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Sample records for valley rrl pwr

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

    Open Energy Information (Open El) [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...

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

    Open Energy Information (Open El) [EERE & EIA]

    Elec Assn Jump to: navigation, search Name: Red River Valley Rrl Elec Assn Place: Oklahoma Phone Number: 1-800-749-3364 or 580-564-1800 Website: www.rrvrea.com Twitter:...

  3. Maquoketa Valley Rrl Elec Coop | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Place: Iowa Phone Number: 319-462-3542 or 800-927-6068 Website: mvec.com Twitter: @mvecia Facebook: https:www.facebook.comMaquoketaValleyElectricCooperative Outage Hotline:...

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

    Open Energy Information (Open El) [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:...

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

    Open Energy Information (Open El) [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...

  6. Harrison County Rrl Elec Coop | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Harrison County Rrl Elec Coop Jump to: navigation, search Name: Harrison County Rrl Elec Coop Place: Iowa Phone Number: 712-647-2727 Website: www.hcrec.coop Outage Hotline:...

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

    Open Energy Information (Open El) [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...

  8. Keosauqua Municipal Light & Pwr | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

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

  9. 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 ...

  10. PWR AXIAL BURNUP PROFILE ANALYSIS

    SciTech Connect (OSTI)

    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).

  11. 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, ...

  12. Northeast Missouri El Pwr Coop | Open Energy Information

    Open Energy Information (Open El) [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...

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

    Open Energy Information (Open El) [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...

  14. Sam Rayburn Municipal Pwr Agny | Open Energy Information

    Open Energy Information (Open El) [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...

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

    Open Energy Information (Open El) [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...

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

    SciTech Connect (OSTI)

    Ocken, H.; Knott, S.

    1981-03-01

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

  17. South Mississippi El Pwr Assn | Open Energy Information

    Open Energy Information (Open El) [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...

  18. East Mississippi Elec Pwr Assn | Open Energy Information

    Open Energy Information (Open El) [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 --...

  19. 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)...

  20. 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 ...

  1. West Valley Demonstration Project | Department of Energy

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

    West Valley Demonstration Project West Valley Demonstration Project West Valley Demonstration Project Aerial View West Valley Demonstration Project Aerial View The West Valley ...

  2. 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...

  3. PWR representative behavior during a LOCA

    SciTech Connect (OSTI)

    Allison, C.M.

    1981-01-01

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

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

    SciTech Connect (OSTI)

    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.

  5. 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; ...

  6. Melton Valley Watershed

    Energy.gov [DOE]

    This document explains the cleanup activities and any use limitations for the land surrounding the Melton Valley Watershed.

  7. Swing-Down of 21-PWR Waste Package

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  9. ANTELOPE VALLEY SOLAR RANCH | Department of Energy

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

    ANTELOPE VALLEY SOLAR RANCH ANTELOPE VALLEY SOLAR RANCH ANTELOPE VALLEY SOLAR RANCH ANTELOPE VALLEY SOLAR RANCH ANTELOPE VALLEY SOLAR RANCH ANTELOPE VALLEY SOLAR RANCH ANTELOPE VALLEY SOLAR RANCH ANTELOPE VALLEY SOLAR RANCH ANTELOPE VALLEY SOLAR RANCH ANTELOPE VALLEY SOLAR RANCH ANTELOPE VALLEY SOLAR RANCH PROJECT SUMMARY In September 2011, the Department of Energy issued a $646 million loan guarantee to finance Antelope Valley Solar Ranch 1, a 242-MW photovoltaic (PV) solar generation project.

  10. CALIFORNIA VALLEY SOLAR RANCH | Department of Energy

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

    CALIFORNIA VALLEY SOLAR RANCH CALIFORNIA VALLEY SOLAR RANCH CALIFORNIA VALLEY SOLAR RANCH CALIFORNIA VALLEY SOLAR RANCH CALIFORNIA VALLEY SOLAR RANCH CALIFORNIA VALLEY SOLAR RANCH CALIFORNIA VALLEY SOLAR RANCH CALIFORNIA VALLEY SOLAR RANCH CALIFORNIA VALLEY SOLAR RANCH CALIFORNIA VALLEY SOLAR RANCH CALIFORNIA VALLEY SOLAR RANCH PROJECT SUMMARY In September 2011, the Department of Energy issued a $1.2 billion loan guarantee to finance California Valley Solar Ranch, a 250-MW photovoltaic (PV)

  11. Categorical Exclusion Determinations: West Valley Demonstration...

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

    Valley Demonstration Project Categorical Exclusion Determinations: West Valley Demonstration Project Categorical Exclusion Determinations issued by West Valley Demonstration ...

  12. Analysis of PWR RCS Injection Strategy During Severe Accident

    SciTech Connect (OSTI)

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

    2004-05-15

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

  13. Robotic inspection of PWR coolant pump casing welds

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

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

    1983-01-01

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

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

    SciTech Connect (OSTI)

    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.

  16. Surprise Valley water geochmical data

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

    Nicolas Spycher

    2015-04-13

    Chemical analyses of thermal and cold ground waters from Surprise Valley, compiled from publicly available sources.

  17. Surprise Valley water geochmical data

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

    Nicolas Spycher

    Chemical analyses of thermal and cold ground waters from Surprise Valley, compiled from publicly available sources.

  18. Union Valley | Department of Energy

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

    Union Valley Union Valley This document discusses Union Valley. Topics include: * The area's safety * Any use limitations for the area * History and cleanup background for this area * How DOE's cleanup program addressed the problem Union Valley (809.31 KB) More Documents & Publications Melton Valley Watershed Groundwater Contamination and Treatment at Department of Energy Sites Groundwater Contamination and Treatment at Department of Energy Sites - 2008

  19. NV PFA - Steptoe Valley

    SciTech Connect (OSTI)

    Jim Faulds

    2015-10-29

    All datasets and products specific to the Steptoe Valley model area. Includes a packed ArcMap project (.mpk), individually zipped shapefiles, and a file geodatabase for the northern Steptoe Valley area; a GeoSoft Oasis montaj project containing GM-SYS 2D gravity profiles along the trace of our seismic reflection lines; a 3D model in EarthVision; spreadsheet of links to published maps; and spreadsheets of well data.

  20. All Valley Solar | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley Solar Jump to: navigation, search Logo: All Valley Solar Name: All Valley Solar Address: 6851 Cahuenga Park Trail Place: Los Angeles, California Region: Southern CA Area...

  1. Bolton Valley Resort | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Bolton Valley Resort Jump to: navigation, search Name Bolton Valley Resort Facility Bolton Valley Resort Sector Wind energy Facility Type Small Scale Wind Facility Status In...

  2. Hyder Valley Aquaculture Low Temperature Geothermal Facility...

    Open Energy Information (Open El) [EERE & EIA]

    Valley Aquaculture Low Temperature Geothermal Facility Jump to: navigation, search Name Hyder Valley Aquaculture Low Temperature Geothermal Facility Facility Hyder Valley Sector...

  3. Site Programs & Cooperative Agreements: West Valley Demonstration...

    Office of Environmental Management (EM)

    West Valley Demonstration Project Site Programs & Cooperative Agreements: West Valley Demonstration Project West Valley Demonstration Project The Seneca Nation of Indians has ...

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

    SciTech Connect (OSTI)

    2013-11-01

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

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

    Energy Science and Technology Software Center (OSTI)

    2013-11-01

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

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

    SciTech Connect (OSTI)

    J.M. Scaglione

    2004-12-17

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

  7. Comparison of PWR-IMF and FR fuel cycles

    SciTech Connect (OSTI)

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

    2007-07-01

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

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

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

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

  9. Scotts Valley Band of Pomo Indians: Scotts Valley Energy Office...

    Energy.gov (indexed) [DOE]

    ... The goal of this project is to develop a Scotts Valley Energy Development Office (SVEDO). Scotts Valley Energy Office and Human Capacity Project SUMMARY Two Key Elements of SVEDO ...

  10. Blue Valley Energy | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    References: Blue Valley Energy Web Site1 On Jan 1st 2008, Valley Geothermal and Blue Sky Energy Solutions merged to form Blue Valley Energy LLC. Valley Geothermal, led by Monte...

  11. Independent Oversight Review, West Valley Demonstration Project...

    Office of Environmental Management (EM)

    West Valley Demonstration Project Transportation - September 2000 Independent Oversight Review, West Valley Demonstration Project Transportation - September 2000 September 2000 ...

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

    SciTech Connect (OSTI)

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

    1982-12-01

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

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

    SciTech Connect (OSTI)

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

    1988-01-01

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

  14. 21-PWR Waste Package Side and End Impacts

    SciTech Connect (OSTI)

    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.

  15. 21-PWR Waste Package Side and End Impacts

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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)

  17. VERA Core Simulator Methodology for PWR Cycle Depletion

    SciTech Connect (OSTI)

    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.

  18. AMF Deployment, Ganges Valley, India

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

    India Ganges Valley Deployment AMF Home Ganges Valley Home Data Plots and Baseline Instruments Campaign Images Experiment Planning GVAX Full Proposal Abstract and Related Campaigns Science Plan Field Campaign Report Outreach GVAX Backgrounder (PDF, 1.4MB) News Education Flyer (PDF, 2.1MB) AMF Poster, 2011 Images Contacts V. Rao Kotamarthi AMF Deployment, Ganges Valley, India GVAX will take place in the Ganges Valley region of India, gathering cloud and aerosol data. Location: 29° 21'

  19. Elk Valley Rancheria- 2010 Project

    Energy.gov [DOE]

    Elk Valley Rancheria will perform a comprehensive Energy Efficiency and Alternatives Study for tribal properties on the Rancheria.

  20. Bethel Valley Watershed | Department of Energy

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

    Bethel Valley Watershed Bethel Valley Watershed This document discusses the Bethel Valley Watershed. Topics include: * The area's safety * Any use limitations for the area * History and cleanup background for this area * How DOE's cleanup program addressed the problem Bethel Valley Watershed (377.2 KB) More Documents & Publications Bear Creek Valley Watershed Oak Ridge National Laboratory Cleanup Melton Valley Watershed

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

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

    1983-01-01

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

  3. 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 ...

  4. 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 ...

  5. PWR and BWR spent fuel assembly gamma spectra measurements

    DOE PAGES-Beta [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

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

    SciTech Connect (OSTI)

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

    2002-07-01

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

  7. Ganges Valley Aerosol Experiment

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

    Ganges Valley Aerosol Experiment In northeastern India, the fertile land around the Ganges River supports several hundred million people. This river, the largest in India, is fed by monsoon rains and runoff from the nearby Himalayan Mountains. Through an intergovernmental agreement with India, the U.S. Department of Energy's Atmospheric Radiation Measurement (ARM) Climate Research Facility deployed its portable laboratory, the ARM Mobile Facility (AMF), to Nainital, India, in June 2011. During

  8. MONUMENT VALLEY, ARIZONA

    Office of Legacy Management (LM)

    VALLEY, ARIZONA Sampled August 1997 DATA PACKAGE CONTENTS This data package includes the following information: Item No. Descriotion of Contents 1. Site Sampling Lead Summary 2. Data Package Assessment, which includes the following: a. Field procedures verification checklist b. Confirmation that chain-of-custody was maintained. c. Confirmation that holding time requirements were met. d. Evaluation of the adequacy of the QC sample results. Data Assessment Summary, which describes problems

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

    SciTech Connect (OSTI)

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

    1992-03-01

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

  10. Case Study - Sioux Valley Energy

    Energy.gov (indexed) [DOE]

    This detailed billing cannot be done with conventional meters. Critical Peak Pricing Lowers Peak Demands and Electric Bills in South Dakota and Minnesota Sioux Valley Energy (SVE) ...

  11. Pennsylvania Nuclear Profile - Beaver Valley

    U.S. Energy Information Administration (EIA) (indexed site)

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

  12. Valley Forge Corporate Center

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

    55 Jefferson Ave. Valley Forge Corporate Center Norristown, PA 19403-2497 Pauline Foley Assistant General Counsel 610.666.8248 | Fax - 610.666.8211 foleyp@pjm.com October 30, 2013 Via Electronic Mail: juliea.smith@hq.doe.gov Christopher.lawrence@hq.doe.gov Julie A. Smith Office of Electricity Delivery and Energy Reliability Mail Code: OE-20 U.S. Department of Energy 1000 Independence Avenue, SW Washington, D.C. 20585 Re: Department of Energy - Improving Performance of Federal Permitting and

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

    SciTech Connect (OSTI)

    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

  14. Great Valley Ethanol LLC | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley Ethanol LLC Jump to: navigation, search Name: Great Valley Ethanol LLC Place: Bakersfield, California Product: Developing a 63m gallon ethanol plant in Hanford, CA...

  15. Platte Valley Fuel Ethanol | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley Fuel Ethanol Jump to: navigation, search Name: Platte Valley Fuel Ethanol Place: Central City, Nebraska Product: Bioethanol producer using corn as feedstock References:...

  16. Dixie Valley Geothermal Area | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Dixie Valley Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Dixie Valley Geothermal Area Contents 1 Area Overview 2 History and Infrastructure 2.1...

  17. Chuckawalla Valley State Prison | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Chuckawalla Valley State Prison Jump to: navigation, search Name: Chuckawalla Valley State Prison Place: Blythe, California Zip: 92226 Sector: Solar Product: Prison located in...

  18. Dakota Valley Wind Project | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search Name Dakota Valley Wind Project Facility Dakota Valley Sector Wind energy Facility Type Community Wind Location SD Coordinates 42.548355, -96.524841...

  19. Smoky Valley Wind Project | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search Name Smoky Valley Wind Project Facility Smoky Valley Sector Wind energy Facility Type Community Wind Location KS Coordinates 38.578766, -97.683563...

  20. Tippecanoe Valley School Corp | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

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

  1. River Valley Technology Center | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley Technology Center Jump to: navigation, search Name: River Valley Technology Center Place: United States Sector: Services Product: General Financial & Legal Services (...

  2. Thanksgiving Goodwill: West Valley Demonstration Project Food...

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

    Thanksgiving Goodwill: West Valley Demonstration Project Food Drive Provides 640 Turkeys to People in Need Thanksgiving Goodwill: West Valley Demonstration Project Food Drive...

  3. Anderson Valley Brewing Company | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley Brewing Company Jump to: navigation, search Name: Anderson Valley Brewing Company Place: Mendocino Country, California Product: A microbrewery. The brewery is known for...

  4. Tees Valley Biofuels | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Tees Valley Biofuels Jump to: navigation, search Name: Tees Valley Biofuels Place: United Kingdom Sector: Biofuels Product: Company set up by North East Biofuels to establish an...

  5. Independent Activity Report, West Valley Demonstration Project...

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

    West Valley Demonstration Project - July 2012 Independent Activity Report, West Valley Demonstration Project - July 2012 July 2012 Operational Awareness Oversight of the West...

  6. Pumpernickel Valley Geothermal Project Thermal Gradient Wells...

    Open Energy Information (Open El) [EERE & EIA]

    the geothermal activity in the valley are two areas with hot springs, seepages, and wet groundvegetation anomalies near the Pumpernickel Valley fault, which indicate that the...

  7. Golden Valley Wind Park | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Wind Park Jump to: navigation, search Name Golden Valley Wind Park Facility Golden Valley Wind Park Sector Wind energy Facility Type Commercial Scale Wind Facility Status In...

  8. Enterprise Assessments Review, West Valley Demonstration Project...

    Energy Savers

    West Valley Demonstration Project. The onsite review was conducted during May 19-22 and June 9-13, 2014. Enterprise Assessments Review, West Valley Demonstration Project - ...

  9. Enterprise Assessments Review, West Valley Demonstration Project...

    Energy.gov (indexed) [DOE]

    management program at the West Valley Demonstration Project (WVDP) was conducted prior to ... Assessments Review, West Valley Demonstration Project - December 2014 (245.41 KB) ...

  10. West Valley Demonstration Project | Department of Energy

    Energy.gov (indexed) [DOE]

    West Valley Demonstration Project compliance agreements, along with summaries of the agreements, can be viewed here. West Valley Demonstration Project Administrative Consent Order, ...

  11. Imperial Valley Geothermal Area | Department of Energy

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

    Resource Area in Southern California's Imperial Valley. The combined capacity at Imperial Valley is approximately 327 net megawatts. Photo of the Leathers geothermal power plant

  12. Aire Valley Environmental | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Aire Valley Environmental Jump to: navigation, search Name: Aire Valley Environmental Place: United Kingdom Product: Leeds-based waste-to-energy project developer. References: Aire...

  13. Whitewater Valley Rural EMC | Open Energy Information

    Open Energy Information (Open El) [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)...

  14. Hoopa Valley Tribe- 1994 Project

    Energy.gov [DOE]

    The Hoopa Valley Tribe is located in a northern California valley about 45 miles from the nearest city. The tribe is located in remote and mountainous area. The tribe was experiencing high energy costs to operate its community swimming pool due to the equipment's age, inefficient design, and the lack of a pool cover.

  15. Analysis of Potential Hydrogen Risk in the PWR Containment

    SciTech Connect (OSTI)

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

    2006-07-01

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

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

    SciTech Connect (OSTI)

    Cox, B.

    1985-10-01

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

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

    SciTech Connect (OSTI)

    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).

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  1. WEST VALLEY DEVELOPMENT PROJECT WEST VALLEY, NEW YORK NEWS MEDIA...

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

    of high-level waste (HLW) that had been generated by commercial reprocessing of spent nuclear fuel at the Western New York Nuclear Service Center in West Valley, New ...

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

    SciTech Connect (OSTI)

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

    1985-01-01

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

  3. 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

  4. Bear Creek Valley Watershed | Department of Energy

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

    Bear Creek Valley Watershed Bear Creek Valley Watershed This document discusses the Bear Creek Valley Watershed. Topics include: * The area's safety * Any use limitations for the area * History and cleanup background for this area * How DOE's cleanup program addressed the problem Bear Creek Valley Watershed fact sheet (814.29 KB) More Documents & Publications Melton Valley Watershed Upper East Fork Poplar Creek Cleanup Progress Report - 2010

  5. Valley Electric Association- Net Metering

    Energy.gov [DOE]

    The Board of Directors for Valley Electric Association (VEA) approved net metering in April 2008. The rules apply to systems up to 30 kW, though owners of larger systems may be able to negotiate...

  6. Swauk Valley | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Swauk Valley Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner McKinstry Developer McKinstry Location Ellensburg WA Coordinates 47.14163,...

  7. Dixie Valley Bottoming Binary Cycle

    Energy.gov [DOE]

    Project objective: Prove the technical and economic feasibility of utilizing the available unused heat to generate additional electric power from a binary power plant from low-temperature brine at the Dixie Valley Geothermal Power Plant.

  8. Case Study - Sioux Valley Energy

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

    Sioux Valley Energy SVE's smart meters report consumption levels every 30 minutes, which enables SVE to bill customers for critical peak events that occur on particular days and during particular time periods. This detailed billing cannot be done with conventional meters. Critical Peak Pricing Lowers Peak Demands and Electric Bills in South Dakota and Minnesota Sioux Valley Energy (SVE) is an electric cooperative serving approximately 21,000 customers in seven counties in South Dakota and

  9. Boulder Valley School District (Colorado) Power Purchase Agreement...

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

    Boulder Valley School District (Colorado) Power Purchase Agreement Case Study Boulder Valley School District (Colorado) Power Purchase Agreement Case Study Boulder Valley School ...

  10. Greene Valley Gas Recovery Biomass Facility | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley Gas Recovery Biomass Facility Jump to: navigation, search Name Greene Valley Gas Recovery Biomass Facility Facility Greene Valley Gas Recovery Sector Biomass Facility Type...

  11. Kittitas Valley Wind Power Project | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley Wind Power Project Jump to: navigation, search Name Kittitas Valley Wind Power Project Facility Kittitas Valley Wind Power Project Sector Wind energy Facility Type...

  12. Valley Center Municipal Water District | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley Center Municipal Water District Jump to: navigation, search Name: Valley Center Municipal Water District Place: Valley Center, California Zip: 92082 Product: VCMWD is the...

  13. Minnkota Power Cooperative Wind Turbine (Valley City) | Open...

    Open Energy Information (Open El) [EERE & EIA]

    Valley City) Jump to: navigation, search Name Minnkota Power Cooperative Wind Turbine (Valley City) Facility Minnkota Power Cooperative Wind Turbine (Valley City) Sector Wind...

  14. Bureau Valley School District Wind Farm | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley School District Wind Farm Jump to: navigation, search Name Bureau Valley School District Wind Farm Facility Bureau Valley School District Sector Wind energy Facility Type...

  15. South Valley Archived Soil & Groundwater Master Reports | Department...

    Energy.gov (indexed) [DOE]

    South Valley Archived Soil & Groundwater Master Reports South Valley - South Valley Plume (16.5 KB) More Documents & Publications Slick Rock Archived Soil & Groundwater Master ...

  16. Fish Lake Valley Geothermal Area | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Geothermal Area (Redirected from Fish Lake Valley Area) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Fish Lake Valley Geothermal Area Contents 1...

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

    SciTech Connect (OSTI)

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

    1984-03-01

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

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

    SciTech Connect (OSTI)

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

    1984-03-01

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

  19. Monument Valley Open House | Department of Energy

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

    Monument Valley Open House Monument Valley Open House July 18, 2016 - 12:22pm Addthis What does this project do? Goal 6. Engage the public, governments, and interested parties Monument Valley Open House 01.jpg An open house was held at Monument Valley High School in Utah. The U.S. Department of Energy Office of Legacy Management (LM) hosted the Uranium Issues Open House on Saturday, April 9, 2016, at Monument Valley High School in Monument Valley, Utah. Multiple federal agencies and their Navajo

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

    SciTech Connect (OSTI)

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

    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. DOE Awards Contract for the West Valley Demonstration Project...

    Office of Environmental Management (EM)

    the West Valley Demonstration Project Probabilistic Performance Assessment DOE Awards Contract for the West Valley Demonstration Project Probabilistic Performance Assessment ...

  2. West Valley Demonstration Project Phase I Decommissioning - Facility...

    Office of Environmental Management (EM)

    West Valley Demonstration Project Phase I Decommissioning - Facility Disposition Partnering Performance Agreement The Department of Energy, West Valley Demonstration Project ...

  3. City of Sunset Valley- PV Rebate Program

    Energy.gov [DOE]

    The Sunset Valley rebate is $1.00 per watt (W) up to 3,000 W. In order to qualify for the Sunset Valley rebate, the system must first qualify for an Austin Energy rebate. In addition, the system...

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    T.L. Lotz

    1997-01-29

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

  6. Monument Valley, Arizona, Processing Site Fact Sheet

    Office of Legacy Management (LM)

    Monument Valley, Arizona, Processing Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing site at Monument Valley, Arizona. This site is managed by the U.S. Department of Energy Office of Legacy Management. Site Description and History The Monument Valley processing site is located on the Navajo Nation in northeastern Arizona, approximately 15 miles south of Mexican Hat, Utah, on the west side of Cane Valley. A uranium-ore

  7. ANTELOPE VALLEY SOLAR RANCH | Department of Energy

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

    ANTELOPE VALLEY SOLAR RANCH ANTELOPE VALLEY SOLAR RANCH DOE-LPO_Project-Posters_PV_AVSR.pdf (633.27 KB) More Documents & Publications CRESCENT DUNES ANTELOPE VALLEY SOLAR RANCH Powering New Markets: Utility-scale Photovoltaic Solar Hearing Before the House Natural Resources Subcommittee on Oversight and Investigations

  8. CALIFORNIA VALLEY SOLAR RANCH | Department of Energy

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

    CALIFORNIA VALLEY SOLAR RANCH CALIFORNIA VALLEY SOLAR RANCH DOE-LPO_Project-Posters_PV_CVSR.pdf (898.61 KB) More Documents & Publications EA-1840: Finding of No Significant Impact EA-1840: Final Environmental Assessment California Valley Solar Ranch Biological Assessment

  9. Hoopa Valley Tribe- 1995 Project

    Energy.gov [DOE]

    The Hoopa Valley Tribe is located in remote area about 45 miles from the nearest city. There is not much to keep the youth busy. The tribe purchased a 3,672-square-foot metal building and dedicated it to be used as a youth center.

  10. Hoopa Valley Tribe- 2006 Project

    Energy.gov [DOE]

    The Hoopa Valley Tribe will assess the feasibility of smaller-scale hydroelectric facilities (between 100 KW and 5 MW). The feasibility study will focus on analyzing, qualifying, and quantifying the opportunity for the tribe to develop, own and operate hydroelectric plants on tribal lands, either for direct use by the tribe, or for selling power.

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

    SciTech Connect (OSTI)

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

    2014-09-30

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

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

    SciTech Connect (OSTI)

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

    2015-09-30

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

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

    SciTech Connect (OSTI)

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

    1993-07-01

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

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

    SciTech Connect (OSTI)

    Cardoni, Jeffrey

    2010-11-01

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

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

    SciTech Connect (OSTI)

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

    1984-05-01

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

  16. James Valley Ethanol LLC | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    James Valley Ethanol LLC Place: Gronton, South Dakota Zip: 57445 Product: Farmers owned cooperative that built and operates an ethanol production facility. Coordinates: 29.72369,...

  17. Silicon Valley Biodiesel Inc | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Biodiesel Inc Jump to: navigation, search Name: Silicon Valley Biodiesel Inc. Place: Sunnyvale, California Zip: CA 94086 Product: Manufactures biodiesel for the local diesel fuel...

  18. Poudre Valley REA- Commercial Lighting Rebate Program

    Energy.gov [DOE]

    Poudre Valley Rural Electric Association (PVREA), a Touchstone Energy Cooperative, offers a variety of lighting rebates to commercial customers. Rebates are available on commercial lighting...

  19. Dixie Valley Geothermal Project | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    n":"","group":"","inlineLabel":"","visitedicon":"" Hide Map Location Nevada County Churchill County, NV Geothermal Area Dixie Valley Geothermal Area Geothermal Region Central...

  20. Dixie Valley Geothermal Area | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Field Area) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Dixie Valley Geothermal Area Contents 1 Area Overview 2 History and Infrastructure 2.1 U.S. Department...

  1. Golden Valley Electric Association - Residential Energy Efficiency...

    Energy.gov (indexed) [DOE]

    30 Timer Controlling Exterior Vehicle Plug-In Outlet: 20 Switch Controlling Exterior Vehicle Plug-In Outlet: 10 Summary Golden Valley Electric Association's (GVEA) Builder...

  2. Magnetotellurics At Dixie Valley Geothermal Area (Iovenitti,...

    Open Energy Information (Open El) [EERE & EIA]

    H. Ibser, Jennifer Lewicki, B. Mack. Kennedy, Michael Swyer (2013) Egs Exploration Methodology Project Using the Dixie Valley Geothermal System, Nevada, Status Update Phil...

  3. Tennessee Valley Authority | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Authority Jump to: navigation, search Name: Tennessee Valley Authority Place: Tennessee Phone Number: (865) 632-2101 Website: www.tva.gov Twitter: @tvanewsroom Facebook: https:...

  4. Squirrel Mountain Valley, California: Energy Resources | Open...

    Open Energy Information (Open El) [EERE & EIA]

    Squirrel Mountain Valley, California: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 35.6232866, -118.4098058 Show Map Loading map......

  5. Minnesota Valley Electric Coop | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    https:www.facebook.compagesMinnesota-Valley-Electric-Cooperative212971310374 Outage Hotline: 1-800-232-2328 Outage Map: outage.mvec.net References: EIA Form EIA-861...

  6. Hydrologic Monitoring Summary Long Valley Caldera, California...

    Open Energy Information (Open El) [EERE & EIA]

    Summary Long Valley Caldera, California Abstract Abstract unavailable. Author Michael L. Sorey Published ORMAT internal report, 2010 DOI Not Provided Check for DOI...

  7. West Valley Demonstration Project Administrative Consent Order...

    Office of Environmental Management (EM)

    West Valley Demonstration Project (WVDP) Adminstrative Consent Order, August 27, 1996 State New York Agreement Type Consent Order Legal Driver(s) FFCAct Scope Summary Establish ...

  8. Workplace Charging Challenge Partner: Organic Valley | Department...

    Office of Environmental Management (EM)

    Organic Valley believes that the installation of plug-in electric vehicle charging stations coupled with their use of renewable energy demonstrates their commitment to this goal. ...

  9. West Valley Demonstration Project Waste Management Environmental...

    Office of Environmental Management (EM)

    West Valley Demonstration Project Waste Management Environmental Impact Statement ... June 7, 2006 WVDP Waste Management US - Supplement Analysis Table of Contents 1.0 PURPOSE ...

  10. Valley Electric Association- Solar Water Heating Program

    Energy.gov [DOE]

    Valley Electric Association (VEA), a nonprofit member owned cooperative, developed the domestic solar water heating program to encourage energy efficiency at the request of the membership. VEA...

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

    SciTech Connect (OSTI)

    Kwi Lim Lee; Soon Heung Chang

    2004-07-01

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

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

    SciTech Connect (OSTI)

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

    1982-09-01

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

  13. American Ref-Fuel of Delaware Valley Biomass Facility | Open...

    Open Energy Information (Open El) [EERE & EIA]

    Ref-Fuel of Delaware Valley Biomass Facility Jump to: navigation, search Name American Ref-Fuel of Delaware Valley Biomass Facility Facility American Ref-Fuel of Delaware Valley...

  14. Dixie Valley, Nevada: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    article is a stub. You can help OpenEI by expanding it. Dixie Valley is a city in Churchill County, Nevada. Energy Generation Facilities in Dixie Valley, Nevada Dixie Valley...

  15. Poudre Valley R E A, Inc | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Poudre Valley R E A, Inc Jump to: navigation, search Name: Poudre Valley R E A, Inc Place: Colorado Website: www.pvrea.com Twitter: @PoudreValleyREA Facebook: https:...

  16. Solar Goes Big: Launching the California Valley Solar Ranch ...

    Energy Savers

    Goes Big: Launching the California Valley Solar Ranch Solar Goes Big: Launching the California Valley Solar Ranch October 31, 2013 - 4:14pm Addthis The California Valley Solar ...

  17. Monument Valley Phytoremediation Pilot Study:

    Office of Legacy Management (LM)

    1.8 U.S. Department of Energy UMTRA Ground Water Project Monument Valley Ground Water Remediation Work Plan: Native Plant Farming and Phytoremediation Pilot Study August 1998 Prepared for U.S. Department of Energy Albuquerque Operations Office Grand Junction Office Prepared by MACTEC Environmental Restoration Services, LLC Grand Junction, Colorado Project Number UGW-511-0015-10-000 Document Number U0029501 Work Performed under DOE Contract No. DE-AC13-96GJ87335 Note: Some of the section page

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

    SciTech Connect (OSTI)

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

    2000-10-03

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

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  4. 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

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    Shaver, Mark W.; Lanning, Donald D.

    2010-02-01

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

  7. Santa Clara Valley Transportation Authority and San Mateo County...

    Office of Environmental Management (EM)

    Santa Clara Valley Transportation Authority and San Mateo County Transit District -- Fuel Cell Transit Buses: Evaluation Results Santa Clara Valley Transportation Authority and San ...

  8. Lichuan City Yujiang River Valley Hydro Co Ltd | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Lichuan City Yujiang River Valley Hydro Co Ltd Jump to: navigation, search Name: Lichuan City Yujiang River Valley Hydro Co., Ltd. Place: Hubei Province, China Zip: 445400 Sector:...

  9. Langel Valley Space Heating Low Temperature Geothermal Facility...

    Open Energy Information (Open El) [EERE & EIA]

    Langel Valley Space Heating Low Temperature Geothermal Facility Jump to: navigation, search Name Langel Valley Space Heating Low Temperature Geothermal Facility Facility Langel...

  10. Surprise Valley Hospital Space Heating Low Temperature Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    Surprise Valley Hospital Space Heating Low Temperature Geothermal Facility Jump to: navigation, search Name Surprise Valley Hospital Space Heating Low Temperature Geothermal...

  11. Hydroprobe At Gabbs Valley Area (DOE GTP) | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Gabbs Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Hydroprobe At Gabbs Valley Area (DOE GTP) Exploration Activity...

  12. Owens Corning and Silicon Valley Power Partner to Make Energy...

    Energy.gov (indexed) [DOE]

    DOE energy assessments and Silicon Valley Power utility incentives to save 252,000 annually through plant-wide improvements. Owens Corning and Silicon Valley Power Partner to ...

  13. Micro-Earthquake At Dixie Valley Geothermal Area (Katz & J.,...

    Open Energy Information (Open El) [EERE & EIA]

    Dixie Valley Geothermal Area (Katz & J., 1984) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Micro-Earthquake At Dixie Valley Geothermal Area...

  14. City of Water Valley, Mississippi (Utility Company) | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Valley, Mississippi (Utility Company) Jump to: navigation, search Name: City of Water Valley Place: Mississippi Phone Number: (662) 473-3243 Outage Hotline: (662) 473-3243...

  15. Isotopic Analysis- Fluid At Rose Valley Geothermal Area (1990...

    Open Energy Information (Open El) [EERE & EIA]

    Rose Valley Geothermal Area (1990) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Isotopic Analysis- Fluid At Rose Valley Geothermal Area (1990)...

  16. Long Valley Caldera Geothermal Area | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Long Valley Caldera Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Long Valley Caldera Geothermal Area Contents 1 Area Overview 2 History and...

  17. Santa Clara Valley Transportation Authority and San Mateo County...

    Office of Environmental Management (EM)

    Santa Clara Valley Transportation Authority and San Mateo County Transit District Santa Clara Valley Transportation Authority and San Mateo County Transit District Fuel Cell ...

  18. Smith Creek Valley Geothermal Area | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Smith Creek Valley Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Smith Creek Valley Geothermal Area Contents 1 Area Overview 2 History and...

  19. Single-valley engineering in graphene superlattices (Journal...

    Office of Scientific and Technical Information (OSTI)

    Single-valley engineering in graphene superlattices This content will become publicly available on June 14, 2016 Title: Single-valley engineering in graphene superlattices Authors: ...

  20. Rock Sampling At Long Valley Caldera Geothermal Area (Goff, Et...

    Open Energy Information (Open El) [EERE & EIA]

    Long Valley Caldera Geothermal Area (Goff, Et Al., 1991) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Rock Sampling At Long Valley Caldera...

  1. Pressure Temperature Log At Fish Lake Valley Area (DOE GTP) ...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Pressure Temperature Log At Fish Lake Valley Area (DOE GTP)...

  2. Thermochronometry At Fish Lake Valley Area (DOE GTP) | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Thermochronometry At Fish Lake Valley Area (DOE GTP) Exploration...

  3. Static Temperature Survey At Fish Lake Valley Area (Deymonaz...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (Deymonaz, Et Al., 2008) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Static Temperature Survey At Fish Lake Valley Area...

  4. Hyperspectral Imaging At Fish Lake Valley Area (Littlefield ...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (Littlefield & Calvin, 2010) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Hyperspectral Imaging At Fish Lake Valley Area...

  5. Geothermometry At Fish Lake Valley Area (DOE GTP) | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Geothermometry At Fish Lake Valley Area (DOE GTP) Exploration...

  6. Compound and Elemental Analysis At Fish Lake Valley Area (DOE...

    Open Energy Information (Open El) [EERE & EIA]

    ENERGYGeothermal Home Exploration Activity: Compound and Elemental Analysis At Fish Lake Valley Area (DOE GTP) Exploration Activity Details Location Fish Lake Valley Area...

  7. Geographic Information System At Fish Lake Valley Area (Deymonaz...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (Deymonaz, Et Al., 2008) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Geographic Information System At Fish Lake Valley...

  8. Fish Lake Valley Geothermal Area | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Fish Lake Valley Geothermal Area Contents 1 Area Overview 2 History and Infrastructure...

  9. Coachella Valley Fish Farm Aquaculture Low Temperature Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    Coachella Valley Fish Farm Aquaculture Low Temperature Geothermal Facility Jump to: navigation, search Name Coachella Valley Fish Farm Aquaculture Low Temperature Geothermal...

  10. Modeling-Computer Simulations At Fish Lake Valley Area (Deymonaz...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (Deymonaz, Et Al., 2008) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Modeling-Computer Simulations At Fish Lake Valley...

  11. Geothermal Literature Review At Fish Lake Valley Area (Deymonaz...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (Deymonaz, Et Al., 2008) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Geothermal Literature Review At Fish Lake Valley...

  12. Valley Fish Farms Aquaculture Low Temperature Geothermal Facility...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Farms Aquaculture Low Temperature Geothermal Facility Jump to: navigation, search Name Valley Fish Farms Aquaculture Low Temperature Geothermal Facility Facility Valley Fish...

  13. Thermal Gradient Holes At Long Valley Caldera Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    Long Valley Caldera Geothermal Area (Conservation, 2009) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Thermal Gradient Holes At Long Valley...

  14. Contract Awarded for West Valley Demonstration Project Data Management...

    Office of Environmental Management (EM)

    Contract Awarded for West Valley Demonstration Project Data Management System, Technical Services Contract Awarded for West Valley Demonstration Project Data Management System, ...

  15. Enforcement Letter, West Valley Nuclear Services- March 30, 1998

    Energy.gov [DOE]

    Issued to West Valley Nuclear Services related to Hazard Analysis, Design Review, Work Control Implementation, and a Contamination Event at the West Valley Demonstration Project

  16. Structure, Stratigraphy, and Tectonics of the Dixie Valley Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    and Tectonics of the Dixie Valley Geothermal Site, Dixie Valley, Nevada Author Gabriel L. Plank Published Journal Geothermal Resources Council Transactions, 1995 DOI Not...

  17. Hydrology of the Geothermal System in Long Valley Caldera, California...

    Open Energy Information (Open El) [EERE & EIA]

    System in Long Valley Caldera, California Abstract Abstract unavailable. Author Michael L. Sorey Published Unpublished report for the Long Valley Hydrologic Advisory Committee,...

  18. Soil Sampling At Dixie Valley Geothermal Area (Nash & D., 1997...

    Open Energy Information (Open El) [EERE & EIA]

    Dixie Valley Geothermal Area (Nash & D., 1997) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Soil Sampling At Dixie Valley Geothermal Area...

  19. DOE Issues RFP for West Valley Demonstration Project Probabilistic...

    Energy Savers

    RFP for West Valley Demonstration Project Probabilistic Performance Assessment DOE Issues RFP for West Valley Demonstration Project Probabilistic Performance Assessment April 2, ...

  20. DOE - Office of Legacy Management -- West Valley Demonstration...

    Office of Legacy Management (LM)

    Valley Demonstration Project - NY 23 FUSRAP Considered Sites Site: West Valley Demonstration Project (NY.23) Designated Name: Alternate Name: Location: Evaluation Year: Site ...

  1. Enterprise Assessments Review of the West Valley Demonstration...

    Office of Environmental Management (EM)

    West Valley Demonstration Project Site Fire Protection Program - March 2016 Enterprise Assessments Review of the West Valley Demonstration Project Site Fire Protection Program - ...

  2. West Valley Demonstration Project: A Short History and Status...

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

    Project: A Short History and Status West Valley Demonstration Project: A Short History and ... 2013 in Buffalo, NY. West Valley Demonstration Project: A Short History and Status ...

  3. FTCP Site Specific Information - West Valley Demonstration Project...

    Energy Savers

    West Valley Demonstration Project FTCP Site Specific Information - West Valley Demonstration Project Annual Workforce Analysis and Staffing Plan Report Calendar Year 2012

  4. Compound and Elemental Analysis At Little Valley Area (Wood,...

    Open Energy Information (Open El) [EERE & EIA]

    Little Valley Area (Wood, 2002) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Compound and Elemental Analysis At Little Valley Area (Wood,...

  5. Atmospheric dispersion in mountain valleys and basins

    SciTech Connect (OSTI)

    Allwine, K.J.

    1992-01-01

    The primary goal of the research is to further characterize and understand dispersion in valley and basin atmospheres. A secondary, and related goal, is to identify and understand the dominant physical processes governing this dispersion. This has been accomplished through a review of the current literature, and analyses of recently collected data from two field experiments. This work should contribute to an improved understanding of material transport in the atmospheric boundary layer. It was found that dispersion in a freely draining valley (Brush Creek valley, CO) atmosphere is much greater than in an enclosed basin (Roanoke, VA) atmosphere primarily because of the greater wind speeds moving past the release point and the greater turbulence levels. The development of a cold air pool in the Roanoke basin is the dominant process governing nighttime dispersion in the basin, while the nighttime dispersion in the Brush Creek valley is dominated by turbulent diffusion and plume confinement between the valley sidewalls. The interaction between valley flows and above ridgetops flows is investigated. A ``ventilation rate`` of material transport between the valley and above ridgetop flows is determined. This is important in regional air pollution modeling and global climate modeling. A simple model of dispersion in valleys, applicable through a diurnal cycle, is proposed.

  6. Atmospheric dispersion in mountain valleys and basins

    SciTech Connect (OSTI)

    Allwine, K.J.

    1992-01-01

    The primary goal of the research is to further characterize and understand dispersion in valley and basin atmospheres. A secondary, and related goal, is to identify and understand the dominant physical processes governing this dispersion. This has been accomplished through a review of the current literature, and analyses of recently collected data from two field experiments. This work should contribute to an improved understanding of material transport in the atmospheric boundary layer. It was found that dispersion in a freely draining valley (Brush Creek valley, CO) atmosphere is much greater than in an enclosed basin (Roanoke, VA) atmosphere primarily because of the greater wind speeds moving past the release point and the greater turbulence levels. The development of a cold air pool in the Roanoke basin is the dominant process governing nighttime dispersion in the basin, while the nighttime dispersion in the Brush Creek valley is dominated by turbulent diffusion and plume confinement between the valley sidewalls. The interaction between valley flows and above ridgetops flows is investigated. A ventilation rate'' of material transport between the valley and above ridgetop flows is determined. This is important in regional air pollution modeling and global climate modeling. A simple model of dispersion in valleys, applicable through a diurnal cycle, is proposed.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

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

    1996-08-01

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

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

    SciTech Connect (OSTI)

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

    2013-07-01

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

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

    SciTech Connect (OSTI)

    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.

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

    Energy Science and Technology Software Center (OSTI)

    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

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

  16. Hoopa Valley Tribe - Small Hydropower Feasibility Study

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

    Micro-Hydro Feasibility Study Hoopa Valley Tribe Curtis Miller The Hoopa Valley Reservation was established in 1868 by executive order of Ulysses S. Grant and contains the aboriginal homeland of the Hupa People. It encompasses approximately 100,000 acres and is 96% owned by the Hoopa Tribe. Salmon are the life blood of the Hupa and Yurok and Karuk people There are over 1200 miles of major streams within the Hoopa Valley Reservation many of which support Salmon and Rainbow trout. 50-60 inches of

  17. Cumberland Valley Electric Cooperative- Business Energy Efficiency Rebate Program

    Energy.gov [DOE]

    Cumberland Valley Electric Cooperative offers businesses rebates for energy efficient lighting and compressed air delivery retrofits.

  18. Enterprise Assessments Review, West Valley Demonstration Project – December 2014

    Energy.gov [DOE]

    Review of the West Valley Demonstration Project Emergency Management Program Technical Basis and Emergency Preparedness

  19. West Valley Demonstration Project Site Environmental Report Calendar Year 2000

    SciTech Connect (OSTI)

    2001-08-31

    The annual site environmental monitoring report for the West Valley Demonstration Project nuclear waste management facility.

  20. Workplace Charging Challenge Partner: The Valley Health System | Department

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

    of Energy Valley Health System Workplace Charging Challenge Partner: The Valley Health System Workplace Charging Challenge Partner: The Valley Health System Joined the Challenge: June 2016 Headquarters: Ridgewood, NJ Charging Location: Ridgewood, NJ Domestic Employees: 4,000 The Valley Hospital and the Valley Health System have a longstanding commitment to environmental sustainability. As an award-winning member of Practice GreenHealth and as a recipient of the 2016 Vizient Excellence Award

  1. Elkhorn Valley Ethanol LLC | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Elkhorn Valley Ethanol LLC Place: Norfolk, Nebraska Zip: 68701 Product: Operates a 40m gallon ethanol plant in Norfolk, Nebraska. Coordinates: 36.846825, -76.285069 Show Map...

  2. Carroll Valley, Pennsylvania: Energy Resources | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    article is a stub. You can help OpenEI by expanding it. Carroll Valley is a borough in Adams County, Pennsylvania. It falls under Pennsylvania's 19th congressional district.12...

  3. Poudre Valley REA- Photovoltaic Rebate Program

    Office of Energy Efficiency and Renewable Energy (EERE)

    Poudre Valley REA (PVREA) is providing rebates to their residential customers who install photovoltaic (PV) systems on their homes. The consumer agrees to assign all Renewable Energy Credits (RECs)...

  4. Fort Valley Utility Comm | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Fort Valley Utility Comm Place: Georgia Phone Number: 478-825-7701 Website: fvutil.com Twitter: @fvutil Facebook: https:www.facebook.comfvutil Outage Map: fvutil.comnews...

  5. Bear Valley Electric Service- Solar Initiative Program

    Energy.gov [DOE]

    Bear Valley Electric Service is providing an incentive for their residential customers to install photovoltaic (PV) systems. Systems must be sized to provide no more than 90% of the calculated or...

  6. Lower Valley Energy Inc | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    LowerValleyEnergy Outage Hotline: 800-882-5875 References: Energy Information Administration.1 EIA Form 861 Data Utility Id 11273 This article is a stub. You can help OpenEI...

  7. Tennessee Valley Authority (Mississippi) | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Name: Tennessee Valley Authority Place: Mississippi References: Energy Information Administration.1 EIA Form 861 Data Utility Id 18642 This article is a stub. You can help OpenEI...

  8. VALMET-A valley air pollution model

    SciTech Connect (OSTI)

    Whiteman, C.D.; Allwine, K.J.

    1983-09-01

    Following a thorough analysis of meteorological data obtained from deep valleys of western Colorado, a modular air-pollution model has been developed to simulate the transport and diffusion of pollutants released from an elevated point source in a well-defined mountain valley during the nighttime and morning transition periods. This initial version of the model, named VALMET, operates on a valley cross section at an arbitrary distance down-valley from a continuous point source. The model has been constructed to include parameterizations of the major physical processes that act to disperse pollution during these time periods. The model has not been fully evaluated. Further testing, evaluations, and development of the model are needed. Priorities for further development and testing are provided.

  9. Lighthouse Solar Indian Valley | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Lighthouse Solar Indian Valley Address: 5062 McLean Station Road Place: Green Lane, PA Zip: 18054 Sector: Solar Phone Number: (215) 541-5464 Website: www.lighthousesolar.com...

  10. West Valley Demonstration Project Unique Remote Operations

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

    Approved for Public Release; Further Dissemination Unlimited West Valley Demonstration Project 2016 EM Success Story Jeff Bradford, President and General Manager CH2M HILL BWXT West Valley, LLC. September 14, 2016 www.energy.gov/EM 2 2016 Goals * Excellent Safety Performance * Complete the High-Level Waste Relocation and Storage Project * Complete the offsite shipment and disposal of the vitrification components (Melter, CFMT and MHFT) * Complete demolition preparations in the Extraction Cells

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

    DOE PAGES-Beta [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

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    Rodriguez, S.E.

    1985-01-01

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

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

    SciTech Connect (OSTI)

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

    1986-05-01

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

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

    SciTech Connect (OSTI)

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

    1981-01-01

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

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

    SciTech Connect (OSTI)

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

    1983-03-01

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

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

    SciTech Connect (OSTI)

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

    1987-05-21

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

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

    SciTech Connect (OSTI)

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

    1985-02-01

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

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

    SciTech Connect (OSTI)

    Gilles Youinou; Andrea Alfonsi

    2012-03-01

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

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

    SciTech Connect (OSTI)

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

    1995-11-01

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

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

    SciTech Connect (OSTI)

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

    1986-11-01

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

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

    SciTech Connect (OSTI)

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

    2007-07-01

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

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

    SciTech Connect (OSTI)

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

    1985-04-01

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

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

    SciTech Connect (OSTI)

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

    1983-01-01

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

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

    SciTech Connect (OSTI)

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

    1983-01-01

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

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

    SciTech Connect (OSTI)

    J.W. Davis

    1996-08-29

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

  8. Sulphur Springs Valley E C Inc | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Springs Valley E C Inc Jump to: navigation, search Name: Sulphur Springs Valley E C Inc Abbreviation: SSVEC Place: Arizona Phone Number: 1-(800) 422-3275 Website: www.ssvec.org...

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

    Open Energy Information (Open El) [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...

  10. Core Holes At Long Valley Caldera Geothermal Area (Lachenbruch...

    Open Energy Information (Open El) [EERE & EIA]

    Regime of Long Valley Caldera. Journal of Geophysical Research. 81(5):763-768. J.L. Smith,R.W. Rex. 1977. Drilling results from eastern Long Valley Caldera. () : American...

  11. Thermal Gradient Holes At Long Valley Caldera Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    Regime of Long Valley Caldera. Journal of Geophysical Research. 81(5):763-768. J.L. Smith,R.W. Rex. 1977. Drilling results from eastern Long Valley Caldera. () : American...

  12. Long Valley Caldera Field Trip Log | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    to library Conference Paper: Long Valley Caldera Field Trip Log Abstract NA Authors Gene A. Suemnicht and Bastien Poux Conference NGA Long Valley Field Trip, July 5-7, 2012;...

  13. Minnesota Valley Coop L&P Assn | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Minnesota Valley Coop L&P Assn Jump to: navigation, search Name: Minnesota Valley Coop L&P Assn Place: Minnesota Phone Number: 320-269-2163 or 1-800-247-5051 Website:...

  14. Tallahatchie Valley E P A | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley E P A Jump to: navigation, search Name: Tallahatchie Valley E P A Place: Mississippi Phone Number: 662.563.4742 Website: www.tvepa.comhome.aspx Outage Hotline: 662-563-4742...

  15. Lower Valley Energy- Residential Energy Efficiency Rebate Program

    Office of Energy Efficiency and Renewable Energy (EERE)

    Lower Valley Energy offers rebates for residential customers who wish to increase the energy efficiency of eligible homes. Contact Lower Valley Energy by phone for more specific information on the...

  16. West Valley Demonstration Project Prepares to Relocate High-Level...

    Office of Environmental Management (EM)

    Prepares to Relocate High-Level Waste West Valley Demonstration Project Prepares to Relocate High-Level Waste December 24, 2013 - 12:00pm Addthis The West Valley Demonstration ...

  17. West Valley Demonstration Project Low-Level Waste Shipment |...

    Office of Environmental Management (EM)

    Low-Level Waste Shipment West Valley Demonstration Project Low-Level Waste Shipment West Valley Demonstration Project Low-Level Waste Shipment (406.16 KB) More Documents & ...

  18. San Luis Valley R E C, Inc | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Luis Valley R E C, Inc Jump to: navigation, search Name: San Luis Valley R E C, Inc Place: Colorado Phone Number: 1.800.332.7634 Website: www.slvrec.com Twitter: @SLVREC Facebook:...

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

    Open Energy Information (Open El) [EERE & EIA]

    Valley Elec Assn, Inc Jump to: navigation, search Name: Copper Valley Elec Assn, Inc Place: Alaska Phone Number: Copper Basin: 907-822-3211 or Valdez: 907-835-4301 Website:...

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

    Open Energy Information (Open El) [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:...

  1. The Near-Surface Hydrothermal Regime of Long Valley Caldera ...

    Open Energy Information (Open El) [EERE & EIA]

    of Long Valley Caldera Citation Arthur H. Lachenbruch,Michael L. Sorey,Robert Edward Lewis,John H. Sass. 1976. The Near-Surface Hydrothermal Regime of Long Valley Caldera....

  2. Hoopa Valley Tribe - Small Hydro Project

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

    Hydro Power Feasibility Study Hoopa Valley Tribe Curtis Miller cmiller@hoopa-nsn.gov (530)-625-5515 There are over 1200 miles of major streams within the Hoopa Valley Reservation many of which support Salmon, Steelhead and Rainbow trout. 50-60 inches of rainfall /year In the beginning In FY 2005 the Hoopa Tribal EPA received a grant from DOE to conduct a 2 year feasibility study for small scale hydropower on 7 major tributaries of the Reservation that flow into the Trinity River Concept of

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

    SciTech Connect (OSTI)

    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

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

    SciTech Connect (OSTI)

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

    2002-02-11

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

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

    SciTech Connect (OSTI)

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

    2002-07-01

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

  6. Kinarot Jordan Valley Technological Incubator | Open Energy Informatio...

    Open Energy Information (Open El) [EERE & EIA]

    - Jordan Valley Technological Incubator Place: Israel Sector: Services Product: General Financial & Legal Services ( Private family-controlled ) References: Kinarot - Jordan...

  7. Progress Moves West Valley Closer to Finishing Canister Relocation Project

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

    | Department of Energy Moves West Valley Closer to Finishing Canister Relocation Project Progress Moves West Valley Closer to Finishing Canister Relocation Project October 17, 2016 - 12:10pm Addthis Workers place a vertical storage cask liner on a construction pad. Workers place a vertical storage cask liner on a construction pad. WEST VALLEY, N.Y. - EM's West Valley Demonstration Project (WVDP) is about 70 percent complete toward relocating all high-level waste canisters from a building to

  8. 2014 Annual Planning Summary for the West Valley Demonstration Project

    Energy.gov [DOE]

    The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2014 and 2015 within the West Valley Demonstration Project.

  9. WEST VALLEY DEMONSTRATION PROJECT SITE ENVIRONMENTAL REPORT CALENDARY YEAR 2001

    SciTech Connect (OSTI)

    2002-09-30

    THE ANNUAL (CALENDAR YEAR 2001) SITE ENVIRONMENTAL MONITORING REPORT FOR THE WEST VALLEY DEMONSTRATION PROJECT NUCLEAR WASTE MANAGEMENT FACILITY.

  10. California Valley Solar Ranch Biological Assessment | Department of Energy

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

    California Valley Solar Ranch Biological Assessment California Valley Solar Ranch Biological Assessment Biological Assessment for the California Valley Solar Ranch Project San Luis Obispo County, California High Plains Ranch II, LLC (HPR II), a wholly owned subsidiary of SunPower Corporation, Systems ("SunPower") proposes to construct a 250-megawatt (MW) solar photovoltaic (PV) energy plant, the California Valley Solar Ranch Project (CVSR Project or Project), on a 4,747acre site in

  11. Lobbyist Disclosure Form - Silicon Valley | Department of Energy

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

    Silicon Valley Lobbyist Disclosure Form - Silicon Valley Jonathan Silver, Energy Department executive director loans program, gave Colleen Quinn, Silicon Valley Leadership Group vice president of government relations and public policy, a broad overview of the work done by the LPO, and discussed the possible future of clean energy investment. Lobbyist Disclosure Form - Silicon Valley.pdf (35.2 KB) More Documents & Publications Lobbyist Disclosure Form - AltEn Lobbyist Disclosure Form - First

  12. Silicon Valley Power- Residential Energy Efficiency Rebate Program

    Energy.gov [DOE]

    Silicon Valley Power offers rebates to residential customers for the purchase of a variety of energy efficient products including:

  13. Enterprise Assessments Review of the West Valley Demonstration Project Site

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

    Fire Protection Program - March 2016 | Department of Energy West Valley Demonstration Project Site Fire Protection Program - March 2016 Enterprise Assessments Review of the West Valley Demonstration Project Site Fire Protection Program - March 2016 March 2016 Review of the Fire Protection Program at the West Valley Demonstration Project The U.S. Department of Energy (DOE) independent Office of Enterprise Assessments (EA) conducted a review of the fire protection program at the West Valley

  14. Project Reports for Hoopa Valley Tribe- 2006 Project

    Energy.gov [DOE]

    The Hoopa Valley Tribe will assess the feasibility of smaller-scale hydroelectric facilities (between 100 KW and 5 MW).

  15. Modeling-Computer Simulations At Dixie Valley Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Modeling-Computer Simulations At Dixie Valley Geothermal Area (Wisian & Blackwell, 2004) Exploration...

  16. Modeling-Computer Simulations At Dixie Valley Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Modeling-Computer Simulations At Dixie Valley Geothermal Area (Kennedy & Soest, 2006) Exploration...

  17. West Valley Demonstration Project - 2016 EM Success Story | Department of

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

    Energy - 2016 EM Success Story West Valley Demonstration Project - 2016 EM Success Story Presentation from the 2016 DOE National Cleanup Workshop by Jeff Bradford, President and General Manager, CH2M HILL BWXT West Valley, LLC. West Valley Demonstration Project - 2016 EM Success Story (1.75 MB) More Documents & Publications Probabilistic Modeling and Phase 2 Decision Making at the West Valley Demonstration Project and the Western New York Nuclear Service Center The Path to Success Beyond

  18. Field Mapping At Lualualei Valley Area (Thomas, 1986) | Open...

    Open Energy Information (Open El) [EERE & EIA]

    to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Field Mapping At Lualualei Valley Area (Thomas, 1986) Exploration Activity Details Location...

  19. 2012 Annual Planning Summary for West Valley Demonstration Project

    Energy.gov [DOE]

    The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2012 and 2013 within West Valley Demonstration Project.

  20. Santa Clara Valley Transportation Authority | Department of Energy

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

    Technology Validation » Santa Clara Valley Transportation Authority Santa Clara Valley Transportation Authority Santa Clara Valley Transportation Authority logo Santa Clara Valley Transportation Authority (VTA) is based in San Jose, California, and provides service in and around Santa Clara county. VTA provides bus and light rail service in Santa Clara County, as well as congestion mitigation, highway improvement projects, and countywide transportation planning. VTA's 423 buses serve an annual

  1. Project Reports for Elk Valley Rancheria- 2010 Project

    Energy.gov [DOE]

    Elk Valley Rancheria will perform a comprehensive Energy Efficiency and Alternatives Study for tribal properties on the Rancheria.

  2. Geothermal Literature Review At Long Valley Caldera Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Geothermal Literature Review At Long Valley Caldera Geothermal Area (Goldstein & Flexser, 1984)...

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

    SciTech Connect (OSTI)

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

    1986-01-01

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

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

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

    1997-04-01

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

  7. NNSS Soils Monitoring: Plutonium Valley (CAU366)

    SciTech Connect (OSTI)

    Miller, Julianne J.; Mizell, Steve A.; Nikolich, George; Campbell, Scott

    2012-02-01

    The U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Nevada Site Office (NSO), Environmental Restoration Soils Activity has authorized the Desert Research Institute (DRI) to conduct field assessments of potential sediment transport of contaminated soil from Corrective Action Unit (CAU) 366, Area 11 Plutonium Valley Dispersion Sites Contamination Area (CA) during precipitation runoff events.

  8. Indian Wells Valley FORGE Aeromagnetic Data

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

    Doug Blankenship

    1994-11-01

    Aeromagnetic data was collected over the Indian Wells Valley, CA in November 1994. It consisted of 9,033 line-kilometers covering ~4,150 square kilometers, flown at a 250 meter drape with principal line spacing of 0.54 kilometers and 10% cross-lines. The principal orientation is N65E.

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

    SciTech Connect (OSTI)

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

    1985-04-01

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

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

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

    2006-07-01

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

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

    SciTech Connect (OSTI)

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

    1985-03-01

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

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

    SciTech Connect (OSTI)

    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)

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

    SciTech Connect (OSTI)

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

    1997-08-01

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

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

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

    1992-07-01

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

  17. Hudson Valley Clean Energy Office and Warehouse

    High Performance Buildings Database

    Rhinebeck, NY Hudson Valley Clean Energy's new head office and warehouse building in Rhinebeck, New York, achieved proven net-zero energy status on July 2, 2008, upon completing its first full year of operation. The building consists of a lobby, meeting room, two offices, cubicles for eight office workers, an attic space for five additional office workers, ground- and mezzanine-level parts and material storage, and indoor parking for three contractor trucks. 06/01/2015 - 14:11

  18. Valley Entrepreneurs' Network (VEN) Monthly Network Meeting

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

    VEN Monthly Network Meeting Valley Entrepreneurs' Network (VEN) Monthly Network Meeting WHEN: Mar 05, 2015 5:30 PM - 7:00 PM WHERE: Anthony's At the Delta North Paseo De Onate, Española, NM CATEGORY: Community INTERNAL: Calendar Login Event Description An evening of exciting enterprise networking with like-minded entrepreneurs. For more information, contact Alejandro, VEN Coordinator, at (505) 410-0959

  19. West Valley Demonstration Project Unique Remote Operations

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

    Path to Success Beyond Phase 1 Facility Disposition Bryan Bower U.S. Department of Energy West Valley Demonstration Project September 14, 2016 www.energy.gov/EM 2 Approved for Public Release; Further Dissemination Unlimited Where we are . . . www.energy.gov/EM 3 Approved for Public Release; Further Dissemination Unlimited and where we are going. 4 Decision Making Process Phase 2 Decommissioning (Decisions made by 2020) Phase 2 Decisions Decisions for disposition of remaining facilities : 

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

    SciTech Connect (OSTI)

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

    1983-01-01

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

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

    SciTech Connect (OSTI)

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

    1982-08-01

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

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

    SciTech Connect (OSTI)

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

    1986-01-01

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

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

    SciTech Connect (OSTI)

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

    1983-05-01

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

  4. Santa Clara Valley Transportation Authority and San Mateo County Transit

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

    District -- Fuel Cell Transit Buses: Evaluation Results | Department of Energy Santa Clara Valley Transportation Authority and San Mateo County Transit District -- Fuel Cell Transit Buses: Evaluation Results Santa Clara Valley Transportation Authority and San Mateo County Transit District -- Fuel Cell Transit Buses: Evaluation Results This report provides evaluation results for prototype fuel cell transit buses operating at Santa Clara Valley Transportation Authority in San Jose, California.

  5. Imperial Valley Renewable Energy Summit | Department of Energy

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

    Imperial Valley Renewable Energy Summit Imperial Valley Renewable Energy Summit The Energy Department's Geothermal Technologies Office presented on major funding initiatives in 2015 at the eighth annual Imperial Valley Renewable Energy Summit, in southern California in March. Laura Garchar - science and technology policy fellow through DOE's Institute for Science and Education at Oak Ridge, Tennessee (ORISE) - presented. click below for the full presentation IVRES Presentation_Garchar.pdf (2 MB)

  6. NERSC Hosts 50 Enthusiastic Computer Science Students from Dougherty Valley

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

    High Hosts 50 Enthusiastic Computer Science Students from Dougherty Valley High NERSC Hosts 50 Enthusiastic Computer Science Students from Dougherty Valley High May 31, 2016 A group of 50 enthusiastic computer science students from Dougherty Valley High School in San Ramon, CA visited NERSC May 26, where they toured the computer room and participated in lively discussions about the facility and how supercomputers work. They asked great questions, such as "In the future, will there be

  7. Santa Clara Valley Transportation Authority and San Mateo County Transit

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

    District | Department of Energy Santa Clara Valley Transportation Authority and San Mateo County Transit District Santa Clara Valley Transportation Authority and San Mateo County Transit District Fuel Cell Transit Buses: Preliminary Evaluation Results vta_prelim_eval_results.pdf (1.04 MB) More Documents & Publications Santa Clara Valley Transportation Authority and San Mateo County Transit District -- Fuel Cell Transit Buses: Evaluation Results VTA, SamTrans Look into Future with Bus

  8. West Valley Demolition Marks Important Accomplishment for EM | Department

    Energy Savers

    of Energy Demolition Marks Important Accomplishment for EM West Valley Demolition Marks Important Accomplishment for EM June 13, 2013 - 12:00pm Addthis Workers demolish the West Valley Demonstration Project's largest and most complex ancillary facility. Workers demolish the West Valley Demonstration Project's largest and most complex ancillary facility. Demolition work is shown in February 2013. Demolition work is shown in February 2013. Demolition continues in April 2013 with removal of

  9. Micro-Earthquake At Long Valley Caldera Geothermal Area (Stroujkova...

    Open Energy Information (Open El) [EERE & EIA]

    Micro-Earthquake At Long Valley Caldera Geothermal Area (Stroujkova & Malin, 2001) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity:...

  10. Valley wins 2015 Science Bowl | The Ames Laboratory

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

    Valley Seated (l-r) Ryan Thompson, Charles Napier, Gabriel Mintzer. Back row (l-r): coach Nate Speichinger, Sunita Kolareth, Arun Velamuri and Ames Laboratory Director Adam...

  11. Sulphur Springs Valley EC- Residential Energy Efficiency Rebate

    Energy.gov [DOE]

    Sulphur Springs Valley Electric Cooperative (SSVEC) is a Touchstone Energy Cooperative. SSVEC's residential rebate program offers a $500 rebate for the installation of 15 SEER or higher electric...

  12. Multispectral Imaging At Buffalo Valley Hot Springs Area (Laney...

    Open Energy Information (Open El) [EERE & EIA]

    Laney, 2005) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Multispectral Imaging At Buffalo Valley Hot Springs Area (Laney, 2005) Exploration...

  13. Recency Of Faulting And Neotechtonic Framework In The Dixie Valley...

    Open Energy Information (Open El) [EERE & EIA]

    Photography At Beowawe Hot Springs Area (Wesnousky, Et Al., 2003) Aerial Photography At Brady Hot Springs Area (Wesnousky, Et Al., 2003) Aerial Photography At Dixie Valley...

  14. Conceptual Model At Dixie Valley Geothermal Area (Okaya & Thompson...

    Open Energy Information (Open El) [EERE & EIA]

    Okaya & Thompson, 1985) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Conceptual Model At Dixie Valley Geothermal Area (Okaya & Thompson, 1985)...

  15. Valley County, Montana: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Fort Peck, Montana Frazer, Montana Glasgow, Montana Nashua, Montana Opheim, Montana St. Marie, Montana Retrieved from "http:en.openei.orgwindex.php?titleValleyCounty,Montana...

  16. Valley Brook, Oklahoma: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley Brook, Oklahoma: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 35.4020066, -97.4814258 Show Map Loading map... "minzoom":false,"mappin...

  17. Indian Valley Hot Springs Geothermal Area | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Exploration Activity Page Technique Activity Start Date Activity End Date Reference Material Isotopic Analysis- Fluid At Indian Valley Hot Springs Geothermal Area (1990) Isotopic...

  18. Silicon Valley Clean Tech Alliance | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Alliance Jump to: navigation, search Name: Silicon Valley Clean Tech Alliance Address: Box 1855 Place: Cupertino, California Zip: 95015 Region: Bay Area Website:...

  19. Magnetotellurics At Long Valley Caldera Geothermal Area (Nordquist...

    Open Energy Information (Open El) [EERE & EIA]

    Long Valley Caldera Using Magnetotelluric and Time-domain Electromagnetic Measurements Stephen K. Park, Carlos Torres-Verdin (1988) A Systematic Approach to the Interpretation of...

  20. Static Temperature Survey At Long Valley Caldera Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    beneath the resurgent dome. References Christopher Farrar, Jacob DeAngelo, Colin Williams, Frederick Grubb, Shaul Hurwitz (2010) Temperature Data From Wells in Long Valley...

  1. Columbine Valley, Colorado: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Columbine Valley, Colorado: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 39.6010988, -105.032206 Show Map Loading map......

  2. Spokane Valley, Washington: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    city in Spokane County, Washington.1 Utility Companies in Spokane Valley, Washington Modern Electric Water Company References US Census Bureau Incorporated place and minor...

  3. Gas Flux Sampling At Lualualei Valley Area (Thomas, 1986) | Open...

    Open Energy Information (Open El) [EERE & EIA]

    1986) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Gas Flux Sampling At Lualualei Valley Area (Thomas, 1986) Exploration Activity Details...

  4. Prescott Valley, Arizona: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Page Edit with form History Prescott Valley, Arizona: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 34.6100243, -112.315721 Show Map Loading...

  5. Development Wells At Long Valley Caldera Geothermal Area (Associates...

    Open Energy Information (Open El) [EERE & EIA]

    Associates, 1987) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Development Wells At Long Valley Caldera Geothermal Area (Associates, 1987)...

  6. Long Valley Caldera Geothermal and Magmatic Systems | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Magmatic Systems Abstract Long Valley Caldera in eastern California has been explored for geothermal resources since the 1960s. Early shallow exploration wells (<300m) were located...

  7. Technical Geologic Overview of Long Valley Caldera for the Casa...

    Open Energy Information (Open El) [EERE & EIA]

    Project Abstract Long Valley Caldera in eastern California has been explored for geothermal resources since the 1960s. Early exploration wells (<300m) were drilled around...

  8. Cumberland Valley Electric Cooperative- Energy Efficiency and Renewable Energy Program

    Energy.gov [DOE]

    Cumberland Valley Electric offers a number of programs to promote energy conservation. This program offers rebates for air source heat pumps, building insulation (including windows and doors), and...

  9. Magic Valley Electric Coop Inc | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Twitter: @magicvalleyEC Facebook: https:www.facebook.comMagicValleyEC?refts Outage Hotline: 1-866-225-5683 Outage Map: www.magicvalley.coopmapoutag...

  10. Silicon Valley Power and Oklahoma Municipal Power Authority Win...

    Energy.gov (indexed) [DOE]

    today recognized the Oklahoma Municipal Power Authority (OMPA) and Silicon Valley Power (SVP) of Santa Clara, California, as the winners of the 2014 Public Power Wind Awards. ...

  11. Mercury Vapor At Lualualei Valley Area (Thomas, 1986) | Open...

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Mercury Vapor At Lualualei Valley Area (Thomas, 1986) Exploration Activity Details Location...

  12. Chemical Logging At Dixie Valley Geothermal Area (Los Alamos...

    Open Energy Information (Open El) [EERE & EIA]

    Dixie Valley Geothermal Area (Los Alamos National Laboratory, NM, 2002) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Chemical Logging At Dixie...

  13. Deformation of the Long Valley Caldera, California: Inferences...

    Open Energy Information (Open El) [EERE & EIA]

    of the Long Valley Caldera, California: Inferences from Measurements from 1988 to 2001 Jump to: navigation, search OpenEI Reference LibraryAdd to library Journal Article:...

  14. Pioneer Valley Resource Recovery Biomass Facility | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Facility Pioneer Valley Resource Recovery Sector Biomass Facility Type Municipal Solid Waste Location Hampden County, Massachusetts Coordinates 42.1172314, -72.6624209...

  15. Pioneer Valley Photovoltaics Cooperative aka PV Squared | Open...

    Open Energy Information (Open El) [EERE & EIA]

    Photovoltaics Cooperative aka PV Squared Jump to: navigation, search Name: Pioneer Valley Photovoltaics Cooperative (aka PV Squared) Place: New Britain, Connecticut Zip: 6051...

  16. Grass Valley, California: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley, California Connect Renewable Energy Inc DayStar Solar LLC formerly International Energy Trading LLC Environmental Capital Group LLC SMA America References US Census...

  17. Compound and Elemental Analysis At Buffalo Valley Hot Springs...

    Open Energy Information (Open El) [EERE & EIA]

    Location Buffalo Valley Hot Springs Area Exploration Technique Compound and Elemental Analysis Activity Date Usefulness not indicated DOE-funding Unknown Notes Geochemical...

  18. Isotopic Analysis- Fluid At Indian Valley Hot Springs Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    Details Location Indian Valley Hot Springs Geothermal Area Exploration Technique Isotopic Analysis- Fluid Activity Date 1990 Usefulness not indicated DOE-funding Unknown...

  19. Isotopic Analysis- Fluid At Sierra Valley Geothermal Area (1990...

    Open Energy Information (Open El) [EERE & EIA]

    Activity Details Location Sierra Valley Geothermal Area Exploration Technique Isotopic Analysis- Fluid Activity Date 1990 Usefulness not indicated DOE-funding Unknown...

  20. Isotopic Analysis At Buffalo Valley Hot Springs Area (Laney,...

    Open Energy Information (Open El) [EERE & EIA]

    Activity Details Location Buffalo Valley Hot Springs Area Exploration Technique Isotopic Analysis- Fluid Activity Date Usefulness not indicated DOE-funding Unknown Notes...

  1. Office of Enterprise Assessments Review of the West Valley Demonostrat...

    Energy Savers

    ... West Valley, LLC CRAD Criteria and Review Approach ... EMCBC Environmental Management Consolidated Business ... Head End Vent HLW High Level Waste I&C Instrumentation and ...

  2. Ground Gravity Survey At Walker Lake Valley Area (Shoffner, Et...

    Open Energy Information (Open El) [EERE & EIA]

    N. Hinz, A. Sabin, M. Lazaro, S. Alm (2010) Understanding Fault Characteristics And Sediment Depth For Geothermal Exploration Using 3D Gravity Inversion In Walker Valley, Nevada...

  3. Bear Valley Springs, California: Energy Resources | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Valley Springs, California: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 35.1591307, -118.6284245 Show Map Loading map......

  4. Data Acquisition-Manipulation At Valley Of Ten Thousand Smokes...

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Data Acquisition-Manipulation At Valley Of Ten Thousand Smokes Region Area (Kodosky & Keith,...

  5. Yellowstone Valley Electric Cooperative- Residential/Commercial Efficiency Rebate Program

    Energy.gov [DOE]

    The Yellowstone Valley Electric Cooperative offers rebates to residential and commercial members for purchasing energy efficient add-on heat pumps, geothermal heat pumps, water heaters, dishwashers...

  6. Indian Valley Hospital Space Heating Low Temperature Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    Hospital Space Heating Low Temperature Geothermal Facility Jump to: navigation, search Name Indian Valley Hospital Space Heating Low Temperature Geothermal Facility Facility Indian...

  7. Modeling-Computer Simulations At Long Valley Caldera Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    (2003) The Mechanics of Unrest at Long Valley Caldera, California. 2. Constraining the Nature of the Source Using Geodetic and Micro-Gravity Data John O. Langbein (2003)...

  8. DOE - Office of Legacy Management -- Tennessee Valley Authority...

    Office of Legacy Management (LM)

    Valley Authority, Muscle Shoals Alabama; Circa 1987 AL.01-3 - TVA Letter; Siegel to Mott; Subject: Comments on Radiological Report; May 15, 1980. Attachment: Preliminary Survey...

  9. Makaha Valley, Hawaii: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Makaha Valley, Hawaii: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 21.4822222, -158.2038889 Show Map Loading map... "minzoom":false,"mappin...

  10. EA-239 Aroostook Valley Electric Company | Department of Energy

    Energy.gov (indexed) [DOE]

    EA-239 Aroostook Valley Electric Company (25.57 KB) More Documents & Publications EA-193 Energy Atlantic, LLC EA-380 Freeport Commodities EA-249 Exelon Generation Company LLC

  11. Water Sampling At Dixie Valley Geothermal Area (Wood, 2002) ...

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Dixie Valley Geothermal Area (Wood, 2002) Exploration Activity Details...

  12. Water Sampling At Valley Of Ten Thousand Smokes Region Area ...

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Valley Of Ten Thousand Smokes Region Area (Keith, Et Al., 1992)...

  13. Water Sampling At Little Valley Area (Wood, 2002) | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Little Valley Area (Wood, 2002) Exploration Activity Details Location...

  14. Water Sampling At Long Valley Caldera Geothermal Area (Sorey...

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Long Valley Caldera Geothermal Area (Sorey, Et Al., 1991) Exploration...

  15. Water Sampling At Buffalo Valley Hot Springs Area (Laney, 2005...

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Buffalo Valley Hot Springs Area (Laney, 2005) Exploration Activity Details...

  16. Water geochemistry study of Indian Wells Valley, Inyo and Kern...

    Open Energy Information (Open El) [EERE & EIA]

    Final report Jump to: navigation, search OpenEI Reference LibraryAdd to library Report: Water geochemistry study of Indian Wells Valley, Inyo and Kern Counties, California....

  17. Water Sampling At Dixie Valley Geothermal Area (Kennedy & Soest...

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Dixie Valley Geothermal Area (Kennedy & Soest, 2006) Exploration Activity...

  18. Water Sampling At Long Valley Caldera Geothermal Area (Evans...

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Long Valley Caldera Geothermal Area (Evans, Et Al., 2002) Exploration...

  19. Water Sampling At Lualualei Valley Area (Thomas, 1986) | Open...

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Lualualei Valley Area (Thomas, 1986) Exploration Activity Details Location...

  20. Water Sampling At Long Valley Caldera Geothermal Area (Goff,...

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Long Valley Caldera Geothermal Area (Goff, Et Al., 1991) Exploration...

  1. Elkhorn Valley Public Schools Wind Project | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    - Yankton School District Wind Project

  2. Mesa County Valley Wind Project | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    - Yankton School District Wind Project

  3. USD 384 Blue Valley Wind Project | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    - Yankton School District Wind Project

  4. Cherry Valley Elementary School Wind Project | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    - Yankton School District Wind Project

  5. Development Wells At Long Valley Caldera Geothermal Area (Suemnicht...

    Open Energy Information (Open El) [EERE & EIA]

    the geothermal power plants. References Gene A. Suemnicht, Michael L. Sorey, Joseph N. Moore, Robert Sullivan (2007) The Shallow Hydrothermal System of Long Valley Caldera,...

  6. Exploratory Boreholes At Long Valley Caldera Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    the hydrothermal flow system. References Gene A. Suemnicht, Michael L. Sorey, Joseph N. Moore, Robert Sullivan (2007) The Shallow Hydrothermal System of Long Valley Caldera,...

  7. Geothermometry At Long Valley Caldera Geothermal Area (Farrar...

    Open Energy Information (Open El) [EERE & EIA]

    stages of hydrothermal activity, flow, and recharge in the Long Valley caldera groundwater system. Fluids were sampled from LVEW during flow testing in May 2000, July 2000,...

  8. Remote Sensing For Geothermal Exploration Over Buffalo Valley...

    Open Energy Information (Open El) [EERE & EIA]

    and spectral resolution of the data allows for the identification of carbonate, sulfate, silica and clay minerals. Quartz- and clay-rich regions of Buffalo Valley were...

  9. Golden Valley Electric Association- Sustainable Natural Alternative Power (SNAP) Program

    Office of Energy Efficiency and Renewable Energy (EERE)

    Golden Valley Electric Association's (GVEA) SNAP program encourages members to install renewable energy generators and connect them to the utility's electrical distribution system by offering an...

  10. Isotopic Analysis- Fluid At Long Valley Caldera Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    Long Valley Caldera Geothermal Area (Taylor & Gerlach, 1983) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Isotopic Analysis- Fluid At Long...

  11. Teleseismic-Seismic Monitoring At Dixie Valley Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    H. Ibser, Jennifer Lewicki, B. Mack. Kennedy, Michael Swyer (2013) Egs Exploration Methodology Project Using the Dixie Valley Geothermal System, Nevada, Status Update Ileana M....

  12. Egs Exploration Methodology Project Using the Dixie Valley Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    Egs Exploration Methodology Project Using the Dixie Valley Geothermal System, Nevada, Status Update Jump to: navigation, search OpenEI Reference LibraryAdd to library Conference...

  13. Conceptual Model At Dixie Valley Geothermal Area (Iovenitti,...

    Open Energy Information (Open El) [EERE & EIA]

    Unknown Exploration Basis This project is being conducted to develop exploration methodology for EGS development. Dixie Valley is being used as a calibration site for the EGS...

  14. Numerical Modeling At Dixie Valley Geothermal Area (Iovenitti...

    Open Energy Information (Open El) [EERE & EIA]

    H. Ibser, Jennifer Lewicki, B. Mack. Kennedy, Michael Swyer (2013) Egs Exploration Methodology Project Using the Dixie Valley Geothermal System, Nevada, Status Update Christoph...

  15. Gas Flux Sampling At Dixie Valley Geothermal Area (Iovenitti...

    Open Energy Information (Open El) [EERE & EIA]

    H. Ibser, Jennifer Lewicki, B. Mack. Kennedy, Michael Swyer (2013) Egs Exploration Methodology Project Using the Dixie Valley Geothermal System, Nevada, Status Update Additional...

  16. Geothermal Literature Review At Dixie Valley Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    Unknown Exploration Basis This project is being conducted to develop exploration methodology for EGS development. Dixie Valley is being used as a calibration site for the EGS...

  17. Ground Magnetics At Dixie Valley Geothermal Area (Iovenitti,...

    Open Energy Information (Open El) [EERE & EIA]

    H. Ibser, Jennifer Lewicki, B. Mack. Kennedy, Michael Swyer (2013) Egs Exploration Methodology Project Using the Dixie Valley Geothermal System, Nevada, Status Update Additional...

  18. Geographic Information System At Dixie Valley Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    Unknown Exploration Basis This project is being conducted to develop exploration methodology for EGS development. Dixie Valley is being used as a calibration site for the EGS...

  19. Waterville Valley, New Hampshire: Energy Resources | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Waterville Valley, New Hampshire: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 43.9500695, -71.4995204 Show Map Loading map......

  20. Conceptual Model At Long Valley Caldera Geothermal Area (Farrar...

    Open Energy Information (Open El) [EERE & EIA]

    Long Valley caldera groundwater system based on detailed integration of results from pump tests, fluid level monitoring, temperature logging, and fluid samplinganalysis of the...

  1. Static Temperature Survey At Long Valley Caldera Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    Long Valley caldera groundwater system based on detailed integration of results from pump tests, fluid level monitoring, temperature logging, and fluid samplinganalysis of the...

  2. Inhomogeneity smoothing using density valley formed by ion beam...

    Office of Scientific and Technical Information (OSTI)

    in an ion-beam inertial confinement fusion pellets by numerical simulation. The simulation results show that the radiation energy is confined in the density valley, and the ...

  3. Apple Valley, California: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Apple Valley, California: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 34.5008311, -117.1858759 Show Map Loading map... "minzoom":false,"map...

  4. Exploration and Development at Dixie Valley, Nevada- Summary...

    Open Energy Information (Open El) [EERE & EIA]

    at Dixie Valley, Nevada- Summary of Doe Studies Authors David D. Blackwell, Richard P. Smith and Maria C. Richards Conference Thirty-Second Workshop on Geothermal Reservoir...

  5. Isotopic Analysis At Long Valley Caldera Geothermal Area (Smith...

    Open Energy Information (Open El) [EERE & EIA]

    Smith & Suemnicht, 1991) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Isotopic Analysis At Long Valley Caldera Geothermal Area (Smith &...

  6. Field Mapping At Dixie Valley Geothermal Area (Smith, Et Al....

    Open Energy Information (Open El) [EERE & EIA]

    Smith, Et Al., 2001) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Field Mapping At Dixie Valley Geothermal Area (Smith, Et Al., 2001)...

  7. DOE Releases Request for Information for the West Valley Demonstration...

    Office of Environmental Management (EM)

    Request for Information for the West Valley Demonstration Project Technical Services to Develop a Supplemental Environmental Impact Statement Procurement DOE Releases Request for ...

  8. Direct-Current Resistivity At Lualualei Valley Area (Thomas,...

    Open Energy Information (Open El) [EERE & EIA]

    Direct-Current Resistivity At Lualualei Valley Area (Thomas, 1986) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Direct-Current Resistivity At...

  9. Direct-Current Resistivity Survey At Lualualei Valley Area (Thomas...

    Open Energy Information (Open El) [EERE & EIA]

    Direct-Current Resistivity Survey At Lualualei Valley Area (Thomas, 1986) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Direct-Current...

  10. Modeling-Computer Simulations At Dixie Valley Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Modeling-Computer Simulations At Dixie Valley Geothermal Area (Wannamaker, Et Al., 2006) Exploration...

  11. Modeling-Computer Simulations At Long Valley Caldera Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Modeling-Computer Simulations At Long Valley Caldera Geothermal Area (Pribnow, Et Al., 2003)...

  12. Modeling-Computer Simulations At Long Valley Caldera Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Modeling-Computer Simulations At Long Valley Caldera Geothermal Area (Newman, Et Al., 2006) Exploration...

  13. Modeling-Computer Simulations At Long Valley Caldera Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Modeling-Computer Simulations At Long Valley Caldera Geothermal Area (Farrar, Et Al., 2003) Exploration...

  14. Modeling-Computer Simulations At Long Valley Caldera Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Modeling-Computer Simulations At Long Valley Caldera Geothermal Area (Tempel, Et Al., 2011) Exploration...

  15. Hyperspectral Imaging At Dixie Valley Geothermal Area (Kennedy...

    Open Energy Information (Open El) [EERE & EIA]

    Dixie Valley Geothermal Area Exploration Technique Hyperspectral Imaging Activity Date 2003 - 2003 Usefulness useful DOE-funding Unknown Exploration Basis This Study was...

  16. Direct-Current Resistivity Survey At Dixie Valley Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    Valley Geothermal Area Exploration Technique Direct-Current Resistivity Survey Activity Date 2003 - 2003 Usefulness useful DOE-funding Unknown Exploration Basis The Goals of this...

  17. Longwall mining thrives in Colorado's North Fork Valley

    SciTech Connect (OSTI)

    Buchsbaum, L.

    2006-08-15

    With mining units poised for record-setting capacity and rail service restored, these mines in Colorado's North Fork valley are ready to cut coal. 4 photos.

  18. Compound and Elemental Analysis At Fish Lake Valley Area (Deymonaz...

    Open Energy Information (Open El) [EERE & EIA]

    ENERGYGeothermal Home Exploration Activity: Compound and Elemental Analysis At Fish Lake Valley Area (Deymonaz, Et Al., 2008) Exploration Activity Details Location Fish...

  19. Poudre Valley REA- Residential Energy Efficiency Rebate Program

    Energy.gov [DOE]

    Poudre Valley Rural Electric Association (PVREA), a Touchstone Energy Cooperative, offers residential energy efficiency rebate programs for qualified residential heat pumps, air conditioners...

  20. Isotopic Analysis- Gas At Long Valley Caldera Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    Through 30 September Activity T. Winnett, Cathy J. Janik (1986) Isotopic Composition of Carbon in Fluids from the Long Valley Geothermal System, California, In- Proceedings of...

  1. Clean Cities: Clean Cities Coachella Valley Region coalition

    Alternative Fuels and Advanced Vehicles Data Center

    achievements, and from DOE for outstanding public outreach. Through his leadership, hydrogen fueling infrastructure and vehicles were also implemented in the Coachella Valley. In...

  2. Multispectral Imaging At Dixie Valley Geothermal Area (Pal &...

    Open Energy Information (Open El) [EERE & EIA]

    effort of remote sensing specialists and industry sponsored by the U.S. Department of Energy. They are using Hyperspectral data for mineralogy mapping of outcrops. Dixie valley...

  3. Radar At Dixie Valley Geothermal Area (Foxall & Vasco, 2008)...

    Open Energy Information (Open El) [EERE & EIA]

    DOE-funding Unknown Exploration Basis This study was conducted to image ground subsidence over the Dixie Valley Geothermal Field Notes An interferometric synthetic aperture...

  4. Summary Of Recent Research In Long Valley Caldera, California...

    Open Energy Information (Open El) [EERE & EIA]

    Caldera, California Abstract Since 1978, volcanic unrest in the form of earthquakes and ground deformation has persisted in the Long Valley caldera and adjacent parts of the...

  5. Oro Valley, Arizona: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Oro Valley, Arizona: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 32.3909071, -110.966488 Show Map Loading map... "minzoom":false,"mappingse...

  6. Conceptual Model At Dixie Valley Geothermal Area (Reed, 2007...

    Open Energy Information (Open El) [EERE & EIA]

    mean residence times, large surface areas, and adjacent damage zones that provide permeability. The tracers were injected in the center of the Dixie Valley Geothermal Field and...

  7. Numerical Modeling At Dixie Valley Geothermal Area (McKenna ...

    Open Energy Information (Open El) [EERE & EIA]

    Numerical Modeling At Dixie Valley Geothermal Area (McKenna & Blackwell, 2003) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Numerical Modeling...

  8. Reservoir-Scale Fracture Permeability in the Dixie Valley, Nevada...

    Open Energy Information (Open El) [EERE & EIA]

    Reservoir-Scale Fracture Permeability in the Dixie Valley, Nevada, Geothermal Field Jump to: navigation, search OpenEI Reference LibraryAdd to library Conference Paper:...

  9. Verdigris Valley Electric Cooperative- Residential Energy Efficiency Rebate Program

    Energy.gov [DOE]

    Verdigris Valley Electric Cooperative (VVEC) offers rebates for residential customers who purchase energy efficient home equipment. Rebates are available for room air conditioners, electric water...

  10. Hydrothermal Alteration Mineral Studies in Long Valley, In- Proceeding...

    Open Energy Information (Open El) [EERE & EIA]

    in the Long Valley Caldera; Mammoth Lakes, CA; 07151986 Published Lawrence Berkeley Laboratory, 1986 DOI Not Provided Check for DOI availability: http:crossref.org...

  11. Magnetotelluric Studies In Grass Valley, Nevada | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    soundings was initiated in 1974 in Green Valley, Nevada, as part of the Lawrence Berkeley Laboratory's major study of techniques for geothermal exploration in north central...

  12. Geochemistry of Thermal Waters in Long Valley, Mono County, California...

    Open Energy Information (Open El) [EERE & EIA]

    Long Valley, California, issue sodium bicarbonate-chloride waters containing 1000-1420 mgl of dissolved solids. Thermal waters of sodium bicarbonate-chloride composition are...

  13. Geographic Information System At Dixie Valley Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    Nash & D., 1997) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Geographic Information System At Dixie Valley Geothermal Area (Nash & D., 1997)...

  14. Hyperspectral Imaging At Dixie Valley Geothermal Area (Nash ...

    Open Energy Information (Open El) [EERE & EIA]

    Nash & D., 1997) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Hyperspectral Imaging At Dixie Valley Geothermal Area (Nash & D., 1997)...

  15. A Fresh Take on Groundwater at Amargosa Valley Open House

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

    September 25, 2012 A Fresh Take on Groundwater at Amargosa Valley Open House From drilling ... Interactive stations on Monitoring, Drilling, Sampling, Modeling, Protection and ...

  16. Poudre Valley REA- Commercial Energy Efficiency Rebate Program

    Energy.gov [DOE]

    Poudre Valley Rural Electric Association (PVREA), a Touchstone Energy Cooperative, offers a variety of lighting rebates to commercial customers. Rebates are available on commercial lighting...

  17. Canton Valley, Connecticut: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Canton Valley, Connecticut: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 41.8342645, -72.8917676 Show Map Loading map......

  18. Enterprise Assessments Review of the West Valley Demonstration...

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

    Review of the West Valley Demonstration Project Site Fire ... Office of Environment, Safety and Health Assessments ... In this report, EA uses the terms "deficiencies, findings, ...

  19. North Valley, New Mexico: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley, New Mexico: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 35.1733771, -106.6233591 Show Map Loading map... "minzoom":false,"mappingse...

  20. South Valley, New Mexico: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley, New Mexico: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 35.0100487, -106.6780809 Show Map Loading map... "minzoom":false,"mappingse...

  1. Voluntary Protection Program Onsite Review, West Valley Demonstration...

    Energy.gov (indexed) [DOE]

    8 Evaluation to determine whether West Valley Demonstration Project is continuing to perform at a level deserving DOE-VPP Star recognition. The Team conducted its review during...

  2. Aerial Photography At Dixie Valley Geothermal Area (Helton, Et...

    Open Energy Information (Open El) [EERE & EIA]

    analyze faults in southern Dixie Valley. The study was done for the Department of the Navy Geothermal Program Office's NAS Fallon Geothermal Exploration Project. Notes High...

  3. Silicon Valley Technology Centre SVTC | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search Name: Silicon Valley Technology Centre (SVTC) Place: San Jose, California Zip: 915134 Product: Development foundry which offers start-up and...

  4. Roaring Fork Valley- Energy Smart Colorado Renewable Energy Rebate Program

    Energy.gov [DOE]

    Residents of Roaring Fork Valley and Eagle, Gunnison, Lake, and Summit Counties are eligible for energy efficiency and renewable energy assistance, rebates, and financing through the Energy Smart...

  5. Roaring Fork Valley- Energy Smart Colorado Energy Efficiency Rebate Program

    Energy.gov [DOE]

    Residents of Roaring Fork Valley and Eagle, Gunnison, Lake, and Summit Counties are eligible for energy efficiency and renewable energy assistance, rebates, and financing through the Energy Smart...

  6. Ground Gravity Survey At Dixie Valley Geothermal Area (Schaefer...

    Open Energy Information (Open El) [EERE & EIA]

    m of alluvial and lacustrine deposits. The model also indicated that the central depression of the valley is offset to the west closer to the Stillwater Range. References...

  7. Injectivity Test At Dixie Valley Geothermal Area (Benoit, Et...

    Open Energy Information (Open El) [EERE & EIA]

    navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Injectivity Test At Dixie Valley Geothermal Area (Benoit, Et Al., 2000) Exploration Activity Details...

  8. Flow Test At Dixie Valley Geothermal Area (Desormier, 1987) ...

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Dixie Valley Geothermal Area (Desormier, 1987) Exploration Activity Details Location...

  9. Flow Test At Long Valley Caldera Geothermal Area (Farrar, Et...

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Long Valley Caldera Geothermal Area (Farrar, Et Al., 2003) Exploration Activity...

  10. Injectivity Test At Long Valley Caldera Geothermal Area (Farrar...

    Open Energy Information (Open El) [EERE & EIA]

    navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Injectivity Test At Long Valley Caldera Geothermal Area (Farrar, Et Al., 2003) Exploration Activity...

  11. Injectivity Test At Long Valley Caldera Geothermal Area (Morin...

    Open Energy Information (Open El) [EERE & EIA]

    navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Injectivity Test At Long Valley Caldera Geothermal Area (Morin, Et Al., 1993) Exploration Activity...

  12. Dixie Valley - Geothermal Development in the Basin and Range...

    Open Energy Information (Open El) [EERE & EIA]

    Not Provided DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for Dixie Valley - Geothermal Development in the Basin and Range Citation Dixie...

  13. Chino Valley, Arizona: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley, Arizona: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 34.7575227, -112.4537809 Show Map Loading map... "minzoom":false,"mappingservi...

  14. Mohave Valley, Arizona: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley, Arizona: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 34.9330585, -114.5888533 Show Map Loading map... "minzoom":false,"mappingservi...

  15. Paradise Valley, Arizona: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Valley, Arizona: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 33.5311541, -111.9426452 Show Map Loading map... "minzoom":false,"mappingservi...

  16. Yucca Valley, California: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Yucca Valley, California: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 34.1141743, -116.432235 Show Map Loading map... "minzoom":false,"mapp...

  17. DOE - Office of Legacy Management -- MonValley

    Office of Legacy Management (LM)

    ... at the Monument Valley, Arizona, DOE Legacy Waste Site-2008 Pilot Study Status Report ... Arizona, and Shiprock, New Mexico, DOE Legacy Waste Sites-2007 Pilot Study Status ...

  18. Ground water in Animas Valley, Hidalgo County, New Mexico | Open...

    Open Energy Information (Open El) [EERE & EIA]

    to library Report: Ground water in Animas Valley, Hidalgo County, New Mexico Author H. O. Reeder Published New Mexico State Engineer's Office, 1957 Report Number Technical...

  19. Seismotectonics of the Coso Range-Indian Wells Valley region...

    Open Energy Information (Open El) [EERE & EIA]

    Jeffrey R. Unruh, Egill Hauksson, Francis C. Monastero, Robert J. Twiss and Jonathan C. Lewis. 2002. Seismotectonics of the Coso Range-Indian Wells Valley region, California:...

  20. Guadalupe Valley Electric Cooperative- Residential Energy Efficiency Rebate Programs

    Energy.gov [DOE]

    Guadalupe Valley Electric Cooperative (GVC) offers a variety of incentives to help residential customers save energy. Rebates are available for energy efficient new homes and improvements to...

  1. Isotopic Analysis At Long Valley Caldera Geothermal Area (Evans...

    Open Energy Information (Open El) [EERE & EIA]

    search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Isotopic Analysis At Long Valley Caldera Geothermal Area (Evans, Et Al., 2002) Exploration Activity Details...

  2. Compound and Elemental Analysis At Long Valley Caldera Geothermal...

    Open Energy Information (Open El) [EERE & EIA]

    Compound and Elemental Analysis At Long Valley Caldera Geothermal Area (Evans, Et Al., 2002) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity:...

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

    SciTech Connect (OSTI)

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

    2002-07-01

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

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

    Energy.gov [DOE]

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

  5. Engineering assessment of inactive uranium mill tailings: Monument Valley Site, Monument Valley, Arizona

    SciTech Connect (OSTI)

    Not Available

    1981-10-01

    Ford, Bacon and Davis Utah Inc. has reevalated the Monument Valley site in order to revise the March 1977 engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings at Monument Valley, Arizona. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and radiation exposure of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas released from the 1.1 million tons of tailings at the Monument Valley site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation also are factors. The four alternative actions presented in this engineering assessment range from millsite decontamination with the addition of 3 m of stabilization cover material (Option I), to removal of the tailings to remote disposal sites and decontamination of the tailings site (Options II through IV). Cost estimates for the four options range from about $6,600,000 for stabilization in-place, to about $15,900,000 for disposal at a distance of about 15 mi. Three principal alternatives for reprocessing the Monument Valley tailings were examined: heap leaching; Treatment at an existing mill; and reprocessing at a new conventional mill constructed for tailings reprocessing. The cost of the uranium recovery is economically unattractive.

  6. VWZ-0011- In the Matter of West Valley Nuclear Services Co., Inc.

    Energy.gov [DOE]

    This decision considers a Motion to Dismiss filed by West Valley Nuclear Services, Inc. (West Valley) on May 18, 1999. In its Motion, West Valley seeks the partial dismissal of a Complaint filed...

  7. DOE Tour of Zero Floorplans: Glendale by Kalamazoo Valley Habitat for

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

    Humanity | Department of Energy Glendale by Kalamazoo Valley Habitat for Humanity DOE Tour of Zero Floorplans: Glendale by Kalamazoo Valley Habitat for Humanity DOE Tour of Zero Floorplans: Glendale by Kalamazoo Valley Habitat for Humanity

  8. West Valley Site History, Cleanup Status, and Role of the West...

    Office of Environmental Management (EM)

    Site History, Cleanup Status, and Role of the West Valley Citizen Task Force West Valley Site History, Cleanup Status, and Role of the West Valley Citizen Task Force Presentation...

  9. VWZ-0010- In the Matter of West Valley Nuclear Services Co., Inc.

    Energy.gov [DOE]

    This decision considers a “Motion to Dismiss” filed by West Valley Nuclear Services, Inc. (West Valley) on April 27, 1999. In its Motion, West Valley seeks the dismissal of a Complaint filed by...

  10. Preliminary Notice of Violation, West Valley Nuclear Services- EA-1999-09

    Energy.gov [DOE]

    Issued to West Valley Nuclear Services, related to a High-Level Radioactive Waste Contamination Event at the West Valley Demonstration Project,(EA-1999-09)

  11. Slim Holes At Gabbs Valley Area (DOE GTP) | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Gabbs Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Slim Holes At Gabbs Valley Area (DOE GTP) Exploration Activity...

  12. LiDAR At Gabbs Valley Area (DOE GTP) | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Gabbs Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: LiDAR At Gabbs Valley Area (DOE GTP) Exploration Activity Details...

  13. Core Analysis At Gabbs Valley Area (DOE GTP) | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Gabbs Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Gabbs Valley Area (DOE GTP) Exploration Activity...

  14. Density Log at Gabbs Valley Area (DOE GTP) | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Density Log at Gabbs Valley Area (DOE GTP) Exploration Activity Details Location Gabbs Valley...

  15. 2-M Probe At Gabbs Valley Area (DOE GTP) | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: 2-M Probe At Gabbs Valley Area (DOE GTP) Exploration Activity Details Location Gabbs Valley...

  16. Over Core Stress At Gabbs Valley Area (DOE GTP) | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Stress At Gabbs Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Over Core Stress At Gabbs Valley Area (DOE GTP) Exploration...

  17. VWA-0033- In the Matter of Gretencord v. West Valley Nuclear Services Co., Inc.

    Office of Energy Efficiency and Renewable Energy (EERE)

    This decision considers a Complaint filed by John L. Gretencord (Gretencord) against West Valley Nuclear Services, Inc. (West Valley) under the Department of Energy's (DOE) Contractor Employee...

  18. Gas Sampling At Gabbs Valley Area (DOE GTP) | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Gas Sampling At Gabbs Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Gas Sampling At Gabbs Valley Area (DOE GTP)...

  19. Gas Sampling At Gabbs Valley Area (DOE GTP) | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Gas Sampling At Gabbs Valley Area (DOE GTP) (Redirected from Water-Gas Samples At Gabbs Valley Area (DOE GTP)) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home...

  20. Reflection Survey At Fish Lake Valley Area (DOE GTP) | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Reflection Survey At Fish Lake Valley Area (DOE GTP) Exploration...

  1. Field Mapping At Fish Lake Valley Area (DOE GTP) | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Field Mapping At Fish Lake Valley Area (DOE GTP) Exploration Activity Details Location Fish Lake Valley Area...

  2. Density Log at Fish Lake Valley Area (DOE GTP) | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Density Log at Fish Lake Valley Area (DOE GTP) Exploration...

  3. Thermal Gradient Holes At Fish Lake Valley Area (DOE GTP) | Open...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Thermal Gradient Holes At Fish Lake Valley Area (DOE GTP)...

  4. Slim Holes At Fish Lake Valley Area (Deymonaz, Et Al., 2008)...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (Deymonaz, Et Al., 2008) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Slim Holes At Fish Lake Valley Area (Deymonaz, Et...

  5. Core Analysis At Fish Lake Valley Area (DOE GTP) | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Fish Lake Valley Area (DOE GTP) Exploration...

  6. Flow Test At Fish Lake Valley Area (DOE GTP) | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Fish Lake Valley Area (DOE GTP) Exploration Activity...

  7. Resistivity Log At Fish Lake Valley Area (DOE GTP) | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Resistivity Log At Fish Lake Valley Area (DOE GTP) Exploration...

  8. Thermal And-Or Near Infrared At Fish Lake Valley Area (Deymonaz...

    Open Energy Information (Open El) [EERE & EIA]

    Fish Lake Valley Area (Deymonaz, Et Al., 2008) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Thermal And-Or Near Infrared At Fish Lake Valley...

  9. Field Mapping At Gabbs Valley Area (DOE GTP) | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Field Mapping At Gabbs Valley Area (DOE GTP) Exploration Activity Details Location Gabbs Valley...

  10. EA-1980: Spar Canyon-Round Valley Access Road System Improvements...

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

    80: Spar Canyon-Round Valley Access Road System Improvements, Custer County, Idaho EA-1980: Spar Canyon-Round Valley Access Road System Improvements, Custer County, Idaho Summary...

  11. DOE Issues Draft Request for Proposals for the West Valley Demonstrati...

    Energy Savers

    West Valley Demonstration Project Supplemental Environmental Impact Statement Support Service DOE Issues Draft Request for Proposals for the West Valley Demonstration Project ...

  12. DOE Issues Final Request for Proposals for the West Valley Demonstrati...

    Energy Savers

    Valley Demonstration Project Supplemental Environmental Impact Statement Support Service DOE Issues Final Request for Proposals for the West Valley Demonstration Project ...

  13. Flow Test At Gabbs Valley Area (DOE GTP) | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Flow Test At Gabbs Valley Area (DOE GTP) Exploration Activity Details Location Gabbs Valley Area...

  14. TFC-0004- In the Matter of Tri-Valley CARES

    Energy.gov [DOE]

    Tri-Valley CARES filed an Appeal from a determination that the National Nuclear Security Administration (NNSA) issued on June 2, 2010. In that determination, NNSA denied in part a request for information that Tri-Valley CARES had submitted on September 8, 2008, pursuant to the Freedom of Information Act (FOIA), 5 U.S.C. § 552.

  15. Hoopa Valley Small Scale Hydroelectric Feasibility Project

    SciTech Connect (OSTI)

    Curtis Miller

    2009-03-22

    This study considered assessing the feasibility of developing small scale hydro-electric power from seven major tributaries within the Hoopa Valley Indian Reservation of Northern California (http://www.hoopa-nsn.gov/). This study pursued the assessment of seven major tributaries of the Reservation that flow into the Trinity River. The feasibility of hydropower on the Hoopa Valley Indian Reservation has real potential for development and many alternative options for project locations, designs, operations and financing. In order to realize this opportunity further will require at least 2-3 years of intense data collection focusing on stream flow measurements at multiple locations in order to quantify real power potential. This also includes on the ground stream gradient surveys, road access planning and grid connectivity to PG&E for sale of electricity. Imperative to this effort is the need for negotiations between the Hoopa Tribal Council and PG&E to take place in order to finalize the power rate the Tribe will receive through any wholesale agreement that utilizes the alternative energy generated on the Reservation.

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

    SciTech Connect (OSTI)

    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

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

    SciTech Connect (OSTI)

    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).

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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)

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

    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.

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

    SciTech Connect (OSTI)

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

    1980-01-01

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

  4. West Valley Melter Draft Waste Evaluation Released for Public Comment |

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

    Department of Energy Melter Draft Waste Evaluation Released for Public Comment West Valley Melter Draft Waste Evaluation Released for Public Comment March 11, 2011 - 12:00pm Addthis Media Contact Bill Taylor (513) 246-0539 william.taylor@emcbc.doe.gov West Valley, New York - The U.S. Department of Energy today released a Draft Waste Incidental to Reprocessing (WIR) Evaluation of a vitrification melter at the West Valley Demonstration Project (WVDP) for review and comment by the public,

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

    SciTech Connect (OSTI)

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

    2013-07-01

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

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

    SciTech Connect (OSTI)

    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.

  7. DOE - Office of Legacy Management -- South Valley Superfund Site...

    Office of Legacy Management (LM)

    Energy is one of the PRPS because of the Atomic Energy Commissions ownership of an industrial facility in the South Valley from 1951-1967. Also see Documents Related to South...

  8. Silicon Valley Power- Solar Electric Buy Down Program

    Energy.gov [DOE]

    Silicon Valley Power (SVP) offers incentives for the installation of new grid-connected solar electric (photovoltaic, or PV) systems. Incentive levels will step down over the life of the program...

  9. Maple Valley, Washington: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    This article is a stub. You can help OpenEI by expanding it. Maple Valley is a city in King County, Washington. It falls under Washington's 8th congressional district.12...

  10. Isotopic Analysis At Valley Of Ten Thousand Smokes Region Area...

    Open Energy Information (Open El) [EERE & EIA]

    Date Usefulness not indicated DOE-funding Unknown References T. E. C. Keith, J. M. Thompson, R. A. Hutchinson, L. D. White (1992) Geochemistry Of Waters In The Valley Of Ten...

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

    Open Energy Information (Open El) [EERE & EIA]

    Coop, Inc Jump to: navigation, search Name: Central Valley Elec Coop, Inc Place: New Mexico Phone Number: (575) 746-3571 Website: cvecoop.org Outage Hotline: (575) 746-3571...

  12. Compound and Elemental Analysis At Dixie Valley Geothermal Area...

    Open Energy Information (Open El) [EERE & EIA]

    to be related to characteristics of the fluid at Dixie Valley such as a relatively high pH and low concentrations of sulfate and chloride. References Scott A. Wood (2002) Behavior...

  13. Lower Valley Energy Inc (Wyoming) | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Energy Inc Place: Wyoming Phone Number: 800 882 5875 Website: www.lvenergy.com Facebook: https:www.facebook.comLowerValleyEnergy Outage Hotline: 800 882 5875 References:...

  14. Chippewa Valley Ethanol Company CVEC | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

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    Open Energy Information (Open El) [EERE & EIA]

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    Open Energy Information (Open El) [EERE & EIA]

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

  17. Improving Reactor Performance Rose Montgomery The Tennessee Valley...

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

    Improving Reactor Performance Rose Montgomery The Tennessee Valley Authority Mark Uhran Oak Ridge National Laboratory April 9, 2013 CASL-U-2013-0034-001 CASL-U-2013-0034-001 ...

  18. Mill Valley, California: Energy Resources | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Hide Map This article is a stub. You can help OpenEI by expanding it. Mill Valley is a city in Marin County, California. It falls under California's 6th...

  19. West Valley Demonstration Project Transportation Emergency Management Program

    Office of Environmental Management (EM)

    West Valley Demonstration Project Transportation Emergency Management Program Independent Oversight Review of the Office of Independent Oversight and Performance Assurance September 2000 OVERSIGHT Table of Contents EXECUTIVE SUMMARY ................................................................... 1 1.0 INTRODUCTION ........................................................................... 4 2.0 RESULTS .........................................................................................

  20. Silicon Valley Solar Inc SV Solar | Open Energy Information

    Open Energy Information (Open El) [EERE & EIA]

    Solar Inc SV Solar Jump to: navigation, search Name: Silicon Valley Solar Inc (SV Solar) Place: Santa Clara, California Zip: 95051 Sector: Solar Product: A US-based manufacturer of...