevalence of -blockers in the clinical data. We determined that clinical use of -blockers should be minimized in diabetic patients to prevent retinal damage.

  15. RELAP-7 Level 2 Milestone Report: Demonstration of a Steady State Single Phase PWR Simulation with RELAP-7

    SciTech Connect

    David Andrs; Ray Berry; Derek Gaston; Richard Martineau; John Peterson; Hongbin Zhang; Haihua Zhao; Ling Zou

    2012-05-01

    The document contains the simulation results of a steady state model PWR problem with the RELAP-7 code. The RELAP-7 code is the next generation nuclear reactor system safety analysis code being developed at Idaho National Laboratory (INL). The code is based on INL's modern scientific software development framework - MOOSE (Multi-Physics Object-Oriented Simulation Environment). This report summarizes the initial results of simulating a model steady-state single phase PWR problem using the current version of the RELAP-7 code. The major purpose of this demonstration simulation is to show that RELAP-7 code can be rapidly developed to simulate single-phase reactor problems. RELAP-7 is a new project started on October 1st, 2011. It will become the main reactor systems simulation toolkit for RISMC (Risk Informed Safety Margin Characterization) and the next generation tool in the RELAP reactor safety/systems analysis application series (the replacement for RELAP5). The key to the success of RELAP-7 is the simultaneous advancement of physical models, numerical methods, and software design while maintaining a solid user perspective. Physical models include both PDEs (Partial Differential Equations) and ODEs (Ordinary Differential Equations) and experimental based closure models. RELAP-7 will eventually utilize well posed governing equations for multiphase flow, which can be strictly verified. Closure models used in RELAP5 and newly developed models will be reviewed and selected to reflect the progress made during the past three decades. RELAP-7 uses modern numerical methods, which allow implicit time integration, higher order schemes in both time and space, and strongly coupled multi-physics simulations. RELAP-7 is written with object oriented programming language C++. Its development follows modern software design paradigms. The code is easy to read, develop, maintain, and couple with other codes. Most importantly, the modern software design allows the RELAP-7 code to

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

    SciTech Connect

    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.

  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

    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

    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. Probability of pipe fracture in the primary coolant loop of a PWR plant. Volume 2: primary coolant loop model. Final report

    SciTech Connect

    Eberhardt, A.C.

    1981-09-01

    This report describes the Zion Station reactor coolant loop model developed by Sargent and Lundy Engineers for Lawrence Livermore National Laboratory as part of its Load Combination Program. This model was developed for use in performing seismic time history analyses of an actual pressurized water reactor (PWR) system. It includes all major items affecting the seismic response of a 4-loop Westinghouse nuclear steam supply system: the components, supports, and interconnecting piping. The model was further expanded to permit static analysis of dead weight, thermal, and internal pressure load conditions.

  20. Probability of pipe fracture in the primary coolant loop of a PWR plant. Volume 5: probabilistic fracture mechanics analysis. Final report

    SciTech Connect

    Harris, D.O.; Lim, E.Y.; Dedhia, D.D.

    1981-08-01

    The purpose of the portion of the Load Combination Program covered in this volume was to estimate the probability of a seismic induced loss-of-coolant accident (LOCA) in the primary piping of a commercial pressurized water reactor (PWR). Such results are useful in rationally assessing the need to design reactor primary piping systems for the simultaneous occurrence of these two potentially high stress events. The primary piping system at Zion I was selected for analysis. Attention was focussed on the girth butt welds in the hot leg, cold leg and cross-over leg, which are centrifugally cast austenitic stainless steel lines with nominal outside diameters of 32 - 37 inches.

  1. Probability of pipe fracture in the primary coolant loop of a PWR Plant. Volume 2. Primary Coolant Loop Model. Load Combination Program, Project I final report

    SciTech Connect

    Eberhardt, A.C.

    1981-06-01

    This report describes the Zion Station reactor coolant loop model developed by Sargent and Lundy Engineers for Lawrence Livermore National Laboratory as part of its Load Combination Program. This model was developed for use in performing seismic time history analyses of an actual pressurized water reactor (PWR) system. It includes all major items affecting the seismic response of a 4-loop Westinghouse nuclear steam supply system: the components, supports, and interconnecting piping. The model was further expanded to permit static analysis of dead weight, thermal, and internal pressure load conditions. 7 refs., 42 figs., 9 tabs.

  2. BABAR-PUB-14/002 SLAC-PUB-15979

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

    ab , 55 G. Piredda a , 55 C. B unger, 56 S. Dittrich, 56 O. Gr unberg, 56 T. Hartmann, 56 M. Hess, 56 T. Leddig, 56 C. Vo, 56 R. Waldi, 56 T. Adye, 57 E. O. Olaiya, 57...

  3. Rural electric cooperatives IRP survey

    SciTech Connect

    Garrick, C.

    1995-11-01

    This report summarizes the integrated resource planning (IRP) practices of US rural electric cooperatives and the IRP policies which influence these practices. It was prepared by the National Renewable Energy Laboratory (NREL) and its subcontractor Garrick and Associates to assist the US Department of Energy (DOE) in satisfying the reporting requirements of Title 1, Subtitle B, Section 111(e)(3) of the Energy Policy Act of 1992 (EPAct), which states: (e) Report--Not later than 2 years after the date of the enactment of this Act, the Secretary (of the US Department of Energy) shall transmit a report to the President and to the Congress containing--(the findings from several surveys and evaluations, including:); (3) a survey of practices and policies under which electric cooperatives prepare IRPs, submit such plans to REA, and the extent to which such integrated resource planning is reflected in rates charged to customers.

  4. Sustainable Energy Solutions for Rural Alaska | Department of Energy

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

    Sustainable Energy Solutions for Rural Alaska Sustainable Energy Solutions for Rural Alaska Photo of the Sustainable Energy Solutions for Rural Alaska report. The report, "Sustainable Energy Solutions for Rural Alaska," provides recommendations from a study conducted over the course of 18 months that involved in-person interviews with utility staff and community members from more than 30 Alaska rural communities. The purpose of the study was to understand the current challenges and

  5. Newsletter Jan draft 010512.pub

    Office of Environmental Management (EM)

    Green Holidays Fuel Cell Lights Up Festivities at Secretary Chu's Holiday Party For the first time ever, DOE's annual holiday party featured lights powered by a clean, efficient ...

  6. Newsletter Dec draft 120211.pub

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

    GreenGov Awards The White House Council on Environmental Quality (CEQ) recognized two DOE sites for the 2011 GreenGov Presidential Awards:  The Green Innovation Award - The National Renewable Energy Laboratory (NREL) designed a net-zero energy data center that creates as much energy as it consumes by using the climate as a natural coolant, capturing waste heat to ventilate in the cooler months, and employing advanced equipment to minimize energy usage. The data center consumes 81 percent

  7. Newsletter June draft 060512.pub

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

    Oak Ridge Na onal Laboratory hosted its second annual regional Sustainability Summit on May 2-3, 2012. Over 110 a endees represented ci es, coun es, states, universi es, industry, power providers and DOE labs. The Summit covered three major subject areas: low- carbon power genera on, sustainable transporta on, and energy efficiency in buildings. Addi onal informa on on ORNL's Sustainable Campus Ini a ve may be found at h p://sustainability-ornl.org. Send us your champion! SUSTAINABILITY

  8. Newsletter Mar draft 030612.pub

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

    STORIES Retrofits under way at LANL's Occupational Medicine Building Los Alamos NaƟonal Laboratory (LANL) is saving 764 million BTUs from steam and electricity and $11,900 in costs each year at the "Occ Med" building, one of LANL's Įrst High Performance Sustainable Buildings (HPSB). The LANL HPSB Team selected 31 buildings for reͲ commissioning to review energy usage and implement eĸciency improvements and system upgrades. Improvements include: establishing a nightͲsetback

  9. Newsletter May Final 050112.pub

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

    Send us your champion! Two members of DOE were recently honored at the Federal 100 Awards which recognize government and industry leaders in the Federal IT community . DOE CIO, Michael Loca s, was honored for his impact on the collabora ve cybersecurity approach he has taken across the department and throughout the federal government, in par cular the crea on of the Joint Cybersecurity Coordina on Center. Peter Tseronis, Chief Technology Office for the CIO won for his keen eye on ensuring that

  10. Newsletter Oct draft 100611.pub

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

    Milestones Metering Per DOE's 2010 SSPP, DOE sites are submitting new or updated metering plans. Best practices include:  Analysis of practicality and cost-effectiveness;  Summary tables of scheduled metering by building;  Plans on how to use the information generated and;  Financial plans, such as the use of ESPC, third party funding, and internal funds. DOE's Forrestal Building installed electrical sub-meters to measure ligh ng and plug-load electricity consump on

  11. SLAC-PUB-15224 August

    Office of Scientific and Technical Information (OSTI)

    24 August 25, 2012 Theoretical Summary Lecture for Higgs Hunting 2012 Michael E. Peskin 1 SLAC, Stanford University, Menlo Park, California 94025 USA ABSTRACT In this lecture, I...

  12. SLAC-PUB-15193 Compact

    Office of Scientific and Technical Information (OSTI)

    10 decompression (black), and for a transverse gradient undulator without decompression (red). Another method to reduce the gain length of a large energy spread beam is by decom-...

  13. SLAC-PUB-15178 July

    Office of Scientific and Technical Information (OSTI)

    D. Zep- penfeld, Phys. Rev. D 70, 113009 (2004) hep-ph0406323, hep-ph0407190. 7 R. Lafaye, T. Plehn, M. Rauch, D. Zerwas and M. D uhrssen, JHEP 08 (2009) 009...

  14. SLAC-PUB-15416 April

    Office of Scientific and Technical Information (OSTI)

    Accelerator Laboratory Stanford University Menlo Park, CA 94025, USA Frank Zimmermann CERN, Geneva, Switzerland Abstract A ring-based Higgs factory with a center-of-mass energy...

  15. LicWk3.pub

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

    a successful licensee of this product and the benefits you anticipate (increased market share, new market niche, etc.). We give preference to licensing opportunities that will...

  16. SLAC-PUB-15832 November

    Office of Scientific and Technical Information (OSTI)

    AdSCFT correspondence is a powerful tool for computing observables in strongly coupled systems with conformal symmetry by mapping them to weakly coupled dual gravitational...

  17. 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

    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.

  18. Alaska Rural Energy Conference- Federal Energy Track

    Energy.gov [DOE]

    On the first day of the Alaska Rural Energy Conference, the U.S. Department of Energy (DOE) Office of Indian Energy is hosting a federal energy track to cover federal programs and opportunities for Alaska Native villages.

  19. USDA Rural Small Business Connection Event

    Energy.gov [DOE]

    The U.S. Department of Agriculture (USDA) will host Rural Small Business Connections, providing small businesses with networking sessions and opportunities to build capacity and do business with USDA and other Federal agencies.

  20. Rural energy - ODA`s perspective

    SciTech Connect

    Woolnough, D.

    1997-12-01

    The Overseas Development Administration has as a goal `to improve the quality of life of people in poorer countries by contributing to sustainable development and reducing poverty and suffering.` Rural energy fits into this goal as a means to an end. The emphasis is firmly on the service provided, with the aim being provision of basic needs as a part of rural development. ODA plays a role in this task on a number of fronts: research and development; support for NGO`s; aid in a bilateral or multilateral form. The view of ODA is that even rural energy projects must emphasize the service provided and must be economically sustainable. Within its sphere of influence, there is a clearly growing position for the employment of rural energy programs.

  1. Rural Productivity Zones (RPZs) for microenterprises

    SciTech Connect

    Hansen, R.D.

    1997-12-01

    In this paper the authors discuss the concept of rural productivity zones (RPZs) which are defined as a business incubator to foster income-producing opportunities for the rural poor. The essential ingredients of such a program include: electric power; business development assistance; office services; and quality work space. The electric power source must be a good quality system, consisting of a diesel/wind/photovoltaic hybrid type system, providing reliable service, with a local maintenance program and a functional load management program.

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

    SciTech Connect

    Ade, Brian J; Gauld, Ian C

    2011-10-01

    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.

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

    SciTech Connect

    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.

  4. 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

    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.

  5. Estimating pressurized water reactor decommissioning costs: A user`s manual for the PWR Cost Estimating Computer Program (CECP) software. Draft report for comment

    SciTech Connect

    Bierschbach, M.C.; Mencinsky, G.J.

    1993-10-01

    With the issuance of the Decommissioning Rule (July 27, 1988), nuclear power plant licensees are required to submit to the US Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. This user`s manual and the accompanying Cost Estimating Computer Program (CECP) software provide a cost-calculating methodology to the NRC staff that will assist them in assessing the adequacy of the licensee submittals. The CECP, designed to be used on a personnel computer, provides estimates for the cost of decommissioning PWR plant stations to the point of license termination. Such cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial costs; and manpower costs. In addition to costs, the CECP also calculates burial volumes, person-hours, crew-hours, and exposure person-hours associated with decommissioning.

  6. Butler Rural Electric Coop Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Butler Rural Electric Coop Inc Place: Ohio Website: www.butlerrural.coop Facebook: https:www.facebook.comButlerRuralElectricCooperative Outage Hotline: 800-255-2732 Outage Map:...

  7. Dubois Rural Electric Coop Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Dubois Rural Electric Coop Inc Jump to: navigation, search Name: Dubois Rural Electric Coop Inc Place: Indiana Phone Number: 812.482.5454 Website: www.duboisrec.com Facebook:...

  8. Panhandle Rural El Member Assn | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Rural El Member Assn Jump to: navigation, search Name: Panhandle Rural El Member Assn Place: Nebraska Phone Number: 308-762-1311 Website: www.prema.coop Facebook: https:...

  9. Marshall County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Marshall County Rural E M C Jump to: navigation, search Name: Marshall County Rural E M C Place: Indiana Phone Number: (866) 936-3161 Website: www.marshallremc.com Twitter:...

  10. Lagrange County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Lagrange County Rural E M C Jump to: navigation, search Name: Lagrange County Rural E M C Place: Indiana Phone Number: (877)463-7165 Website: www.lagrangeremc.com Twitter:...

  11. Newton County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Newton County Rural E M C Jump to: navigation, search Name: Newton County Rural E M C Place: Indiana Phone Number: 219.474.6224 or (219) 297-3118 Website: www.newtoncountyremc.com...

  12. Hendricks County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Hendricks County Rural E M C Jump to: navigation, search Name: Hendricks County Rural E M C Place: Indiana Phone Number: (317) 745-5473 or (800) 876-5473 Website:...

  13. Jasper County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Jasper County Rural E M C Jump to: navigation, search Name: Jasper County Rural E M C Place: Indiana Phone Number: 1-888-866-7362 or 219-866-4601 Website: www.jasperremc.com...

  14. Fulton County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Fulton County Rural E M C Jump to: navigation, search Name: Fulton County Rural E M C Place: Indiana Phone Number: 574-223-3156 or 1-800-286-2265 Website: www.fultoncountyremc.com...

  15. Decatur County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Decatur County Rural E M C Jump to: navigation, search Name: Decatur County Rural E M C Place: Indiana Phone Number: (812) 663-3391 or 800-844-7362 Website: www.dcremc.com Outage...

  16. Kankakee Valley Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Kankakee Valley Rural E M C Jump to: navigation, search Name: Kankakee Valley Rural E M C Place: Indiana Phone Number: 219.733.2511 or 800.552.2622 Website: www.kvremc.com Outage...

  17. Wabash County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Wabash County Rural E M C Jump to: navigation, search Name: Heartland Rural E M C Address: 350 Wedcor Avenue Place: Wabash, Indiana Phone Number: (260) 563-2146 Website:...

  18. Johnson County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Johnson County Rural E M C Jump to: navigation, search Name: Johnson County Rural E M C Place: Indiana Phone Number: 317.736.6174 Website: jcremc.com Facebook: https:...

  19. Jay County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Jay County Rural E M C Jump to: navigation, search Name: Jay County Rural E M C Place: Indiana Phone Number: 260-726-7121 or 1-800-TEL-REMC Website: www.jayremc.com Outage...

  20. Bartholomew County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Bartholomew County Rural E M C Jump to: navigation, search Name: Bartholomew County Rural E M C Address: 1697 W. Deaver Road Place: Columbus, Indiana Zip: 47201 Phone Number: (812)...

  1. Kosciusko County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Kosciusko County Rural E M C Jump to: navigation, search Name: Kosciusko County Rural E M C Place: Indiana Phone Number: 574.267.6331 or 1.800.790.7362 Website: kremc.com Twitter:...

  2. Clark County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    County Rural E M C Jump to: navigation, search Name: Clark County Rural E M C Place: Indiana Phone Number: (812) 246-3316 Website: www.theremc.com Facebook: https:...

  3. Henry County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    County Rural E M C Jump to: navigation, search Name: Henry County Rural E M C Place: Indiana Phone Number: 1-800-248-8413 Website: www.henrycountyremc.com Twitter:...

  4. Warren County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    County Rural E M C Jump to: navigation, search Name: Warren County Rural E M C Address: 15 Midway St Place: Williamsport, Indiana Zip: 47993 Service Territory: Indiana Phone...

  5. Hancock County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Rural E M C Jump to: navigation, search Name: Hancock County Rural E M C Place: Indiana Phone Number: (800) 248-8413 Website: www.henrycountyremc.com Twitter: @henrycountyremc...

  6. Parke County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Parke County Rural E M C Jump to: navigation, search Name: Parke County Rural E M C Place: Indiana Phone Number: 765-569-3133 or 800-537-3913 Website: www.pcremc.com Outage...

  7. Brown County Rural Elec Assn | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Rural Elec Assn Jump to: navigation, search Name: Brown County Rural Elec Assn Place: Minnesota Phone Number: 1-800-658-2368 Website: www.browncountyrea.coop Outage Hotline:...

  8. Jackson County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Jackson County Rural E M C Jump to: navigation, search Name: Jackson County Rural E M C Place: Indiana Phone Number: 1.800.288.4458 Website: www.jacksonremc.com Twitter:...

  9. Taylor County Rural E C C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Taylor County Rural E C C Jump to: navigation, search Name: Taylor County Rural E C C Place: Kentucky Phone Number: 1-800-931-4551 Website: www.tcrecc.com Outage Hotline: (800)...

  10. Morgan County Rural Elec Assn | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search Name: Morgan County Rural Elec Assn Place: Colorado Website: www.mcrea.org Twitter: @MorganCountyREA Facebook: https:www.facebook.compagesMorgan-County-Rural-Ele...

  11. T I P Rural Electric Coop | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    I P Rural Electric Coop Jump to: navigation, search Name: T I P Rural Electric Coop Abbreviation: TIPR Place: Iowa Phone Number: 641-522-9223 Website: www.tiprec.com Outage...

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

    OpenEI (Open Energy Information) [EERE & EIA]

    Rural Elec Coop, Inc Jump to: navigation, search Name: Cavalier Rural Elec Coop, Inc Place: North Dakota Phone Number: 701-256-5511 Facebook: https:www.facebook.compages...

  13. Harrison Rural Elec Assn, Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Harrison Rural Elec Assn, Inc Jump to: navigation, search Name: Harrison Rural Elec Assn, Inc Place: West Virginia Phone Number: 304.624.6365 Website: www.harrisonrea.com...

  14. Harrison County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Harrison County Rural E M C Jump to: navigation, search Name: Harrison County Rural E M C Place: Indiana Phone Number: 712-647-2727 or 800-822-5591 Website: www.hcrec.coop Outage...

  15. Howard Greeley Rural P P D | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Rural P P D Jump to: navigation, search Name: Howard Greeley Rural P P D Place: Nebraska Phone Number: 308.754.4457 Website: www.howardgreeleyrppd.com Facebook: https:...

  16. Flint Hills Rural E C A, Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Rural E C A, Inc Jump to: navigation, search Name: Flint Hills Rural E C A, Inc Place: Kansas Phone Number: 620-767-5144 Website: www.flinthillsrec.com Facebook: https:...

  17. Guthrie County Rural E C A | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Guthrie County Rural E C A Jump to: navigation, search Name: Guthrie County Rural E C A Place: Iowa Phone Number: 641.747.2206 Website: www.guthrie-rec.coop Outage Hotline:...

  18. Ninnescah Rural E C A Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Ninnescah Rural E C A Inc Jump to: navigation, search Name: Ninnescah Rural E C A Inc Place: Kansas Phone Number: (620) 672-5538 Website: www.ninnescah.com Outage Hotline: (800)...

  19. Meade County Rural E C C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    County Rural E C C Jump to: navigation, search Name: Meade County Rural E C C Place: Kentucky Phone Number: 1.877.276.5353 or Brandenburg: 270.422.2162, Hardinsburg: 270.756.5172...

  20. Linn County Rural E C A | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Linn County Rural E C A Jump to: navigation, search Name: Linn County Rural E C A Place: Iowa Phone Number: 319-377-1587 or 1-800-332-5420 Website: linncountyrec.com Outage...

  1. Cumberland Valley Rural E C C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Valley Rural E C C Jump to: navigation, search Name: Cumberland Valley Rural E C C Place: Kentucky Phone Number: 1-800-513-2677 Website: www.cumberlandvalley.coop Twitter:...

  2. West Kentucky Rural E C C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    West Kentucky Rural E C C Jump to: navigation, search Name: West Kentucky Rural E C C Place: Kentucky Phone Number: 270-247-1321 or 1-877-495-7322 Website: www.wkrecc.com Twitter:...

  3. Woodbury County Rural E C A | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    County Rural E C A Jump to: navigation, search Name: Woodbury County Rural E C A Place: Iowa Phone Number: 712.873.3125 Website: www.woodburyrec.com Outage Hotline: 1.800.469.3125...

  4. Lewis County Rural E C A | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    County Rural E C A Jump to: navigation, search Name: Lewis County Rural E C A Place: Missouri Phone Number: 573-215-4000 Website: lewiscountyrec.org Outage Hotline: 888-454-4485...

  5. 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

    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.

  6. Probability of pipe fracture in the primary coolant loop of a PWR plant. Volume 1. Summary, Load Combination Program. Project I final report

    SciTech Connect

    Lu, S.; Streit, R.D.; Chou, C.K.

    1981-06-01

    This report summarizes work performed to establish a technical basis for the NRC to use in reassessing its requirement that earthquake and large loss-of-coolant accident (LOCA) loads be combined in the design of nuclear power plants. A systematic probabilistic approach is used to treat the random nature of earthquake and transient loading and to estimate the probability of large LOCAs that are directly and indirectly induced by earthquakes. A large LOCA is defined in this report as a double-ended guillotine break of the primary reactor coolant loop piping (the hot leg, cold leg, and crossover) of a pressurized water reactor (PWR). Unit 1 of the Zion Nuclear Power Plant, a four-loop PWR, is the demonstration plant used in this study. To estimate the probability of a large LOCA directly induced by earthquakes, only fatigue crack growth resulting from the combined effects of thermal, pressure, seismic, and other cyclic loads is considered. Fatigue crack growth is simulated by a deterministic fracture mechanics model with stochastic inputs of initial crack size distribution, material properties, stress histories, and leak detection probability. Results of the simulation indicate that the probability of a double-ended guillotine break, either with or without earthquake, is very small (on the order of 10/sup -12/). The probability of a leak was found to be several orders of magnitude greater than that of a large LOCA, complete pipe rupture. A limited investigation involving engineering judgment of a double-ended guillotine break indirectly induced by an earthquake is also reported.

  7. 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

    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.

  8. Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks

    SciTech Connect

    Mueller, Don E.; Marshall, William J.; Wagner, John C.; Bowen, Douglas G.

    2015-09-01

    The U.S. Nuclear Regulatory Commission (NRC) Division of Spent Fuel Storage and Transportation recently issued Interim Staff Guidance (ISG) 8, Revision 3. This ISG provides guidance for burnup credit (BUC) analyses supporting transport and storage of PWR pressurized water reactor (PWR) fuel in casks. Revision 3 includes guidance for addressing validation of criticality (keff) calculations crediting the presence of a limited set of fission products and minor actinides (FP&MA). Based on previous work documented in NUREG/CR-7109, recommendation 4 of ISG-8, Rev. 3, includes a recommendation to use 1.5 or 3% of the FP&MA worth to conservatively cover the bias due to the specified FP&MAs. This bias is supplementary to the bias and bias uncertainty resulting from validation of keff calculations for the major actinides in SNF and does not address extension to actinides and fission products beyond those identified herein. The work described in this report involves comparison of FP&MA worths calculated using SCALE and MCNP with ENDF/B-V, -VI, and -VII based nuclear data and supports use of the 1.5% FP&MA worth bias when either SCALE or MCNP codes are used for criticality calculations, provided the other conditions of the recommendation 4 are met. The method used in this report may also be applied to demonstrate the applicability of the 1.5% FP&MA worth bias to other codes using ENDF/B V, VI or VII based nuclear data. The method involves use of the applicant s computational method to generate FP&MA worths for a reference SNF cask model using specified spent fuel compositions. The applicant s FP&MA worths are then compared to reference values provided in this report. The applicants FP&MA worths should not exceed the reference results by more than 1.5% of the reference FP&MA worths.

  9. Obama Administration's Rural Tour Stops in Western Alaska | Department of

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

    Energy Administration's Rural Tour Stops in Western Alaska Obama Administration's Rural Tour Stops in Western Alaska August 13, 2009 - 12:00am Addthis WASHINGTON D.C. - Four Cabinet Secretaries brought the Obama Administration's Rural Tour to rural Alaska today, with stops in Bethel and Hooper Bay, representing the largest Cabinet-level delegation to visit the state. Energy Secretary Steven Chu, Housing and Urban Development Secretary Shaun Donovan, Education Secretary Arne Duncan, and

  10. Rural Energy for America Program | Department of Energy

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

    Energy for America Program Rural Energy for America Program The Rural Energy for America Program (REAP) provides financial assistance to agricultural producers and rural small businesses in rural America to purchase, install, and construct renewable energy systems; to make energy efficiency improvements to non-residential buildings and facilities; to use renewable technologies that reduce energy consumption; and to participate in energy audits and renewable energy development assistance. Partner

  11. Linn County Rural Electric Cooperative - Residential Energy Efficiency...

    Energy.gov [DOE] (indexed site)

    County Rural Electric Cooperative Association Website http:www.linncountyrec.comenergy-efficiencyincentivescurrent-incent... State Iowa Program Type Rebate Program Rebate...

  12. Resources and Opportunities: 2015 Rural Utilities Study Under Way

    Energy.gov [DOE]

    Featured article in the Alaska Energy Pioneer Summer 2015 newsletter on the 2015 DOE Rural Utilities Study (RUS).

  13. Rural Development Multi-Family Housing Energy Efficiency Initiative |

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

    Department of Energy Rural Development Multi-Family Housing Energy Efficiency Initiative Rural Development Multi-Family Housing Energy Efficiency Initiative In order to help create a more energy independent rural America for the next century, the USDA Rural Development Multi-Family Housing Energy Efficiency Initiative enables applicants to several USDA housing programs to increase their program funding eligibility by incorporating green building practices into project designs, construction,

  14. Rural Communities Benefit from Wind Energy's Continued Success

    Energy.gov [DOE]

    John Stulp, Colorado Interbasin Compact Committee chairman, discusses how wind energy benefits rural communities, farms, and ranches.

  15. Comments of the National Rural Electric Cooperative Association, Request

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

    for Information Addressing Policy and Logistical Challenges to Smart Grid Implementation | Department of Energy National Rural Electric Cooperative Association, Request for Information Addressing Policy and Logistical Challenges to Smart Grid Implementation Comments of the National Rural Electric Cooperative Association, Request for Information Addressing Policy and Logistical Challenges to Smart Grid Implementation The National Rural Electric Cooperative Association (-NRECA‖) is the

  16. Tensile and Fatigue Testing and Material Hardening Model Development for 508 LAS Base Metal and 316 SS Similar Metal Weld under In-air and PWR Primary Loop Water Conditions

    SciTech Connect

    Mohanty, Subhasish; Soppet, William; Majumdar, Saurin; Natesan, Ken

    2015-09-01

    This report provides an update on an assessment of environmentally assisted fatigue for light water reactor components under extended service conditions. This report is a deliverable in September 2015 under the work package for environmentally assisted fatigue under DOE’s Light Water Reactor Sustainability program. In an April 2015 report we presented a baseline mechanistic finite element model of a two-loop pressurized water reactor (PWR) for systemlevel heat transfer analysis and subsequent thermal-mechanical stress analysis and fatigue life estimation under reactor thermal-mechanical cycles. In the present report, we provide tensile and fatigue test data for 508 low-alloy steel (LAS) base metal, 508 LAS heat-affected zone metal in 508 LAS–316 stainless steel (SS) dissimilar metal welds, and 316 SS-316 SS similar metal welds. The test was conducted under different conditions such as in air at room temperature, in air at 300 oC, and under PWR primary loop water conditions. Data are provided on materials properties related to time-independent tensile tests and time-dependent cyclic tests, such as elastic modulus, elastic and offset strain yield limit stress, and linear and nonlinear kinematic hardening model parameters. The overall objective of this report is to provide guidance to estimate tensile/fatigue hardening parameters from test data. Also, the material models and parameters reported here can directly be used in commercially available finite element codes for fatigue and ratcheting evaluation of reactor components under in-air and PWR water conditions.

  17. 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

    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

  18. 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

    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

  19. Rural development update for South Africa

    SciTech Connect

    Arent, D.

    1997-12-01

    This paper describes renewable energy programs implemented in South Africa as part of a collaborative program for rural development. Different facets of this program include: Renewable Energy for South Africa (REFSA); hybrid collaborative R&D; electricity sector restructuring; provincial level initiation of renewable energy applications; renewable energy for African development (REFAD); and Suncorp photovoltaic manufacturing company. Limited detailed information is provided on the activities of each of these different program facets over the past year in particular.

  20. Sustainable Energy Solutions for Rural Alaska

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

    Energy Solutions for Rural Alaska Disclaimer This document was prepared as an account of work sponsored by the United States Government. While this document is believed to contain correct information, neither the United States Government nor any agency thereof, nor The Regents of the University of California, nor any of their employees, makes any warranty, express or implied, or assumes any legal responsibility for the accuracy, completeness, or usefulness of any information, apparatus,

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

    SciTech Connect

    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.

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

    SciTech Connect

    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.

  3. Probability of pipe fracture in the primary coolant loop of a PWR plant. Volume 5. Probabilistic fracture mechanics analysis. Load Combination Program Project I final report

    SciTech Connect

    Harris, D.O.; Lim, E.Y.; Dedhia, D.D.

    1981-06-01

    The primary purpose of the Load Combination Program covered in this report is to estimate the probability of a seismic induced LOCA in the primary piping of a commercial pressurized water reactor (PWR). Best estimates, rather than upper bound results are desired. This was accomplished by use of a fracture mechanics model that employs a random distribution of initial cracks in the piping welds. Estimates of the probability of cracks of various sizes initially existing in the welds are combined with fracture mechanics calculations of how these cracks would grow during service. This then leads to direct estimates of the probability of failure as a function of time and location within the piping system. The influence of varying the stress history to which the piping is subjected is easily determined. Seismic events enter into the analysis through the stresses they impose on the pipes. Hence, the influence of various seismic events on the piping failure probability can be determined, thereby providing the desired information.

  4. The role of Hydrogen and Creep in Intergranular Stress Corrosion Cracking of Alloy 600 and Alloy 690 in PWR Primary Water Environments ? a Review

    SciTech Connect

    Rebak, R B; Hua, F H

    2004-07-12

    Intergranular attack (IGA) and intergranular stress corrosion cracking (IGSCC) of Alloy 600 in PWR steam generator environment has been extensively studied for over 30 years without rendering a clear understanding of the essential mechanisms. The lack of understanding of the IGSCC mechanism is due to a complex interaction of numerous variables such as microstructure, thermomechanical processing, strain rate, water chemistry and electrochemical potential. Hydrogen plays an important role in all these variables. The complexity, however, significantly hinders a clearer and more fundamental understanding of the mechanism of hydrogen in enhancing intergranular cracking via whatever mechanism. In this work, an attempt is made to review the role of hydrogen based on the current understanding of grain boundary structure and chemistry and intergranular fracture of nickel alloys, effect of hydrogen on electrochemical behavior of Alloy 600 and Alloy 690 (e.g. the passive film stability, polarization behavior and open-circuit potential) and effect of hydrogen on PWSCC behavior of Alloy 600 and Alloy 690. Mechanistic studies on the PWSCC are briefly reviewed. It is concluded that further studies on the role of hydrogen on intergranular cracking in both inert and primary side environments are needed. These studies should focus on the correlation of the results obtained at different laboratories by different methods on materials with different metallurgical and chemical parameters.

  5. New light on rural electrification: the evidence from Bolivia

    SciTech Connect

    Tendler, J.

    1980-09-01

    In 1973-74, A.I.D. financed a project to expand existing municipal electrical systems in Bolivia to seven outlying rural areas with the aim of servicing an additional 81,000 rural customers within 10 years. This report evaluates the project's impact on the rural poor in terms of three project objectives: improving the quality of life; stimulating economic production; and creating viable electric utilities.

  6. Rural Energy for America Program Loan Guarantee and Grant Program

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

    Today's Topics  Introduction  Rural Energy For America Program (REAP) Loan Guarantee and Grant program  Questions California Energy Coordinator Steven Scott Nicholls 530-792-5805 Davis, CA Regional Coordinator Regional Energy Coordinator State Distribution West Region Rob Fry Brian Buch Mid-West Region Robin Templeton Lisa Noty South Region Valarie Flanders Will Dodson Rural Energy For America Program (REAP) Eligible Applicants: 1. Agricultural producers 2. Rural small businesses 3.

  7. Loan Guarantees Can Play a Role in Rural Opportunity Investment...

    Energy.gov [DOE] (indexed site)

    Today, I moderated a panel at the White House Rural Opportunity Investment Conference ... and Nevada to California and urban areas with a high concentration of energy consumption. ...

  8. Rural Development Multi-Family Housing Energy Efficiency Initiative...

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

    incorporating green building practices into project designs, construction, and operations. ... Rural Publication Date: NA Resource Link: http:www.rurdev.usda.goveehome.html

  9. Best Practices of the Alliance for Rural Electrification: what...

    OpenEI (Open Energy Information) [EERE & EIA]

    of the Alliance for Rural Electrification: what renewable energy can achieve in developing countries Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Best Practices of...

  10. Illinois Rural Electric Cooperative Wins DOE Wind Cooperative...

    Office of Environmental Management (EM)

    The utility was cited for its leadership, demonstrated success, and innovation in its wind power program. "Illinois Rural Electric has been awarded for its innovation and ...

  11. Grayson Rural Electric Cooperative- Energy Efficiency Rebate Program

    Energy.gov [DOE]

    Grayson Rural Electric Cooperative provides rebates to its customers for increasing their energy efficiency. Members who make improvements based on recommendations by the utility's energy advisor...

  12. Missouri Rural Electric Cooperative- Residential Energy Efficiency Rebate Program

    Energy.gov [DOE]

    Missouri Rural Electric Cooperative (MREC) offers a number of rebates to residential customers for the purchase and installation of energy efficient equipment. Eligible equipment includes room air...

  13. Wind Energy for Rural Electric Cooperatives | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    cooperatives, many rural electric utilities have been initially reluctant to embrace wind energy. Reasons for this include: Some REAs in the western Great Plains have lost...

  14. Power to the people: rural electrification sector. Summary report

    SciTech Connect

    Wasserman, G.; Davenport, A.

    1983-12-01

    Results of studies of the impact of rural electrification (RE) programs in Bolivia, Costa Rica, Ecuador, and the Philippines are summarized.

  15. Tipmont Rural Elec Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

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

  16. The Other 15%: Expanding Energy Efficiency to Rural Populations

    Energy.gov [DOE]

    Better Buildings Residential Network Peer Exchange Call Series: The Other 15%: Expanding Energy Efficiency to Rural Populations, call slides and discussion summary.

  17. Illinois Institute for Rural Affairs | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    include rural economic and community development (including value-added agriculture), health care, education, public transportation, public management policies, housing, and...

  18. Promotion of Rural Renewable Energy in Western China | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Energy in Western China Place: Beijing Municipality, China Zip: 100026 Sector: Bioenergy Product: A programme launched by China Association of Rural Energy Industry (CAREI)...

  19. German Club for Rural Electrification CLE | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Electrification CLE Jump to: navigation, search Name: German Club for Rural Electrification (CLE) Place: Freiburg, Germany Zip: 79114 Sector: Renewable Energy Product: German...

  20. Community-Driven Development Decision Tools for Rural Development...

    OpenEI (Open Energy Information) [EERE & EIA]

    (CDD) investment programmes as a way to further enabling rural poor people to overcome poverty in WCA." References "Community-Driven Development Decision Tools" Retrieved from...

  1. Ghana-NREL Rural Electrification | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    electrification project in Ghana in cooperation with UNDP and GEF. NREL also piloted a business model for providing energy services in rural areas of Ghana.1 References ...

  2. The Other 15%: Expanding Energy Efficiency to Rural Populations

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

    Other 15%: Expanding Energy Efficiency to Rural Populations September 10, 2015 Call Slides and Discussion Summary Agenda Call Logistics and Opening Poll Residential Network ...

  3. Illinois Rural Electric Cooperative Wind Farm | Open Energy Informatio...

    OpenEI (Open Energy Information) [EERE & EIA]

    Electric Cooperative Energy Purchaser Illinois Rural Electric Cooperative Location Pike County IL Coordinates 39.6189, -90.9627 Show Map Loading map......

  4. Policy Flash 2014-27 Implementation of Division D, Titles III and V, and Division E, Title VII of the Consolidated Appropriations Act, 2014,Pub. L. No. 113-76. (AL) 2014-04 and (FAL) 2014-01 revised

    Energy.gov [DOE]

    SUMMARY: Acquisition Letter (AL) 2014-04 and Financial Assistance Letter (FAL) 2014-01 have been revised to remove language from Section 502 that was not carried forward from previous appropriation acts. FAL 2014-01was also revised to update the Corporate Felony Conviction and Federal Tax Liability Representations and Assurances and the Conference Spending term. As a result, AL 2014-04 (Rev 1) and FAL 2014-01 (Rev 1) provide implementing instructions and guidance for Division D, Titles III and V, and Division E, Title VII of the Consolidated Appropriations Act, 2014, Pub. L. No. 113-76.

  5. (Rural electrification: Grid extension, decentralization, and financing)

    SciTech Connect

    Perlack, R.D.

    1990-02-22

    H.G. (Mike) Jones and I had numerous meetings with EEGSA staff. We discussed rural electrification plans, reviewed documents, and collaborated on collecting information on decentralized energy alternatives. Meetings were also held with USAID/Guatemala, USAID/ROCAP, NRECA, MEM, PVOs, and equipment vendors. A preliminary draft report and spreadsheet for comparing decentralized power alternatives was completed. The report and findings were presented to EEGSA and the methodology transferred to EEGSA staff. A set of recommended followup activities was also presented to EEGSA.

  6. Incubating Innovation for Rural Electrification. Executive Summary

    SciTech Connect

    2013-07-01

    In June, the team held a workshop on ''Low Carbon Sustainable Rural Electrification'' in Salima, Malawi. Co-organized with the Government of Malawi's Department of Energy, this event gathered participants from the energy, telecom, non-profit, banking sectors as well as from governmental and international agencies to discuss the potential development of private led off-grid electrification in Malawi where only 9% of the population has currently access to electricity. A very active participation provided us with insightful feedback and valuable recommendations.

  7. Renewable energy and rural development activities experience in Bangladesh

    SciTech Connect

    Barua, D.C.

    1997-12-01

    The per capita per year fuel consumption in Bangladesh is only 56 kg oil equivalent. The supply of electricity by Bangladesh power development board (BPDB) and Dhaka electricity supply authority (DESA) is mainly confined to cities and towns. Rural Electrification Board (REB) distributes electricity to the rural people through cooperatives. The rural cooperatives cover only 10% of the total population. Only about 15% of the total population is directly connected to the electricity. In order to meet the increasing energy demand for development of agriculture and industry and for the generation of better employment opportunities, it will be necessary to harness all the available alternative sources of energy immediately.

  8. Buckeye Rural Elec Coop, Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Buckeye Rural Elec Coop, Inc Place: Ohio Website: www.buckeyerec.commain Facebook: https:www.facebook.combuckeyerec Outage Hotline: 1-800-282-7204 References: EIA Form EIA-861...

  9. Big Horn Rural Electric Co | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    307-568-2419 Website: www.bighornrea.com Facebook: https:www.facebook.compagesBig-Horn-Rural-Electric Outage Hotline: 1-800-564-2419 References: EIA Form EIA-861 Final...

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

    OpenEI (Open Energy Information) [EERE & EIA]

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

  11. Okefenoke Rural El Member Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

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

  12. Electric Cooperatives Channel Solar Resources to Rural American Communities

    Energy.gov [DOE]

    Some of the most remote areas in the United States were also some of the last places to get access to electricity, with as many as nine out of ten rural homes without electricity in the mid-1930s....

  13. White County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    White County Rural E M C Address: 302 North Sixth Street Place: Monticello, IN Zip: 47960 Service Territory: Indiana Phone Number: (574) 583-7161 Website: www.cwremc.com Facebook:...

  14. Chile-NREL Rural Electrification Activities | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    early 2000 and was inaugurated by President Lagos in October of that year and the San Pedro and the small rural school of Aqua Fresca, all to demonstrate the use of wind...

  15. Steuben County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Steuben County Rural E M C Address: 1212 S. Wayne Street Place: Angola, Indiana Zip: 46703 Phone Number: 260.665.3563 Website: www.remcsteuben.com Twitter: @steubencoremc...

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

    OpenEI (Open Energy Information) [EERE & EIA]

    Raft River Rural Elec Coop Inc Place: Idaho Service Territory: Idaho, Utah, Nevada Phone Number: 208-645-2211 Website: rrelectric.com Facebook: https:www.facebook.compages...

  17. QER- Comment of National Rural Electric Cooperative Association 2

    Energy.gov [DOE]

    Please find attached additional comments from the National Rural Electric Cooperative Association (NRECA). Thank you for the opportunity to participate. If you have questions or need additional information, please do not hesitate to contact me.

  18. Resources and Opportunities: 2015 Rural Utilities Study Under...

    Energy Saver

    The Shugnak power plant is one of nearly 30 rural utilities the RUS team is visiting in 2015. Photo from Alaska Center for Energy and Power, NREL 33697. The Shugnak power plant is ...

  19. Butler Rural El Coop Assn, Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Coop Assn, Inc Jump to: navigation, search Name: Butler Rural El Coop Assn, Inc Place: Kansas Phone Number: 316.321.9600 Website: www.butler.coop Facebook: https:...

  20. Orange County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    search Name: Orange County Rural E M C Place: Indiana Phone Number: 1-812-865-2229 Toll Free: 1-888-337-5900 Website: www.orangecountyremc.org Facebook: https:www.facebook.com...

  1. Valley Rural Electric Coop Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Valley Rural Electric Coop Inc Place: Pennsylvania Phone Number: 814643-2650 or toll-free 800432-0680 Website: www.valleyrec.com Facebook: https:www.facebook.compages...

  2. Fact #759: December 24, 2012 Rural vs. Urban Driving Differences

    Energy.gov [DOE]

    According to the National Household Travel Survey, those living in rural areas drive ten more miles in a day than those who live in cities. People living in the suburbs drive only about three to...

  3. USDA Offers Renewable Energy Feasibility Studies for Rural Businesses

    Energy.gov [DOE]

    The U.S. Department of Agriculture (USDA) announced on September 7 the availability of grants of up to $50,000 for agricultural producers and rural small businesses to conduct feasibility studies for installing renewable energy systems.

  4. Northwestern Rural E C A, Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    E C A, Inc Jump to: navigation, search Name: Northwestern Rural E C A, Inc Place: Pennsylvania Phone Number: 1-800-474-1710 Website: www.northwesternrec.com Twitter: @NWRECA...

  5. White House Rural Council: Creating New Business Opportunities | Department

    Energy.gov [DOE] (indexed site)

    of Energy Senior Advisor Henry Kelly Senior Advisor Henry Kelly Senior Advisor Last Thursday, on behalf of Secretary Chu, I attended the first meeting of the White House Rural Council. The Council, established by President Obama's Executive Order on Thursday, provides a new mechanism to ensure that our work creating new business opportunities and jobs in rural America is well-coordinated between agencies and that no important opportunity is missed. The Energy Department has many programs

  6. Kansas wind program stimulates rural economy | Department of Energy

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

    Kansas wind program stimulates rural economy Kansas wind program stimulates rural economy December 9, 2009 - 11:38am Addthis Joshua DeLung What will the project do? Students in the Wind for Schools program gain not only practical knowledge in wind turbine technologies, but also they get hands-on experience installing turbines statewide. During an economic downturn, it's always a struggle for recent college graduates to find jobs and a place to put down roots amid a tightening workforce.

  7. Smart Meter Investments Support Rural Economy in Arkansas

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

    Smart Meter Investments Support Rural Economy in Arkansas Woodruff Electric Cooperative (Woodruff) serves customers in seven eastern Arkansas counties. The proportion of residents living in poverty in those counties is more than double the national average. As a member-owned rural electric cooperative, Woodruff is connected to its customers and engaged in economic development efforts to bring more jobs and higher incomes to local communities. In order to bring the capital investment and its

  8. The Gut Microbiota of Rural Papua New Guineans: Composition, Diversity

    Office of Scientific and Technical Information (OSTI)

    Patterns, and Ecological Processes (Journal Article) | DOE PAGES The Gut Microbiota of Rural Papua New Guineans: Composition, Diversity Patterns, and Ecological Processes Title: The Gut Microbiota of Rural Papua New Guineans: Composition, Diversity Patterns, and Ecological Processes Comparisons between the fecal microbiota of humans from industrialized and non-industrialized communities indicate a pronounced impact of westernization on the diversity and composition of the human gut

  9. USDA Rural Development: Sustaining Relationships in Indian Country

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

    Sustaining Relationships in Indian Country USDA Rural Development Organizational Structure National Office State Directors Program Directors Specialists Architects Engineers Technicians Area Directors Native American Coordinators General Field Representatives Rur al Utilities Ser vice Rur al Housing & Community Facilities Rur al Business Cooper ative Ser vice Rural Development Program Areas Progr am Areas Business & Industr y Guar anteed Loans Rur al Business Enter pr ise Gr ants Rur al

  10. Final_report_pub1.pdf

    SciTech Connect

    O'Brien, Nicholas

    2014-08-15

    The paper describes Soitecs project to plan,install,qualify and ramp a high volume CPV module manufactruing facility in Southern California. Soitec’s CPV module factory in San Diego was planned with an annual production capacity of 280MWDC. It was scheduled to be operational by the first quarter of 2013, and was expected to create several hundred direct and indirect jobs in the San Diego region. From ground breaking to facility readiness was completed in six months. This enabled the docking of equipment in the Q3’12 time frame. The first 140 MW of capacity was ready for operation in Q4’12. Production of the CX-M500 modules started in Q4 2012. The line yield and factory capacity were ramped in 2013. The annual production capacity demonstration was successfully completed in Q2 2014. The modules manufactured at the plant were used to supply utility scale demand in the US and also world markets.

  11. Newsletter Feb draft 012512_V3.pub

    Office of Environmental Management (EM)

    On the same cycle, the SPR Maintenance Department tracks the fuel used, the cost, and mileage or ... drains energy when not in use (i.e. cell phone chargers, fans, coffeemakers, ...

  12. FERMILAB-PUB-15-596-CD

    Office of Scientific and Technical Information (OSTI)

    17 May 2015 Comprehensive Monitoring for Heterogeneous Geographically Distributed Storage. ... For comprehensive tracking and monitoring of the storage utilization across all ...

  13. Index of /datasets/files/961/pub

    OpenEI (Open Energy Information) [EERE & EIA]

    ARCHIVE 02-Jul-2013 09:51 - COMMERCIALLOADDATAEPLUSOUTPUT.part1.tar.gz 03-Nov-2013 13:09 386M COMMERCIALLOADDATAEPLUSOUTPUT.part2.tar.gz 03-Nov-2013 13:12 386M ...

  14. 2011 October Center Directory.pub

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

    Watt Way, VHE 309 ningfenh@usc.edu 213-740-0713 Gisele Ragusa, PhD, MS Department of Psychology in Education 3470 Trousdale Parkway, WPH 401 Los Angeles, Ca, 90089 ragusa@usc.edu...

  15. Request Form for Purchases_CAMD.pub

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

    Johnston, Sr. Center for Advanced Microstructures and Devices (CAMD) Louisiana State University, 6980 Jefferson Highway, Baton Rouge, LA 70806 Office 225/578-8884 Fax 225/578-6954 REQUEST FORM FOR PURCHASES Purchaser's Name: ___________________________________________________ Purchaser's Phone Number: ____________________________________________ Purchaser's Initials/Supervisor's Initials: __________________________________ Vendor Name: _________________________________________________________

  16. IG-0739 Report Cover.pub

    Energy.gov [DOE] (indexed site)

    the schedule to cleanup waste tanks at the Hanford Site and included 72 ... to retrieve waste from 22 single-shell tanks and for interim closure of eight tanks by ...

  17. Index of /datasets/files/41/pub

    OpenEI (Open Energy Information) [EERE & EIA]

    PUBID82185 22-May-2012 00:11 - DIR PUBID82188 22-May-2012 00:11 - DIR PUBID82189 22-May-2012 00:11 - DIR PUBID82190 22-May-2012 00:11 - DIR PUBID82191...

  18. Newsletter July draft 070312 v2.pub

    Office of Environmental Management (EM)

    For more informa on, visit h p:go.usa.govvYZ. DOE Sustainability SPOtlight U.S. ... The app converts Green Bu on energy data into the number of trees required to offset pollu ...

  19. SCANNED Version of SIF.pub

    Energy.gov [DOE] (indexed site)

    ......... 8 2. Objective, Scope, and Methodology ......Fund share the same goal, at a strategic level, and thus, use generic scope of work. ...

  20. Newsletter Nov draft 110211pm.pub

    Energy.gov [DOE] (indexed site)

    2011 DOE Sustainability Awards DOE presented the first annual DOE Sustainability Awards on November 3rd. The awards recognize teams and individuals at DOE sites and field offices ...

  1. Index of /datasets/files/39/pub

    OpenEI (Open Energy Information) [EERE & EIA]

    a file-level view of datasets. Go back to Datasets Listing About us Disclaimers Energy blogs Linked Data Developer services OpenEI partners with a broad range of international...

  2. SLAC-PUB-15076 The Higgs Sector

    Office of Scientific and Technical Information (OSTI)

    Distribution of the lightest CP-even Higgs mass for the neutralino (blue) and gravitino (red) LSP pMSSM model sets, highlighting the m h 125 2 GeV region. 5 Neutralino LSP...

  3. BABAR-PUB-14/006 Study

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

    + followed by D 0 K - + (and the charge-conjugate process). The ratios of the efficien- cies between data and MC samples are used to scale the misidentified muon component...

  4. 2001 IG Report WEB Ver..pub

    Office of Environmental Management (EM)

    ... access only) web server operating at the Department's Sandia National Laboratory (Sandia), Albuquerque, New Mexico, and defaced the web page replacing it with obscene statements. ...

  5. Scanned version of Rpt4.pub

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

    University of California's Costs Claimed and Related Internal Controls for Operation of Los Alamos National Laboratory DOE/IG-0596 April 2003 Los Alamos Costs and Controls Background ................................................................................ 1 Results of Audit .......................................................................... 1 Recommendations and Comments .......................................... 11 Appendices 1. Objective, Scope, and Methodology

  6. MICROBOONE-NOTE-1006-PUB Study Towards

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

    ... In terms of the big picture the steps are as follows: 1. ... possible in an event. 2. Search for events that produce ... Nearly half of the 0 s enter the TPC through a neutron. 4 ...

  7. MICROBOONE-NOTE-1005-PUB May

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

    of cosmic rays are expected to enter the detector volume. ... L is the absorption length in terms of atmospheric density ... on the MicroBooNE elec- tromagnetic excess search. ...

  8. WR-B-02-03.pub

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

    02-03 AUDIT REPORT U.S. DEPARTMENT OF ENERGY OFFICE OF INSPECTOR GENERAL OFFICE OF AUDIT SERVICES SANDIA NATIONAL LABORATORIES PROCUREMENT CARD PROGRAM AUGUST 2002 MEMORANDUM FOR: ASSOCIATE DIRECTOR FOR MANAGEMENT AND ADMINISTRATION FROM: Lawrence R. Ackerly, Director (Signed) National Nuclear Security Administration Audit Division SUBJECT: INFORMATION: Audit Report on "Sandia National Laboratories Procurement Card Program" BACKGROUND Sandia National Laboratories' Procurement Card

  9. PWR FLECHT SEASET 21-rod-bundle flow-blockage task: data and analysis report. NRC/EPRI/Westinghouse report No. 11, main report and appendices A-J

    SciTech Connect

    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.

  10. Biogas as a source of rural energy

    SciTech Connect

    Kalia, A.K.

    2000-01-01

    The hilly state of Himachal Pradesh, with nearly 2.15 million cattle and 0.7 million buffalo, has the potential to install 0.64 million biogas plants of 1 m{sup 3} size. These plants could generate nearly 4.90 x 105 m{sup 3} of biogas, equivalent to 3.07 x 10{sup 5} L kerosene per day to meet domestic energy needs of nearly one-fourth of its rural population. During 1982--1998, only 12.8% of this potential was achieved. The percent of possible potential achieved in plant installations in 12 districts of this state, namely, Bilaspur, Chamba, Hamirpur, Kangra, Kinnaur, Kullu, Lahul-Spiti, Mandi, Shimla, Sirmour, Solan, and Una, are 35.35, 1.70, 20.96, 8.67, 1.54, 6.96, 0.00, 18.49, 3.84, 8.521, 18.29, and 13.23%, respectively. There is a need to strengthen biogas promotion, particularly in the districts of Kangra, Mandi, Solan, and Una, which range from mid-hill to low-hill terrain and which have large potential due to high concentration of bovine population. Increased costs and comparatively low rate of subsidies has resulted in a decreasing rate of plant installation annually, from 3,500 during 1987--1992 to fewer than 1,200 during 1995--1998. The percentage of functioning plants was 82% in 1987--1988 but has decreased to 63%. To ensure proper installation and functionality of plants, the authors discuss the needed improvements in the biogas promotion program.

  11. Strategies for Adapting to Climate Change in Rural Sub-Saharan...

    OpenEI (Open Energy Information) [EERE & EIA]

    for Adapting to Climate Change in Rural Sub-Saharan Africa Jump to: navigation, search Name Strategies for Adapting to Climate Change in Rural Sub-Saharan Africa AgencyCompany...

  12. D S & O Rural E C A, Inc | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    & O Rural E C A, Inc Jump to: navigation, search Name: D S & O Rural E C A, Inc Place: Kansas Phone Number: 785-655-2011 Website: dsoelectric.com Twitter: @DSOElectricCoop Outage...

  13. Building America Whole-House Solutions for New Homes: Rural Development,

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

    Inc., Greenfield, Massachusetts | Department of Energy Rural Development, Inc., Greenfield, Massachusetts Building America Whole-House Solutions for New Homes: Rural Development, Inc., Greenfield, Massachusetts Case study of Rural Development Inc. who worked with Building America research partner CARB to design affordable HERS-8 homes (60 w/o PV), with double-stud walls heavy insulation, low-load sealed-combustion gas space heaters, triple-pane windows, solar water heating, and PV. Rural

  14. Bolivia: rural electrification. Project impact evaluation report No. 16

    SciTech Connect

    Butler, E.; Poe, K.M.; Tendler, J.

    1980-12-01

    Two rural electrification systems initiated in Bolivia in 1973 and 1974 are the subject of this report. By 1979, all distribution networks were completed, except in the La Paz region. Power was supplied to 42,000 consumers and was used primarily for residential lighting. Although demand outpaced supply, consumption per household was lower than projected, and irrigation and industrial use was negligible. The preponderant positive impact of the projects was social. Household lighting improved the physical quality of life for 7% of Bolivia's rural population.

  15. Buckland Students Explore Ways to Address Rural Alaska Energy Challenges |

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

    Department of Energy Buckland Students Explore Ways to Address Rural Alaska Energy Challenges Buckland Students Explore Ways to Address Rural Alaska Energy Challenges May 23, 2016 - 6:03pm Addthis Students pose in front of Buckland’s 10.53-kW solar system used to power the village’s new water plant. Photo from Alison Jech, Buckland School. Students pose in front of Buckland's 10.53-kW solar system used to power the village's new water plant. Photo from Alison Jech, Buckland School.

  16. User-owned utility models for rural electrification

    SciTech Connect

    Waddle, D.

    1997-12-01

    The author discusses the history of rural electric cooperatives (REC) in the United States, and the broader question of whether such organizations can serve as a model for rural electrification in other countries. The author points out the features of such cooperatives which have given them stability and strength, and emphasizes that for success of such programs, many of these same features must be present. He definitely feels the cooperative models are not outdated, but they need strong local support, and a governmental structure which is supportive, and in particular not negative.

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

    OpenEI (Open Energy Information) [EERE & EIA]

    Steuben Rural Elec Coop, Inc Place: New York Phone Number: 607-776-4161 or 800-843-3414 or 716-296-5651 or 800-883-8236 Website: www.steubenrec.coop Outage Hotline: 1-866-430-4293...

  18. Energy Department Announces Technical Assistance for Self-Sufficiency and Lower Energy Costs for Rural Alaska Communities, and Releases “Sustainable Energy Solutions for Rural Alaska” Report

    Energy.gov [DOE]

    The Energy Department has announced 13 recipients of Remote Alaska Communities Energy Efficiency (RACEE) technical assistance, and released its “Sustainable Energy Solutions for Rural Alaska” report.

  19. Human alteration of the rural landscape: Variations in visual perception

    SciTech Connect

    Cloquell-Ballester, Vicente-Agustin Carmen Torres-Sibille, Ana del; Cloquell-Ballester, Victor-Andres; Santamarina-Siurana, Maria Cristina

    2012-01-15

    The objective of this investigation is to evaluate how visual perception varies as the rural landscape is altered by human interventions of varying character. An experiment is carried out using Semantic Differential Analysis to analyse the effect of the character and the type of the intervention on perception. Interventions are divided into elements of 'permanent industrial character', 'elements of permanent rural character' and 'elements of temporary character', and these categories are sub-divided into smaller groups according to the type of development. To increase the reliability of the results, the Intraclass Correlation Coefficient tool, is applied to validate the semantic space of the perceptual responses and to determine the number of subjects required for a reliable evaluation of the scenes.

  20. Indonesia solar home systems project for rural electrification

    SciTech Connect

    Sanghvi, A.P.

    1997-12-01

    This paper presents, from a financing aspect the broad issues involved in a plan to provide solar home systems (SHS) to provide rural electrification in several areas of rural Indonesia. The paper discusses the approaches being used to provide funding, develop awareness of the technology, and assure the success of the project. The plan involves the use of grant money to help with some of the initial costs of such systems, and thereby to encourage local financing on a terms rather than cash basis. There are needs for market development, and development of a business structure in the country to support this type of technology. Provided this plan can succeed, it may serve as a model for further efforts.

  1. FROM: Keith Dennis, National Rural Electric Cooperative Association (NRECA

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

    TO: Ex parte communications, U.S. Department of Energy FROM: Keith Dennis, National Rural Electric Cooperative Association (NRECA DATE: September 6, 2013 RE: NRECA's Ex Parte Communication with DOE on June 11, 2013 Teleconference summary Attendees: John Cymbalsky - DOE Jay Morrison - NRECA Keith Dennis - NRECA Julie Barkemeyer - NRECA Issues Discussed: The attendees identified above met via teleconference on July 10, 2013, to discuss DOE's proposed rulemaking to allow waivers from energy

  2. OPTIMIZATION OF LONG RURAL FEEDERS USING A GENETIC ALGORITHM

    SciTech Connect

    Wishart, Michael; Ledwich, Gerard; Ghosh, Arindam; Ivanovich, Grujica

    2010-06-15

    This paper describes the optimization of conductor size and the voltage regulator location and magnitude of long rural distribution lines. The optimization minimizes the lifetime cost of the lines, including capital costs and losses while observing voltage drop and operational constraints using a Genetic Algorithm (GA). The GA optimization is applied to a real Single Wire Earth Return (SWER) network in regional Queensland and results are presented.

  3. USDA Seeks Applications for Grants to Assist Rural Communities with Extremely High Energy Costs

    Energy.gov [DOE]

    Applications are due July 30, 2012, for USDA Rural Development grants to assist communities where expenditures for home energy exceed 275% of the national average.

  4. Fact #902: December 7, 2015 Rural versus Urban Vehicle Miles of Travel by

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

    State | Department of Energy 2: December 7, 2015 Rural versus Urban Vehicle Miles of Travel by State Fact #902: December 7, 2015 Rural versus Urban Vehicle Miles of Travel by State SUBSCRIBE to the Fact of the Week In the United States, the U.S. Department of Transportation classifies 3.9 million miles of roadway as rural and 1.2 million miles of roadway as urban. Each state has a different travel pattern affecting the proportion of vehicle miles traveled (VMT) on rural versus urban roads.

  5. Building America Whole-House Solutions for New Homes: Rural Developmen...

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

    Development, Inc., Greenfield, Massachusetts Case study of Rural Development Inc. who worked with Building America research partner CARB to design affordable HERS-8 homes (60 ...

  6. USDA- Rural Energy for America Program (REAP) Energy Audit and Renewable Energy Development Assistance (EA/REDA) Program

    Energy.gov [DOE]

    Note: The U.S. Department of Agriculture's Rural Development periodically issues Notices of Solicitation of Applications for the Rural Energy for America Program (REAP) in the Federal Register. The...

  7. Ecuador rural electrification. Project impact evaluation report 21

    SciTech Connect

    Kessler, J.L.; Ballantyne, J.; Maushammer, R.; Simancas, N.R.

    1981-01-01

    The direct and indirect benefits of rural electrification in Ecuador warrant A.I.D.'s continued sponsorship of such programs. This assessment of A.I.D.'s 1964-75 sponsorship of four electrification projects in Ecuador concludes that, although implemented along with other development projects such as road construction, the program was a key factor in upgrading the towns of Santa Elena, Santo Domingo de los Colorados, Daule, and Ambato into regional market and service centers. The main benefits of this program, which was not originally designed to benefit the poor, were job creation, access to agricultural product processing facilities, and increased opportunities for small commercial enterprises.

  8. Mid-term evaluation of the NRECA (National Rural Electric Cooperative Association) Central America Rural Electrification Support Program (CARES)

    SciTech Connect

    Perlack, R.D. ); Jones, H.G. ); Garcia, A. III . Dept. of Agricultural Engineering); Flores, E. , Guatemala City )

    1990-09-01

    Oak Ridge National Laboratory was requested by the Regional Office for Central America and Panama to conduct a mid-term evaluation of the Cares Project, which is being implemented by the National Rural Electric Cooperative Association. This evaluation was conducted over a three week period by a four person team. Overall, the project has had numerous successes and is highly valued by local counterpart utilities and USAID Missions. Notwithstanding the significant results of the project, changes can be made in certain operating procedures and in the direction of some programmatic activities that can lead to an even more effective project.

  9. Oil, power, and rural change in Ecuador: 1972-1979

    SciTech Connect

    Zevallos, J.V.

    1985-01-01

    This study explores the role of the State in Ecuador's agriculture during the period of oil boom and military rule (1972-1979). It focuses on: (1) how the availability of oil revenues affected formation and implementation of agricultural policies; (2) the impact of oil-financed policies on agrarian structure, agricultural production, and rural inequality. Historical analysis is based on interviews with policy makers, newspaper chronology, and government documents. Policy impact assessment is based on macroeconomic evidence and microlevel studies. Although agrarian reform was central to the military's development plan, the 1973 Agrarian Reform Law imposed no farm size limits and postponed enforcement of efficiency requirements until 1976. Oil revenues eliminated some political and economic incentives for reform. State action shifted away from land redistribution towards colonization and promotion of agricultural production. The oil boom had an overall negative impact on rural income distribution. It removed incentives for reform. Increased state spending benefitted primarily medium and large landowners. Macroeconomic trends favored adoption of capital intensive methods in livestock and industrial crop production and decapitalization of food and export agriculture, harming wage-dependent laborers.

  10. Sustainable fuelwood use in rural Mexico. Volume 1: Current patterns of resource use

    SciTech Connect

    Masera, O.

    1993-04-01

    The present report summarizes the results of the first phase of a project of cooperation between the Mexican National Commission for Energy Conservation (CONAE) and the United States Environmental Protection Agency (U.S. EPA) on sustainable biofuel use in rural Mexico. This first phase has been devoted to (i) conducting an in-depth review of the status of fuelwood use in rural and peri-urban areas of Mexico, (ii) providing improved estimates of biomass energy use, (iii) assessing the socioeconomic and environmental impacts of fuelwood use, and (iv) identifying preliminary potential lines of action to improve the patterns of biomass energy use in Mexico; in particular, identifying those interventions that, by improving living conditions for rural inhabitants, can result in global benefits (such as the reduction in greenhouse gas emissions). A comprehensive review of the existing documentation of biofuel use in rural and peri-urban Mexico was conducted. Reports from official, academic, and non-governmental organizations were gathered and analyzed. A computerized rural energy database was created by re-processing a national rural energy survey. Because of the paucity of information about biofuel use in small rural industries, most of the analysis is devoted to the household sector.

  11. Fact #902: December 7, 2015 Rural versus Urban Vehicle Miles of Travel by

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

    State - Dataset | Department of Energy 2: December 7, 2015 Rural versus Urban Vehicle Miles of Travel by State - Dataset Fact #902: December 7, 2015 Rural versus Urban Vehicle Miles of Travel by State - Dataset Excel file and dataset for Rural versus Urban Vehicle Miles of Travel by State fotw#902_web.xlsx (177.48 KB) More Documents & Publications Fact #904: December 21, 2015 Gross Domestic Product and Vehicle Travel: Both Increased during 2015 - Dataset Fact #906: January 4, 2016 VMT

  12. Table HC7-8a. Home Office Equipment by Urban/Rural Location,

    Energy Information Administration (EIA) (indexed site)

    8a. Home Office Equipment by Urban/Rural Location, Million U.S. Households, 2001 Home Office Equipment RSE Column Factor: Total Urban/Rural Location 1 RSE Row Factors City Town Suburbs Rural 0.5 0.9 1.3 1.2 1.4 Total .............................................................. 107.0 49.9 18.0 21.2 17.9 4.1 Households Using Office Equipment ......................................... 96.2 43.9 16.0 20.2 16.1 4.1 Personal Computers 2 ................................. 60.0 25.6 9.3 15.0 10.1 4.7

  13. Milepost locations in rural emergency response : the missing piece.

    SciTech Connect

    Armstrong, Hillary Minich

    2004-06-01

    An incident location must be translated into an address that responders can find on the ground. In populated areas it's street name and address number. For sparsely populated areas or highways it's typically road name and nearest milepost number. This is paired with road intersection information to help responders approach the incident as quickly and safely as possible. If responders are new to the area, or for cross-country response, more assistance is needed. If dispatchers had mileposts as points on their maps they could provide this assistance as well as vital information to public safety authorities as the incident unfolds. Mileposts are already universally understood and used. The missing rural response piece is to get milepost locations onto dispatch and control center screens.

  14. Economic evaluation of rural woodlots in a developing country: Tanzania

    SciTech Connect

    Kihiyo, V.B.M.S.

    1996-03-01

    Rural areas in developing countries use wood as their main source of energy. Previously, wood has been obtained free from natural forests and woodlands. The pressure of increased demand through population growth, and the fact that natural trees take longer to grow, has made this resource scarce. Thus, raising trees in woodlots has been adopted as the solution to its shortage in the wild. However, growing trees in woodlots will inevitably require resources in terms of capital, land and manpower. Economic evaluation becomes necessary to ascertain that these resources are used economically. This paper dwells on some of the salient features of the economic evaluation of woodlots, such as interest rates, shadow prices of factors of production, social opportunity, cost of capital and sensitivity analysis of such woodlots in a developing country such as Tanzania. 19 refs., 5 tabs.

  15. Builders Challenge High Performance Builder Spotlight - Rural Development Inc., Turner Falls, Massachusetts

    SciTech Connect

    2008-01-01

    Building America/Builders Challenge fact sheet on Rural Development Inc, an energy-efficient home builder in cold climate using radiant floor heat, solar hot water, and PV. Examines cost impacts.

  16. Laying the Foundation for a More Energy-Secure Future in Rural...

    Energy.gov [DOE] (indexed site)

    to seek follow-on support through DOE technical assistance, funding, and other related future opportunities. In rural Alaska, energy is just one of a host of challenges Native...

  17. Building America Whole-House Solutions for New Homes: Rural Developmen...

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

    homes (60 wo PV), with double-stud walls heavy insulation, low-load sealed-combustion gas space heaters, triple-pane windows, solar water heating, and PV. PDF icon Rural ...

  18. Energy Department and USDA Partner to Support Energy Efficiency in Rural Communities

    Energy.gov [DOE]

    Partnering with USDA, the Energy Department has created the State Energy Extension Partnership to equip America’s farm families and rural small businesses with the efficiency tools, resources and training needed to reduce energy costs.

  19. Miami-Cass County Rural E M C | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Name: Miami-Cass County Rural E M C Place: Indiana Phone Number: 765-473-6668 or toll free 800-844-6668 Website: www.mcremc.coop Twitter: @MiamiCassREMC Outage Hotline:...

  20. Rural areas electrification (Latin America), Guatemala City, Guatemala, June 4--7, 1989: Foreign trip report

    SciTech Connect

    Katzman, M.T.

    1989-01-01

    ORNL serves the function of monitoring the Central American Rural Electrification Support Program (CARES) of US Agency for International Development (USAID), which is administered by NRECA. The results of the Demand Assessment Model, presented at the conference, were reviewed, and a paper on the use of marginal cost analysis for rural electrification was delivered for presentation by NRECA staff. Discussions on the acceptability of the model were discussed with utility representatives.

  1. Rural Alaska Community Action Program Inc.'s Energy Wise Program

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

    Rural Alaska Community Action Program, Inc. Ellen Kazary, Community Development Manager (907) 865-7358, ekazary@ruralcap.com GOALS: * Create jobs for rural Alaskans * Lower residential energy burden in tribal communities Additional Goals - Demonstrate that education and simple efficiency improvements can make an important difference in lowering residential energy costs - Provide a model component for energy plans - important to incorporate Energy Wise strategies in holistic energy plans Energy

  2. LOFT lead rod test results evaluation. [PWR

    SciTech Connect

    Driskell, W.B.; Tolman, E.L.

    1980-07-30

    The purpose for evaluating the LOFT Lead Rod Test (simulations of large break, loss-of-coolant accidents) data was to determine; (a) if the centerline thermocouple and fuel rod elongation sensor data show indications of the collapsed fuel rod cladding, (b) the capability of the FRAP-T5 computer code to accurately predict cladding collapse, and (c) if cladding surface thermocouples enhance fuel rod cooling. With consideration to unresolved questions on data integrity, it was concluded that: the fuel rod centerline thermocouple and elongation sensor data do show indications of the fuel rod cladding collapse; the FRAP-T5 code conservatively predicts cladding collapse; and there is an indication that cladding surface thermocouples are enhancing fuel rod cooling.

  3. Fuel performance during severe accidents. [PWR

    SciTech Connect

    Buescher, B.J.; Gruen, G.E.; MacDonald, P.E.

    1982-01-01

    As a result of the Three Mile Island Unit-2 (TMI-2) accident, the Nuclear Regulatory Commission has initiated a severe fuel damage test program to evaluate fuel rod and core response during severe accidents similar to TMI-2. This program is underway in the Power Burst Facility at the Idaho National Engineering Laboratory. In preparation for the first test, predictions have been performed using the TRAC-BD1 computer. This paper presents the calculated results showing a slow heatup to 2400 K over 5 hours, and the analysis includes accelerated oxidation of the zirconium cladding at temperatures above 1850 K.

  4. Cracked-fuel mechanics. [PWR; BWR

    SciTech Connect

    Williford, R.E.; Lanning, D.D.

    1982-01-01

    This paper presents a modelling concept and a set of measurable parameters that have been shown to improve the prediction of the mechanical behavior of cracked fuel/cladding systems without added computational expense. The transition from classical annular gap/cylindrical pellet models to modified bulk properties and further to local behavior for cracked fuel systems is discussed. The results of laboratory experiments to verify these modelling parameters are shown. Data are also presented from laboratory experiments on unirradiated and irradiated rods which show that fuel rod mechanical response depends on fuel fragment size. The impact of these data on cracked fuel behavior and failure modelling is also discussed.

  5. PWR fuel performance program. Final report

    SciTech Connect

    Kunishi, H.; Miller, R.S.; Roberts, E.

    1985-09-01

    Tests of 15 x 15 and 17 x 17 fuel assemblies, irradiated at burnup levels well beyond the standard 33 GWd/MtU, showed that no inherent material limitations stand in the way of such assemblies achieving average burnups of approximately 55 GWd/MtU. The study also showed that cladding waterside corrosion can be minimized by controlling the lithium-to-boron ratio in the coolant to reduce crud deposition.

  6. Transport of lead in PWR secondary cycles

    SciTech Connect

    Sawochka, S.G.; Clouse, M.E.; Miller, M.R. )

    1991-04-01

    Since lead can accelerate IGA/IGSCC of Alloy 600 steam generator tubing, lead transport studies were performed at several pressurized water reactors to establish a basis for recommendations regarding transport reduction techniques. Special emphasis was given to sampling and analysis procedures since lead concentrations in the feedwater generally were very low, i.e., 5 to 20 parts per trillion. Lead sources were determined to be highly distributed in the secondary cycle, e.g., turbine and pump bearings and seals and valve packing materials. The major materials of construction (carbon steel, stainless steel, and copper alloy tubing) were not major lead sources in the study plants. Most of the lead that entered the steam generators via the feedwater deposited on the tubes or in the sludge pile leading to concentrations in the range of 1000 ppM. The ubiquitous nature of the lead release phenomenon is expected to lead to significant difficulties in identifying techniques for reducing lead concentrations in the steam generator sludge. 8 refs., 19 figs., 13 tabs.

  7. US PWR steam generator management: An overview

    SciTech Connect

    Welty, C.S. Jr.

    1997-02-01

    This paper provides an overview on the status of steam generator management activities in US PWRs, and includes: (1) an overview of the impact of steam generator problems; (2) a brief discussion of historical damage trends and the current damage mechanism of most concern; (3) a discussion of the elements of {open_quotes}steam generator management{close_quotes}; and (4) a description of the approach being followed to implement a degradation-specific protocol for tubing inspection and repair. This paper was prepared in conjunction with another paper presented during the Plenary Session of this Conference, {open_quotes}Steam Generator Degradation: Current Mitigation Strategies for Controlling Corrosion{close_quotes}, and is provided as a supplement to that material.

  8. Consolidation and disposal of PWR fuel inserts

    SciTech Connect

    Wakeman, B.H. (Virginia Electric and Power Co., Glen Allen, VA (United States))

    1992-08-01

    Design and licensing of the Surry Power Station Independent Spent Fuel Storage Installation was initiated in 1982 by Virginia Power as part of a comprehensive strategy to increase spent fuel storage capacity at the Station. Designed to use large, metal dry storage casks, the Surry Installation will accommodate 84 such casks with a total storage capacity of 811 MTU of spent pressurized water reactor fuel assemblies. Virginia Power provided three storage casks for testing at the Idaho National Engineerinq Laboratory's Test Area North and the testing results have been published by the Electric Power Research Institute. Sixty-nine spent fuel assemblies were transported in truck casks from the Surry Power Station to Test Area North for testing in the three casks. Because of restrictions imposed by the cask testing equipment at Test Area North, the irradiated insert components stored in these fuel assemblies at Surry were removed prior to transport of the fuel assemblies. Retaining these insert components proved to be a problem because of a shortage of spent fuel assemblies in the spent fuel storage pool that did not already contain insert components. In 1987 Virginia Power contracted with Chem-Nuclear Systems, Inc. to process and dispose of 136 irradiated insert components consisting of 125 burnable poison rod assemblies, 10 thimble plugging devices and 1 part-length rod cluster control assembly. This work was completed in August and September 1987, culminating in the disposal at the Barnwell, SC low-level radioactive waste facility of two CNS 3-55 liners containing the consolidated insert components.

  9. Best-Estimate Analysis PWR LOCA.

    Energy Science and Technology Software Center

    2005-11-11

    Version: 00 TRAC‑PF1 performs best estimate analyses of loss of coolant accidents and other transients in pressurized light water reactors. The program can also be used to model a wide range of thermal hydraulic experiments in reduced scale facilities. Models employed include reflood, multi‑dimensional two‑phase flow, nonequilibrium thermodynamics, generalized heat transfer, and reactor kinetics. Automatic steady‑state and dump/restart capabilities are provided. The changes reported in TRACNEWS issues through Number 7 are incorporated in this release.more » TRAC-PF1 was developed on a CDC computer at Los Alamos National Laboratory. The PC version of TRAC‑PF1 was converted at CNEN in 1989 and has not been updated since that time. The NRC no longer supports the TRAC codes. They currently develop and maintain the TRACE code system, which is the TRAC/RELAP Advanced Computational Engine. TRACE is a modernized thermal-hydraulics code designed to consolidate the capabilities of NRC's 3 legacy safety codes - TRAC-P, TRAC-B and RELAP. This is NRC's flagship thermal-hydraulics analysis tool. See the website for more information http://www.nrccodes.com/.« less

  10. Stress corrosion cracking of Alloy 600. [PWR

    SciTech Connect

    Serra, E.

    1981-11-01

    The stress corrosion cracking of Alloy 600 tubing has affected the performance of several pressurized water reactor steam generators. The purpose of this report is to summarize the research which has followed that reviewed by D. van Rooyen in 1975. Although several papers and reports have been published there still is not a general model that can explain the stress corrosion cracking behavior of Alloy 600 in deaerated or aerated high-temperature pure water or in the environments that might exist in the primary and secondary coolant of a steam generator. Such a model, if it exists, must cover the complex interaction of the environmental, metallurgical, and mechanical variables which control the susceptibility of Alloy 600 to stress corrosion cracking. Each of these classes of variables is discussed in the text.

  11. (Monitoring and evaluation of the Central American Rural Electrification Program)

    SciTech Connect

    Garcia, A. III )

    1990-03-20

    CARES has been successful in leveraging its effort with similar programs in other countries. NRECA has done an exceptional job of coordinating the related activities of other AID contracts. The informal lines of communication appear to work well with a relaxed and productive environment evident. ROCAP has expressed confidence in the ability of NRECA to carry out the Workplan successfully. Recent initiatives by Mr. Funes in the area of indicators are seen by the review team as a positive and mutual step to articulate specific goals and accomplishments. Communication and coordination among the ROCAP staff and the local AID Mission appears to have improved since last mentioned in the Engineering Standards Review. This is especially true in Guatemala and Costa Rica. Better reporting procedures would facilitate NRECA-ROCAP-AID Mission communication. Impressive progress has been made in the way local officials approach rural electrification. This is very evident in the areas of engineering design and the productive uses campaign. The Planning and Engineering sections of INDE and CEL rapidly adopted the new mechanical strength based standards as reasonable design solutions. Similarly, productive uses has received much greater attention by all of the various divisions of the utilities in El Salvador, Guatemala and Costa Rica. This was not the case previous to the CARES Project. The final report specifically addresses several areas that should be de-emphasized or given more attention. 26 refs.

  12. Opportunities and Challenges for Solar Minigrid Development in Rural India

    SciTech Connect

    Thirumurthy, N.; Harrington, L.; Martin, D.; Thomas, L.; Takpa, J.; Gergan, R.

    2012-09-01

    The goal of this report is to inform investors about the potential of solar minigrid technologies to serve India's rural market. Under the US-India Energy Dialogue, the US Department of Energy's (DOE) National Renewable Energy Laboratory (NREL) is supporting the Indian Ministry of New and Renewable Energy (MNRE)'s Jawaharlal Nehru National Solar Mission (JNNSM) in performing a business-case and policy-oriented analysis on the deployment of solar minigrids in India. The JNNSM scheme targets the development of 2GW of off-grid solar power by 2022 and provides large subsidies to meet this target. NREL worked with electricity capacity and demand data supplied by the Ladakh Renewable Energy Development Agency (LREDA) from Leh District, to develop a technical approach for solar minigrid development. Based on the NREL-developed, simulated solar insolation data for the city of Leh, a 250-kW solar photovoltaic (PV) system can produce 427,737 kWh over a 12-month period. The business case analysis, based on several different scenarios and JNNSM incentives shows the cost of power ranges from Rs. 6.3/kWh (US$0.126) to Rs. 9/kWh (US$0.18). At these rates, solar power is a cheaper alternative to diesel. An assessment of the macro-environment elements--including political, economic, environmental, social, and technological--was also performed to identify factors that may impact India?s energy development initiatives.

  13. Biomass District Heat System for Interior Rural Alaska Villages

    SciTech Connect

    Wall, William A.; Parker, Charles R.

    2014-09-01

    Alaska Village Initiatives (AVI) from the outset of the project had a goal of developing an integrated village approach to biomass in Rural Alaskan villages. A successful biomass project had to be ecologically, socially/culturally and economically viable and sustainable. Although many agencies were supportive of biomass programs in villages none had the capacity to deal effectively with developing all of the tools necessary to build a complete integrated program. AVI had a sharp learning curve as well. By the end of the project with all the completed tasks, AVI developed the tools and understanding to connect all of the dots of an integrated village based program. These included initially developing a feasibility model that created the capacity to optimize a biomass system in a village. AVI intent was to develop all aspects or components of a fully integrated biomass program for a village. This meant understand the forest resource and developing a sustainable harvest system that included the “right sized” harvest equipment for the scale of the project. Developing a training program for harvesting and managing the forest for regeneration. Making sure the type, quality, and delivery system matched the needs of the type of boiler or boilers to be installed. AVI intended for each biomass program to be of the scale that would create jobs and a sustainable business.

  14. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    in reduced variable costs unless increases in fuel costs exceed the savings from efficiency gains. In addition to considerations of levelized costs 11, some technologies...

  15. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    Electricity use per household declines from 2012 to 2040 in the Reference case Continuing efficiency gains restrain growth in residential electricity use Extending tax credits...

  16. MIT Plasma Science & Fusion Center: research, alcator, pubs,...

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

    pm Executive SessionDiscussions with C-Mod team as desired * Priorities Marmar * 8 Tesla Wolfe 7:00 pm PAC Dinner (if desired) Wednesday, February 25, 2004 8:00 am Executive...

  17. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    Refining & processing Stocks All reports Browse by Tag Alphabetical Frequency Tag Cloud Proposed Natural Gas Liquids Realignment EIA has reviewed the approaches and...

  18. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    ... The U.S. Department of Energy is required by law to investigate whether updated standards are technologically feasible and economically justified and to work with stakeholders to ...

  19. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    period. Among the most uncertain aspects of this analysis are the potential effects of alternative resource and technology assumptions on the global market for liquid fuels,...

  20. Northern Indiana Pub Serv Co | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    797,092 2,502 135 1,398 1 96,260 1,329,444 455,645 2008-04 23,474 220,184 399,632 29,709 320,619 53,732 42,089 800,788 2,503 146 1,507 1 95,418 1,343,098 455,868 2008-03 26,217...

  1. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    from 3.4 MMbbld in 2012 to 4.3 MMbbld in 2040, primarily for use in HDVs. Both ethanol blending into gasoline and E85 consumption are essentially flat throughout the...

  2. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    ... a class of nonutility generators called Qualifying Facilities permitted to produce power for resale. W. Barber, "More nuclear power plant retirements forecast," Electric Light and ...

  3. Analysis & Projections - Pub - U.S. Energy Information Administration...

    Energy Information Administration (EIA) (indexed site)

    Summary of meeting Transportation modeling plans presentation Second AEO2013 Meeting (October 15, 2012) Summary of meeting Transportation modeling plans presentation Contacts: John ...

  4. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    tables Appendix D Results from side cases tables Appendix E NEMS overview and brief description of cases Appendix F: Regional Maps United States Census Divisions Electricity...

  5. Analysis & Projections - Pub - U.S. Energy Information Administration...

    Annual Energy Outlook

    Summary of meeting Presentation Future Operating and Maintenance Considerations for the ... Presentation 2: Future Operating and Maintenance Considerations for Existing Coal-Fired ...

  6. FY 2007 Fee Adequacy, Pub 2008 | Department of Energy

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

    the fee will provide sufficient revenues to offset the commercial utilities' share of the total life cycle costs of the Civilian Radioactive Waste Management Program (the Program). ...

  7. Newsletter 8th draft one pager.pub

    Energy.gov [DOE] (indexed site)

    data center energy expenses by 10% to 40% 1 by reducing physical servers, floor space, hea ngcooling, and manpower. Every DOE site has implemented virtualiza on, including big ...

  8. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    methanol, ethanol, compressed natural gas (CNG), liquefied natural gas (LNG), and hydrogen-in the transportation sector, subject to delivered energy prices, macroeconomic...

  9. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    economic growth projections in AEO2015 with actual growth rates over the past 30 years. ... 2040-a rate that is 0.4 percentage points slower than the average over the past 30 years. ...

  10. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    Trends in economic activity Growth in business fixed investment offsets slow growth in labor force Growth in the output of the U.S. economy depends on increases in the labor force,...

  11. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    (Figure MT-4). The AEO2014 price cases included varying assumptions about: (1) investment and production decisions by the Organization of the Petroleum Exporting Countries...

  12. Analysis & Projections - Pub - U.S. Energy Information Administration...

    Energy Information Administration (EIA) (indexed site)

    Oil and Natural Gas AEO2016 Meetings First AEO2016 Meeting (December 15, 2015) Summary of meeting Oil and Gas presentation AEO2015 Meetings First AEO2015 Meeting (August 7, 2014) ...

  13. Analysis & Projections - Pub - U.S. Energy Information Administration...

    Energy Information Administration (EIA) (indexed site)

    Liquid Fuels Markets AEO2016 Meetings First AEO2016 Meeting (November 19, 2015) Summary of meeting Presentation Second AEO2016 Meeting (February 24, 2016) Summary of meeting ...

  14. Analysis & Projections - Pub - U.S. Energy Information Administration...

    Energy Information Administration (EIA) (indexed site)

    Renewables AEO2016 Meetings First AEO2016 Meeting (December 23, 2015) Summary of meeting Presentation Second AEO2016 Meeting (February 9, 2016) Presentation AEO2015 Meetings First ...

  15. Analysis & Projections - Pub - U.S. Energy Information Administration...

    Energy Information Administration (EIA) (indexed site)

    Electricity AEO2016 Meetings First AEO2016 Meeting (December 8, 2015) Summary of meeting Presentation Second AEO2016 Meeting (February 10, 2016) Summary of meeting Presentation ...

  16. U.S. Energy Information Administration (EIA) - Pub

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

    required by both the Clean Air Interstate Rule (CAIR)29 and the Cross-State Air Pollution Rule (CSAPR).30,31 Total electricity generation increases by 24% from 2013 to ...

  17. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    by 26% over the period. More use of distributed generation, such as from rooftop solar panels, would further reduce delivered energy intensity, but it is not projected to...

  18. April2002SAR Revised Final 6-3-02.pub

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

    4 October 1, 2001 - March 31, 2002 Office of Inspector General Office of Inspector General The Inspector General's Message - Page 1 The Department's Management Challenges Page 2...

  19. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    from IHSGI, as well as others that concentrate on economic growth, international oil prices, energy consumption, electricity, natural gas, petroleum, and coal, are...

  20. Central Vermont Pub Serv Corp | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Outage Hotline: 1 (888) 835-4672 Outage Map: wss.greenmountainpower.comcus Green Button Access: Planned Green Button Reference Page: www.efficiencyvermont.com...

  1. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    Coal Western coal supply shows largest decline among regions with Clean Power Plan in effect In the AEO2016 Reference case, total coal production decreases from 873 million short tons (MMst) in 2015 to 827 MMst in 2022 when the Clean Power Plan (CPP) takes effect, and to 643 MMst in 2040. The CPP affects coal supply differently in the West, Interior, and Appalachia regions because of differences in coal quality and markets served (Figure MT-58). Compared with the No CPP case, the West region

  2. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    Trends in economic activity With lower labor productivity growth, investment is key to improving living standards Growth in labor productivity is an important determinant of economic growth [1]. Since the end of the latest U.S. recession in June 2009 [2], labor productivity has been slow to recover. From 1987-2014, U.S. labor productivity growth averaged 1.9%/ year [3]. The average rate of growth in the previous expansion (2001-07) was 2.6%, compared with 1.3%/year in the current expansion

  3. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    Emissions Energy-related carbon dioxide emissions projections depend on assumptions about economic growth, energy prices, resource availability, and policies The AEO2016 Reference case assumes that current laws and regulations remain in effect through 2040. However, the status of the Clean Power Plan (CPP), which is on hold pending judicial review, is uncertain. The Reference case assumes implementation of the CPP as scheduled and uses mass-based standards that impose limits on carbon dioxide

  4. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    Industrial sector energy demand Industrial shipments grow more rapidly than energy consumption In the AEO2016 Reference case, manufacturing shipments increase by more than 60% from 2015-40, while delivered energy consumption for heat and power in the manufacturing sector increases by 16%. The continued decline in energy intensity of manufacturing results in part from continued improvement in the efficiency of industrial equipment, as well as a shift in the share of shipments from

  5. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    International Energy Range of oil price cases represents uncertainty in world oil markets In AEO2016, the North Sea Brent crude oil price is the main benchmark for world oil prices. Three oil price cases-Reference, High Oil Price, and Low Oil Price-examine the potential effects of alternative price paths on energy markets (Figure MT-4). In the Low Oil Price case, global demand for liquids is assumed to be relatively low, and supply is relatively high; in the High Oil Price case demand is high

  6. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    transportation, and economic activity. However, the structure and efficiency of the U.S. economy are changing in ways that can lower energy use. Changes in consumer behavior can...

  7. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    levels in 2016, as the need for electricity generators to comply with Mercury and Air Toxic Standards (MATS) leads to a wave of coal-fired capacity retirements. From 2016 to...

  8. http://pubs.usgs.gov/wri/wri034090/

    National Nuclear Security Administration (NNSA)

    ... Snowfall, sublimation, and snowmelt were modeled as functions of the spatially distributed daily climate input and the simulated solar radiation component of the potential ...

  9. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    of Energy, U.S. Energy Information Administration. 6. U.S. Department of Energy, Office of Energy Efficiency and Renewable Energy, Residential Lighting End-Use Consumption...

  10. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    for EIA's Annual Energy Outlook"-the U.S. Energy Information Administration (EIA) evaluated a range of trends and issues that could have major implications for U.S. energy markets. ...

  11. Index of /datasets/files/39/pub/documentation

    OpenEI (Open Energy Information) [EERE & EIA]

    11:05 103K NSRDBStationsMetaMeta.doc 18-Apr-2012 11:05 35K NSRDB data dictionary(Solar only).doc 18-Apr-2012 11:05 98K NSRDBusermanual.pdf 18-Apr-2012 11:05 14M...

  12. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    Delivered energy consumption by sector Transportation Energy consumption in the transportation sector declines in the AEO2015 Reference case from 27.0 quadrillion Btu (13.8 million ...

  13. U.S. Energy Information Administration (EIA) - Pub

    Gasoline and Diesel Fuel Update

    Prices Crude oil AEO2015 considers a number of factors related to the uncertainty of future world crude oil prices, including changes in worldwide demand for petroleum products, ...

  14. Cal. Pub. Res. Code 6009 | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Code 6009Legal Abstract Statutory section containing general provisions for administration and control of state lands in California. Published NA Year Signed or Took Effect...

  15. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    on a generalized economic evaluation and do not reflect a specific evaluation or knowledge of decisions on pending LNG export applications. figure data In the High Oil and Gas...

  16. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    consumption grows by 0.7%year despite 1.0% annual growth in commercial floorspace. Natural gas consumption also increases over the period despite increases in building...

  17. EA-283_Pub_Svs_of_CO___CN.pdf

    Energy Saver

  18. Impact of oil in the tropical marine environment. Technical pub

    SciTech Connect

    Cintron, G.; Lugo, A.E.; Martinez, R.; Cintron, B.B.; Encarnacion, L.

    1981-11-01

    Oil spills have a devastating effect on biologically rich coastal environments. This report investigates this problem, covering damage by oil to biological systems, the use of dispersants (toxicity and considerations for dispersant use), impact of oil and dispersants on coral reefs, impact of oil on seagrass beds and sandy beaches, impact of oil on mangroves (seedling survival and tolerance, regeneration, forest type vulnerability, and cleanup and recovery activities in mangroves), conclusions, and recommendations. The study concludes that coral reefs and seagrass beds may escape significant spill damage if pollution is not chronic and if dispersants are not used. Sandy and rocky shores may be severely impacted but recover quickly. Mangroves are the most vulnerable coastal ecosystem. Recommendations are that oil spill contingency plans must be prepared for all areas, and that the necessary equipment for the plans must be in place.

  19. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    Increasing energy efficiency reduces the energy intensity of many residential end uses between 2013 and 2040. Total energy consumption for space heating is 4.2 quadrillion Btu in ...

  20. U.S. Energy Information Administration (EIA) - Pub

    Annual Energy Outlook

    used for any particular scenario. The AEO2014 Reference case projection is a business-as-usual trend estimate, given known technology and technological and demographic...