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Sample records for rico electric pwr

  1. 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.

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

    SciTech Connect (OSTI)

    Bailey, W.J.

    1987-05-01

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

  3. Keosauqua Municipal Light & Pwr | Open Energy Information

    Open Energy Info (EERE)

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

  4. University of Puerto Rico (Universidad de Puerto Rico) | OSTI...

    Office of Scientific and Technical Information (OSTI)

    Social Media University of Puerto Rico's You Tube Channel University of Puerto Rico on Facebook Follow the University of Puerto Rico on Twitter Bioprocess Development and Training ...

  5. 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 ...

  6. 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).

  7. 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, ...

  8. Photovoltaics on Landfills in Puerto Rico

    SciTech Connect (OSTI)

    Salasovich, J.; Mosey, G.

    2011-01-01

    cost of electricity. Currently, PREPA has an average electric rate of $0.119/kWh. Based on past electric rate increases in Puerto Rico and other islands in the Caribbean, this rate could increase to $0.15/kWh or higher in a relatively short amount of time. In the coming years, increasing electrical rates and increased necessity for clean power will continue to improve the feasibility of implementing solar PV systems at these sites.

  9. Puerto Rico- Green Energy Fund

    Office of Energy Efficiency and Renewable Energy (EERE)

    In July 2010, Puerto Rico enacted two important laws aimed at accelerating Puerto Rico's adaptation of renewable energy and to reduce the island's reliance on fossil fuels. This is especially...

  10. Universidad del Turabo (Puerto Rico) | Department of Energy

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

    Universidad del Turabo (Puerto Rico) Universidad del Turabo (Puerto Rico) Team roster: Harry Bonilla, Mechanical Engineering; Coral D. Colón, Electrical Engineering; Gabriel Cotto, Mechanical Engineering; Miguel Díaz, Mechanical Engineering; Eduardo Fenollal, Mechanical Engineering; Jorge W. Flores, Mechanical Engineering; Leishla González, Graphic Design (International School of Design and Architecture); Viany González, Industrial Engineering; Rubén I. Maldonado, Mechanical Engineering;

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

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

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

    Open Energy Info (EERE)

    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:...

  13. Northeast Missouri El Pwr Coop | Open Energy Information

    Open Energy Info (EERE)

    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...

  14. Sam Rayburn Municipal Pwr Agny | Open Energy Information

    Open Energy Info (EERE)

    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. Red River Valley Coop Pwr Assn | Open Energy Information

    Open Energy Info (EERE)

    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...

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

    Open Energy Info (EERE)

    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...

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

    Open Energy Info (EERE)

    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...

  18. ORISE Resources: Puerto Rico Equal Access Program

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

    Puerto Rico Equal Access Program: Programa de Igualdad de Acceso para Puerto Rico: Recursos de Informacin del VIHSIDA de la Biblioteca Nacional de Medicina Workbook The Oak...

  19. 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

  20. 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

  1. 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)

  2. ELECTRIC

    Office of Legacy Management (LM)

    ELECTRIC cdrtrokArJclaeT 3 I+ &i, y$ \I &OF I*- j< t j,fci..- ir )(yiT !E-li, ( \-,v? Cl -p/4.4 RESEARCH LABORATORIES EAST PITTSBURGH, PA. 8ay 22, 1947 Mr. J. Carrel Vrilson General ?!!mager Atomic Qxzgy Commission 1901 Constitution Avenue Kashington, D. C. Dear Sir: In the course of OUT nuclenr research we are planning to study the enc:ri;y threshold anti cross section for fission. For thib program we require a s<>piAroted sample of metallic Uranium 258 of high purity. A

  3. Other: Universidad de Puerto Rico - Carribean Affordable Solar...

    Office of Scientific and Technical Information (OSTI)

    Universidad de Puerto Rico - Carribean Affordable Solar House Citation Details Title: Universidad de Puerto Rico - Carribean Affordable Solar House

  4. Commonwealth of Puerto Rico Energy Affairs Administration …...

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

    Commonwealth of Puerto Rico Energy Affairs Administration - Energy Efficiency and ... of Puerto Rico Energy Affairs Administration - Energy Efficiency and Conservation ...

  5. 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.

  6. Arizona Electric Pwr Coop Inc | Open Energy Information

    Open Energy Info (EERE)

    Facebook: https:www.facebook.compagesArizonas-GT-Cooperatives347352335037?refts Outage Hotline: (520) 586-3631 References: EIA Form EIA-861 Final Data File for 2010...

  7. Rushmore Electric Pwr Coop Inc | Open Energy Information

    Open Energy Info (EERE)

    MRO NERC MRO Yes Activity Transmission Yes Activity Buying Transmission Yes Activity Wholesale Marketing Yes This article is a stub. You can help OpenEI by expanding it. Utility...

  8. Lessons Learned from the Puerto Rico Battery Energy Storage System

    SciTech Connect (OSTI)

    BOYES, JOHN D.; DE ANA, MINDI FARBER; TORRES, WENCESLANO

    1999-09-01

    The Puerto Rico Electric Power Authority (PREPA) installed a distributed battery energy storage system in 1994 at a substation near San Juan, Puerto Rico. It was patterned after two other large energy storage systems operated by electric utilities in California and Germany. The U.S. Department of Energy (DOE) Energy Storage Systems Program at Sandia National Laboratories has followed the progress of all stages of the project since its inception. It directly supported the critical battery room cooling system design by conducting laboratory thermal testing of a scale model of the battery under simulated operating conditions. The Puerto Rico facility is at present the largest operating battery storage system in the world and is successfully providing frequency control, voltage regulation, and spinning reserve to the Caribbean island. The system further proved its usefulness to the PREPA network in the fall of 1998 in the aftermath of Hurricane Georges. The owner-operator, PREPA, and the architect/engineer, vendors, and contractors learned many valuable lessons during all phases of project development and operation. In documenting these lessons, this report will help PREPA and other utilities in planning to build large energy storage systems.

  9. Puerto Rico - Renewable Energy Equipment Certification | Department...

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

    State Puerto Rico Program Type Equipment Certification Summary Certification of Photovoltaic Equipment EAA specifies that PV equipment must meet UL 1703 requirements, and...

  10. South Mississippi El Pwr Assn | Open Energy Information

    Open Energy Info (EERE)

    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...

  11. East Mississippi Elec Pwr Assn | Open Energy Information

    Open Energy Info (EERE)

    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 --...

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

    Open Energy Info (EERE)

    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...

  13. 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 ...

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

    Broader source: Energy.gov [DOE]

    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)...

  15. The Absent House: The Ecological House of Puerto Rico

    High Performance Buildings Database

    Vega Alta, PR The Absent House takes advantage of the benevolent climate of the humid tropics of Puerto Rico to play with the ambiguity of interior and exterior spaces. Main spaces include: a kitchenette and master bathroom suite; a guest tower with a bedroom, bathroom, and small library; an open, public pavilion for cooking, dining, and porch activities; a bathroom for visitors; an infrastructure pavilion for electricity and water consumption management; and an organic garden. The Patio of the Sun and the Stars, the most important s

  16. Center for Energy and Environmental Research, Puerto Rico, Sites...

    Office of Legacy Management (LM)

    Center for Energy and Environmental Research, Puerto Rico, Sites This fact sheet provides information about the Center for Energy and Environmental Research, Puerto Rico, Sites....

  17. Fermilab Today | University of Puerto Rico - Mayaguez Profile

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

    of Puerto Rico - Mayaguez HOME TOWN: Mayaguez, Puerto Rico MASCOT: Tarzan the Bulldog SCHOOL COLOR: Green PARTICLE PHYSICS COLLABORATIONS: CMS COLLABORATING AT FERMILAB SINCE:...

  18. 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.

  19. 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.

  20. 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...

  1. 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; ...

  2. Puerto Rico- Solar and Wind Contractor Certification

    Broader source: Energy.gov [DOE]

    In October 2008, the Energy Affairs Administration (EAA) of Puerto Rico adopted regulations for the certification of photovoltaic (PV) systems and installers in response to the passing of Act No....

  3. Puerto Rico- Excise Tax Exemption for Farmers

    Broader source: Energy.gov [DOE]

    In Puerto Rico, "bona fide farmers" are exempted from paying all types of excises for equipment, articles and objects whose operation depend solely on solar, wind, hydro or any other type of power,...

  4. Puerto Rico- Economic Development Incentives for Renewables

    Office of Energy Efficiency and Renewable Energy (EERE)

    The 2008 Economic Incentives for the Development of Puerto Rico Act (EIA) provides a wide array of tax credits and incentives that enable local and foreign companies dedicated to certain business...

  5. Puerto Rico: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Tons NA 2008 EIA Natural Gas Reserves 0 Cubic Meters (cu m) 144 2010 CIA World Factbook Oil Reserves 0 Barrels (bbl) 134 2010 CIA World Factbook Energy Maps featuring Puerto Rico...

  6. Center for Energy and Environmental Research, Puerto Rico, Sites

    SciTech Connect (OSTI)

    2015-12-16

    This fact sheet provides information about the Center for Energy and Environmental Research, Puerto Rico, Sites

  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. 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.

  10. Puerto Rico Regions | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    state, county, city, or district. For more information, please visit the Middle School Coach page. Puerto Rico Region Middle School Regional Puerto Rico Puerto Rico Middle School...

  11. Puerto Rico Regions | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    for your school's state, county, city, or district. For more information, please visit the High School Coach page. Puerto Rico Region High School Regional Puerto Rico Puerto Rico...

  12. Puerto Rico- Building Energy Code with Mandatory Solar Water Heating

    Broader source: Energy.gov [DOE]

    In 2009, the Governor of Puerto Rico provided assurance that Puerto Rico would update its building energy codes as part of the state's application for State Energy Program funds from the American...

  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. 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.

  15. 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.

  16. Recovery Act State Memos Puerto Rico

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

    Puerto Rico For questions about DOE's Recovery Act activities, please contact the DOE Recovery Act Clearinghouse: 1-888-DOE-RCVY (888-363-7289), Monday through Friday, 9 a.m. to 7 p.m. Eastern Time https://recoveryclearinghouse.energy.gov/contactUs.htm. All numbers and projects listed as of June 1, 2010 TABLE OF CONTENTS RECOVERY ACT SNAPSHOT................................................................................... 1 FUNDING ALLOCATION

  17. Consolidation and disposal of PWR fuel inserts

    SciTech Connect (OSTI)

    Wakeman, B.H. (Virginia Electric and Power Co., Glen Allen, VA (United States))

    1992-08-01

    Design and licensing of the Surry Power Station Independent Spent Fuel Storage Installation was initiated in 1982 by Virginia Power as part of a comprehensive strategy to increase spent fuel storage capacity at the Station. Designed to use large, metal dry storage casks, the Surry Installation will accommodate 84 such casks with a total storage capacity of 811 MTU of spent pressurized water reactor fuel assemblies. Virginia Power provided three storage casks for testing at the Idaho National Engineerinq Laboratory's Test Area North and the testing results have been published by the Electric Power Research Institute. Sixty-nine spent fuel assemblies were transported in truck casks from the Surry Power Station to Test Area North for testing in the three casks. Because of restrictions imposed by the cask testing equipment at Test Area North, the irradiated insert components stored in these fuel assemblies at Surry were removed prior to transport of the fuel assemblies. Retaining these insert components proved to be a problem because of a shortage of spent fuel assemblies in the spent fuel storage pool that did not already contain insert components. In 1987 Virginia Power contracted with Chem-Nuclear Systems, Inc. to process and dispose of 136 irradiated insert components consisting of 125 burnable poison rod assemblies, 10 thimble plugging devices and 1 part-length rod cluster control assembly. This work was completed in August and September 1987, culminating in the disposal at the Barnwell, SC low-level radioactive waste facility of two CNS 3-55 liners containing the consolidated insert components.

  18. 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.

  19. Using Electricity",,,"Electricity Consumption",,,"Electricity...

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

    . Total Electricity Consumption and Expenditures, 2003" ,"All Buildings* Using Electricity",,,"Electricity Consumption",,,"Electricity Expenditures" ,"Number of Buildings...

  20. 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.

  1. 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)

  2. Feasibility Study of Economics and Performance of Solar Photovoltaics in the Commonwealth of Puerto Rico

    SciTech Connect (OSTI)

    Salasovich, J.; Mosey, G.

    2011-03-01

    This report presents the results of an assessment of the technical and economic feasibility of deploying a photovoltaics (PV) system on brownfield sites in the Commonwealth of Puerto Rico. All of the assessed sites are landfills. The sites were assessed for possible PV installations. The cost, performance, and site impacts of different PV options were estimated. The economics of the potential systems were analyzed using an electric rate of $0.119/kWh and incentives offered by Puerto Rico and by the serving utility, PREPA. According to the site production calculations, the most cost-effective system in terms of return on investment is the thin-film fixed-tilt technology. The report recommends financing options that could assist in the implementation of such a system.

  3. BONUS, Puerto Rico, Decommissioned Reactor Site Fact Sheet

    Office of Legacy Management (LM)

    information about the Defense Decontamination and Decommissioning Program Boiling Nuclear Superheater (BONUS) reactor located northwest of Rincn, Puerto Rico. The site is...

  4. Puerto Rico Recovery Act State Memo | Department of Energy

    Energy Savers [EERE]

    Puerto Rico Recovery Act State Memo The American Recovery & Reinvestment Act (ARRA) is making a meaningful down payment on the nation's energy and environmental future. The ...

  5. 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.

  6. 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.

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

    SciTech Connect (OSTI)

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

    1982-12-01

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

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

    SciTech Connect (OSTI)

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

    1988-01-01

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

  9. CASL-U-2015-0132-000 Fausto Franceschini Westinghouse Electric Co. LLC,

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

    32-000 Fausto Franceschini Westinghouse Electric Co. LLC, March 26, 2015 AP1000 ® PWR Startup Core Modeling and Simulation with VERA-CS CASL-U-2015-0132-000 F Advances in Nuclear Fuel Management V (ANFM 2015) Hilton Head Island, South Carolina, USA, March 29 - April 1, 2015, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2015) © 2015 Westinghouse Electric Company LLC. All Rights Reserved. p. 1/12 AP1000 ® PWR STARTUP CORE MODELING AND SIMULATION WITH VERA-CS F. Franceschini

  10. Puerto Rico State Historic Preservation Programmatic Agreement | Department

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

    of Energy Puerto Rico State Historic Preservation Programmatic Agreement Puerto Rico State Historic Preservation Programmatic Agreement Fully executed programmatic agreement between DOE, State Energy Office and State Historic Preservation Office. state_historic_preservation_programmatic_agreement_pr.pdf (1.41 MB) More Documents & Publications Arizona State Historic Preservation Programmatic Agreement Delaware State Historic Preservation Programmatic Agreement Florida State Historic

  11. Puerto Rico`s EcoElectrica LNG/power project marks a project financing first

    SciTech Connect (OSTI)

    Lammers, R.; Taylor, S.

    1998-02-23

    On Dec. 15, 1997, Enron International and Kenetech Energy Services achieved financial close on the $670 million EcoElectrica liquefied natural gas terminal and cogeneration project proposed for Puerto Rico. The project involves construction of a liquefied natural gas terminal, cogeneration plant, and desalination unit on the southern coast of Puerto Rico, in the Penuelas/Guayanilla area. EcoElectrica will include a 500-mw, combined-cycle cogeneration power plant fueled mainly by LNG imported from the 400 MMcfd Atlantic LNG project on the island of Trinidad. Achieving financial close on a project of this size is always a time-consuming matter and one with a number of challenges. These challenges were increased by the unique nature of both the project and its financing--no project financing had ever before been completed that combined an LNG terminal and power plant. The paper discusses the project, financing details and challenges, key investment considerations, and integrated project prospects.

  12. 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.

  13. 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.

  14. PWR and BWR spent fuel assembly gamma spectra measurements

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

    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

  15. 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)

  16. 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 ...

  17. 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 ...

  18. Using Electricity",,,"Electricity Consumption",,,"Electricity...

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

    A. Total Electricity Consumption and Expenditures for All Buildings, 2003" ,"All Buildings Using Electricity",,,"Electricity Consumption",,,"Electricity Expenditures" ,"Number of...

  19. Electricity",,,"Electricity Consumption",,,"Electricity Expenditures...

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

    C9. Total Electricity Consumption and Expenditures, 1999" ,"All Buildings Using Electricity",,,"Electricity Consumption",,,"Electricity Expenditures" ,"Number of Buildings...

  20. Electricity",,,"Electricity Consumption",,,"Electricity Expenditures...

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

    DIV. Total Electricity Consumption and Expenditures by Census Division, 1999" ,"All Buildings Using Electricity",,,"Electricity Consumption",,,"Electricity Expenditures" ,"Number...

  1. 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.

  2. Puerto Rico- Tax Deduction for Solar Energy Systems

    Broader source: Energy.gov [DOE]

    Puerto Rico offers a 30% tax deduction (up to $1,500) for expenses incurred in the purchase and installation of solar equipment to heat water for residential use. "Solar equipment" is defined as ...

  3. Puerto Rico- Green Energy Fund Tier I Incentive Program

    Office of Energy Efficiency and Renewable Energy (EERE)

    With funding from Puerto Rico's Green Energy Fund, Tier I rebates are available for photovoltaic (PV) and wind systems up to and including 100 kW in capacity on a first-come, first-served basis. ...

  4. 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

  5. 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)

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

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

    SciTech Connect (OSTI)

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

    1982-09-01

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

  14. EIS-0511: Aguirre Offshore GasPort Project, Puerto Rico

    Broader source: Energy.gov [DOE]

    FERC prepared an EIS with 10 cooperating agencies, including DOE, for the proposed Aguirre Offshore GasPort Project. The proposal would include construction and operation of a marine LNG-receiving facility about 1 mile outside of Jobos Bay, near the towns of Salinas and Guayama, Puerto Rico, and a 4-mile subsea pipeline connecting to the Aguirre Plant in Salinas.

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

    SciTech Connect (OSTI)

    Bandy, R.; van Rooyen, D.

    1982-09-01

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

  16. Electric Vehicles

    Broader source: Energy.gov [DOE]

    This album contains a variety of all-electric, plug-in hybrid electric and fuel cell electric vehicles. For a full list of all electric vehicles visit the EV Everywhere website.

  17. Thermometry in the multirod burst test program. [PWR; BWR

    SciTech Connect (OSTI)

    Anderson, R.L.; Carr, K.R.; Kollie, T.G.

    1982-03-01

    A temperature measurement error analysis was performed for the Type S (0.25-mm-diam, bare-wire) and Type K (0.71-mm-diam, sheathed) thermocouple circuits used to measure the temperature of the Zircaloy-clad, electrically heated fuel-rod simulators in the Multirod Burst Test program (MRBT) at Oak Ridge National Laboratory (ORNL). An important objective of the MRBT program is to improve the understanding of the behavior of the Zircaloy cladding of nuclear fuel rods under conditions postulated for a large-break, loss-of-coolant accident. Eight categories of error sources were studied both analytically and experimentally: thermal shunting; electrical shuntng and leakage; thermocouple calibration; thermocouple decalibration in service; thermoelectric properties of thermocouple extension wire, plugs, and jacks; thermocouple reference junction; data acquisition system; and electrical noise.

  18. Geothermal Geodatabase for Rico Hot Springs Area and Lemon Hot Springs, Dolores and San Miguel Counties, Colorado

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

    Zehner, Richard

    2012-11-01

    Geothermal Geodatabase for Rico Hot Springs Area and Lemon Hot Springs, Dolores and San Miguel Counties, Colorado By Richard “Rick” Zehner Geothermal Development Associates Reno Nevada USA For Flint Geothermal LLC, Denver Colorado Part of DOE Grant EE0002828 2013 This is an ESRI geodatabase version 10, together with an ESRI MXD file version 10.2 Data is in UTM Zone 13 NAD27 projection North boundary: approximately 4,215,000 South boundary: approximately 4,160,000 West boundary: approximately 216,000 East boundary: approximately 245,000 This geodatabase was built to cover several geothermal targets developed by Flint Geothermal in 2012 during a search for high-temperature systems that could be exploited for electric power development. Several of the thermal springs have geochemistry and geothermometry values indicative of high-temperature systems. In addition, the explorationists discovered a very young Climax-style molybdenum porphyry system northeast of Rico, and drilling intersected thermal waters at depth. The datasets in the geodatabase are a mixture of public domain data as well as data collected by Flint Geothermal, now being made public. It is assumed that the user has internet access, for the mxd file accesses ESRI’s GIS servers. Datasets include: 1. Structural data collected by Flint Geothermal 2. Point information 3. Mines and prospects from the USGS MRDS dataset 4. Results of reconnaissance shallow (2 meter) temperature surveys 5. Air photo lineaments 6. Areas covered by travertine 7. Groundwater geochemistry 8. Land ownership in the Rico area 9. Georeferenced geologic map of the Rico Quadrangle, by Pratt et al. 10. Various 1:24,000 scale topographic maps

  19. 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.

  20. 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.

  1. Puerto Rico- Sales and Use Tax Exemption for Green Energy

    Office of Energy Efficiency and Renewable Energy (EERE)

    Puerto Rican law exempts from the sales and use tax solar electric equipment, associated accessories, and components used to produce electrical energy. Distributors or manufacturers must submit a...

  2. Decontamination and decommissioning of the Mayaguez (Puerto Rico) facility

    SciTech Connect (OSTI)

    Jackson, P.K.; Freemerman, R.L.

    1989-11-01

    On February 6, 1987 the US Department of Energy (DOE) awarded the final phase of the decontamination and decommissioning of the nuclear and reactor facilities at the Center for Energy and Environmental Research (CEER), in Mayaguez, Puerto Rico. Bechtel National, Inc., was made the decontamination and decommissioning (D and D) contractor. The goal of the project was to enable DOE to proceed with release of the CEER facility for use by the University of Puerto Rico, who was the operator. This presentation describes that project and lesson learned during its progress. The CEER facility was established in 1957 as the Puerto Rico Nuclear Center, a part of the Atoms for Peace Program. It was a nuclear training and research institution with emphasis on the needs of Latin America. It originally consisted of a 1-megawatt Materials Testing Reactor (MTR), support facilities and research laboratories. After eleven years of operation the MTR was shutdown and defueled. A 2-megawatt TRIGA reactor was installed in 1972 and operated until 1976, when it woo was shutdown. Other radioactive facilities at the center included a 10-watt homogeneous L-77 training reactor, a natural uranium graphite-moderated subcritical assembly, a 200KV particle accelerator, and a 15,000 Ci Co-60 irradiation facility. Support facilities included radiochemistry laboratories, counting rooms and two hot cells. As the emphasis shifted to non-nuclear energy technology a name change resulted in the CEER designation, and plans were started for the decontamination and decommissioning effort.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. Temperature estimates from zircaloy oxidation kinetics and microstructures. [PWR

    SciTech Connect (OSTI)

    Olsen, C.S.

    1982-10-01

    This report reviews state-of-the-art capability to determine peak zircaloy fuel rod cladding temperatures following an abnormal temperature excursion in a nuclear reactor, based on postirradiation metallographic analysis of zircaloy microstructural and oxidation characteristics. Results of a comprehensive literature search are presented to evaluate the suitability of available zircaloy microstructural and oxidation data for estimating anticipated reactor fuel rod cladding temperatures. Additional oxidation experiments were conducted to evaluate low-temperature zircaloy oxidation characteristics for postirradiation estimation of cladding temperature by metallographic examination. Results of these experiments were used to calculate peak cladding temperatures of electrical heater rods and nuclear fuel rods that had been subjected to reactor temperature transients. Comparison of the calculated and measured peak cladding temperatures for these rods indicates that oxidation kinetics is a viable technique for estimating peak cladding temperatures over a broad temperature range. However, further improvement in zircaloy microstructure technology is necessary for precise estimation of peak cladding temperatures by microstructural examination.

  9. Puerto Rico- Property Tax Exemption for Solar and Renewable Energy Equipment

    Broader source: Energy.gov [DOE]

    Puerto Rico provides a property tax exemption for all "solar powered material, equipment or accessory and renewable energy collection, storage, generation, distribution, and application equipment."...

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

    SciTech Connect (OSTI)

    Unterzuber, R.; Wright, J.B.

    1980-09-01

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

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

    SciTech Connect (OSTI)

    Unterzuber, R.

    1981-09-01

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

  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. 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.

  14. 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.

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

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

  16. 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.

  17. 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.

  18. 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.

  19. Viva Energía! Energy Department Partners with the University of Puerto Rico

    Broader source: Energy.gov [DOE]

    As one of the leading research institutions in Puerto Rico, the University of Puerto Rico has the largest and most diverse academic offerings on the Carribean island. And now -- thanks to funding from the Recovery Act -- the university is undertaking several energy conservation and renewable energy projects that will reduce the school's energy costs by $230,000 a year.

  20. Electric vehicles

    SciTech Connect (OSTI)

    Not Available

    1990-03-01

    Quiet, clean, and efficient, electric vehicles (EVs) may someday become a practical mode of transportation for the general public. Electric vehicles can provide many advantages for the nation's environment and energy supply because they run on electricity, which can be produced from many sources of energy such as coal, natural gas, uranium, and hydropower. These vehicles offer fuel versatility to the transportation sector, which depends almost solely on oil for its energy needs. Electric vehicles are any mode of transportation operated by a motor that receives electricity from a battery or fuel cell. EVs come in all shapes and sizes and may be used for different tasks. Some EVs are small and simple, such as golf carts and electric wheel chairs. Others are larger and more complex, such as automobile and vans. Some EVs, such as fork lifts, are used in industries. In this fact sheet, we will discuss mostly automobiles and vans. There are also variations on electric vehicles, such as hybrid vehicles and solar-powered vehicles. Hybrid vehicles use electricity as their primary source of energy, however, they also use a backup source of energy, such as gasoline, methanol or ethanol. Solar-powered vehicles are electric vehicles that use photovoltaic cells (cells that convert solar energy to electricity) rather than utility-supplied electricity to recharge the batteries. This paper discusses these concepts.

  1. RFA-14-0001- In the Matter of Commonwealth Oil Refining Company, Inc./Commonwealth of Puerto Rico

    Broader source: Energy.gov [DOE]

    On July 29, 2014, OHA approved a distribution plan submitted by the Commonwealth of Puerto Rico (Puerto Rico) to use approximately $1.2 million of petroleum overcharge funds held in escrow by the...

  2. 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

  3. 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.

  4. 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)

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

    SciTech Connect (OSTI)

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

    2009-05-01

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

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. PWR FLECHT SEASET 21-rod-bundle flow-blockage task: data and analysis report. NRC/EPRI/Westinghouse report No. 11, main report and appendices A-J

    SciTech Connect (OSTI)

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

    1982-09-01

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

  12. Electric Vehicles

    ScienceCinema (OSTI)

    Ozpineci, Burak

    2014-07-23

    Burak Ozpineci sees a future where electric vehicles charge while we drive them down the road, thanks in part to research under way at ORNL.

  13. Electrical Engineer

    Broader source: Energy.gov [DOE]

    Transmission Field Services is responsible for field switching operation and maintenance of Bonneville Power Administration's high-voltage electrical transmission system to provide safe, reliable,...

  14. Electrical Safety

    Office of Environmental Management (EM)

    Handbook that was originally issued in 1998, and revised in 2004. DOE handbooks are ... the National Fire Protection Association (NFPA) 70, the National Electrical Code (NEC), ...

  15. Electric Vehicles

    SciTech Connect (OSTI)

    Ozpineci, Burak

    2014-05-02

    Burak Ozpineci sees a future where electric vehicles charge while we drive them down the road, thanks in part to research under way at ORNL.

  16. Microsoft PowerPoint - MISO-SPP Market Impacts HydPwrConf 2014

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

    Slide 7 Southwestern Power Administration early afternoon operating day prior. Customer Electrical Demand Loads Transmission System ConditionsOutages Electrical System Operations ...

  17. Roles of electricity: Electric steelmaking

    SciTech Connect (OSTI)

    Burwell, C.C.

    1986-07-01

    Electric steel production from scrap metal continues to grow both in total quantity and in market share. The economics of electric-steel production in general, and of electric minimills in particular, seem clearly established. The trend towards electric steelmaking provides significant economic and competitive advantages for producers and important overall economic, environmental, and energy advantages for the United States at large. Conversion to electric steelmaking offers up to a 4-to-1 advantage in terms of the overall energy used to produce a ton of steel, and s similar savings in energy cost for the producer. The amount of old scrap used to produce a ton of steel has doubled since 1967 because of the use of electric furnaces.

  18. WINDExchange: Puerto Rico and U.S. Virgin Islands 50-Meter Wind Resource

    Wind Powering America (EERE)

    Map Maps & Data Printable Version Bookmark and Share Land-Based Utility-Scale Maps Potential Capacity Maps Offshore Wind Maps Community-Scale Maps Residential-Scale Maps Installed Capacity Maps Puerto Rico and U.S. Virgin Islands 50-Meter Wind Resource Map Puerto Rico and U.S. Virgin Islands wind resource map. Click on the image to view a larger version. Enlarge image This Puerto Rico wind map and the U.S. Virgin Islands wind map shows the wind resource at 50 meters. Download a printable

  19. Tapping Solar for Hot Water and Cheaper Bills for Puerto Rico | Department

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

    of Energy Solar for Hot Water and Cheaper Bills for Puerto Rico Tapping Solar for Hot Water and Cheaper Bills for Puerto Rico November 3, 2010 - 10:00am Addthis Stephen Graff Former Writer & editor for Energy Empowers, EERE What does this mean for me? 150 new jobs. 1200 solar water heaters installed. In Puerto Rico, solar water heaters have been popular for decades. But even with energy savings, not everyone can afford one. Through a new Recovery Act-funded program for the island, more

  20. Electric machine

    DOE Patents [OSTI]

    El-Refaie, Ayman Mohamed Fawzi; Reddy, Patel Bhageerath

    2012-07-17

    An interior permanent magnet electric machine is disclosed. The interior permanent magnet electric machine comprises a rotor comprising a plurality of radially placed magnets each having a proximal end and a distal end, wherein each magnet comprises a plurality of magnetic segments and at least one magnetic segment towards the distal end comprises a high resistivity magnetic material.

  1. Electric avenues

    SciTech Connect (OSTI)

    Stone, P.; Chang, A.

    1994-12-31

    Highly efficient electric drive technology developed originally for defense applications is being applied to the development of all electric shuttle buses for the San Jose International Airport. An innovative opportunity charging system using induction chargers will be incorporated to extend operation hours. The project, if successful, is expected to reduce pollution at the airport and generate jobs for displaced defense workers.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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)

  11. 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.

  12. Puerto Rico State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-10-01

    The Puerto Rico State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Puerto Rico. The profile is the result of a survey of NRC licensees in Puerto Rico. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Puerto Rico.

  13. Energy Transition Initiative: Island Energy Snapshot - Puerto Rico (Fact Sheet); NREL(National Renewable Energy Laboratory)

    SciTech Connect (OSTI)

    2015-03-01

    This profile provides a snapshot of the energy landscape of the Commonwealth of Puerto Rico - a U.S. territory located about 60 miles east of the Dominican Republic and directly west of the U.S. Virgin Islands.

  14. Electrical connector

    DOE Patents [OSTI]

    Dilliner, Jennifer L.; Baker, Thomas M.; Akasam, Sivaprasad; Hoff, Brian D.

    2006-11-21

    An electrical connector includes a female component having one or more receptacles, a first test receptacle, and a second test receptacle. The electrical connector also includes a male component having one or more terminals configured to engage the one or more receptacles, a first test pin configured to engage the first test receptacle, and a second test pin configured to engage the second test receptacle. The first test receptacle is electrically connected to the second test receptacle, and at least one of the first test pin and the second test pin is shorter in length than the one or more terminals.

  15. Puerto Rico Middle School Regional Science Bowl | U.S. DOE Office of

    Office of Science (SC) Website

    Science (SC) Puerto Rico Middle School Regional Science Bowl National Science Bowl® (NSB) NSB Home About Regional Competitions Rules, Forms, and Resources High School Regionals Middle School Regionals National Finals Volunteers Key Dates Frequently Asked Questions News Media Contact Us WDTS Home Contact Information National Science Bowl® U.S. Department of Energy SC-27/ Forrestal Building 1000 Independence Ave., SW Washington, DC 20585 E: Email Us Middle School Regionals Puerto Rico Middle

  16. Puerto Rico Regional High School Science Bowl | U.S. DOE Office of Science

    Office of Science (SC) Website

    (SC) Puerto Rico Regional High School Science Bowl National Science Bowl® (NSB) NSB Home About Regional Competitions Rules, Forms, and Resources High School Regionals Middle School Regionals National Finals Volunteers Key Dates Frequently Asked Questions News Media Contact Us WDTS Home Contact Information National Science Bowl® U.S. Department of Energy SC-27/ Forrestal Building 1000 Independence Ave., SW Washington, DC 20585 E: Email Us High School Regionals Puerto Rico Regional High

  17. Electrical Safety

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

    ... Fig. 1-1. Flow down of Electrical AHJ and worker responsibility. 3 DOE-HDBK-1092-2013 2.0 ... When equipment contains storage batteries, workers should be protected from the various ...

  18. 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.

  19. Electric generator

    DOE Patents [OSTI]

    Foster, Jr., John S.; Wilson, James R.; McDonald, Jr., Charles A.

    1983-01-01

    1. In an electrical energy generator, the combination comprising a first elongated annular electrical current conductor having at least one bare surface extending longitudinally and facing radially inwards therein, a second elongated annular electrical current conductor disposed coaxially within said first conductor and having an outer bare surface area extending longitudinally and facing said bare surface of said first conductor, the contiguous coaxial areas of said first and second conductors defining an inductive element, means for applying an electrical current to at least one of said conductors for generating a magnetic field encompassing said inductive element, and explosive charge means disposed concentrically with respect to said conductors including at least the area of said inductive element, said explosive charge means including means disposed to initiate an explosive wave front in said explosive advancing longitudinally along said inductive element, said wave front being effective to progressively deform at least one of said conductors to bring said bare surfaces thereof into electrically conductive contact to progressively reduce the inductance of the inductive element defined by said conductors and transferring explosive energy to said magnetic field effective to generate an electrical potential between undeformed portions of said conductors ahead of said explosive wave front.

  20. 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.

  1. 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.

  2. 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.

  3. 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

  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.

    2002-07-01

    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

  5. Electrically powered hand tool

    DOE Patents [OSTI]

    Myers, Kurt S.; Reed, Teddy R.

    2007-01-16

    An electrically powered hand tool is described and which includes a three phase electrical motor having a plurality of poles; an electrical motor drive electrically coupled with the three phase electrical motor; and a source of electrical power which is converted to greater than about 208 volts three-phase and which is electrically coupled with the electrical motor drive.

  6. 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.

  7. 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.

  8. 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.

  9. Final Report- Streamlined and Standardized Permitting and Interconnection Processes for Rooftop PV in Puerto Rico

    Office of Energy Efficiency and Renewable Energy (EERE)

    The plan to transform the rooftop photovoltaic (PV) market in Puerto Rico strives to create not only a standardized framework for PV deployment, but also streamlined and organized, lean permitting and interconnection processes where most residential and small commercial PV systems can be installed safely and quickly. Puerto Rico has regulations and requirements that limit our ability to adopt the expedited permitting recommendations proposed by Solar ABC and the Network for New Energy Choices. It is the intent of this proposal to identify, analyze, and provide best practices that overcomes these obstacles. The final deliverable of the proposal will be a holistic framework that ensures process predictability and standardization while dealing with rooftop PV market barriers. The plan may impact all of Puerto Rico (pop. 3.7 million), and bolster the incipient PV market in the Island.

  10. Puerto Rico and U.S. Virgin Islands Wind Resource Map at 50 meters

    Wind Powering America (EERE)

    % % % % % % % % % % % % % % % % % % % % % 19-JUN-2007 1.1.1 U.S. Department of Energy National Renewable Energy Laboratory Puerto Rico and U.S. Virgin Islands - 50 m Wind Power Mayaguez 20 0 20 40 60 80 100 Kilometers 20 0 20 40 60 Miles Ponce San Juan Charlotte Amalie Cruz Bay PUERTO RICO VIRGIN ISLANDS Wind Power Class 1 2 3 4 5 Resource Potential Poor Marginal Fair Good Excellent Wind Power Density at 50 m W/m 0 - 200 200 - 300 300 - 400 400 - 500 500 - 600 2 Wind Speed at 50 m m/s 0.0 - 5.9

  11. Electricity Monthly Update

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

    Contact Information and Staff The Electricity Monthly Update is prepared by the Electric Power Operations Team, Office of Electricity, Renewables and Uranium Statistics, U.S....

  12. Electricity Monthly Update

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

    Methodology and Documentation General The Electricity Monthly Update is prepared by the Electric Power Operations Team, Office of Electricity, Renewables and Uranium Statistics,...

  13. Electrical machine

    DOE Patents [OSTI]

    De Bock, Hendrik Pieter Jacobus; Alexander, James Pellegrino; El-Refaie, Ayman Mohamed Fawzi; Gerstler, William Dwight; Shah, Manoj Ramprasad; Shen, Xiaochun

    2016-06-21

    An apparatus, such as an electrical machine, is provided. The apparatus can include a rotor defining a rotor bore and a conduit disposed in and extending axially along the rotor bore. The conduit can have an annular conduit body defining a plurality of orifices disposed axially along the conduit and extending through the conduit body. The rotor can have an inner wall that at least partially defines the rotor bore. The orifices can extend through the conduit body along respective orifice directions, and the rotor and conduit can be configured to provide a line of sight along the orifice direction from the respective orifices to the inner wall.

  14. Electrical receptacle

    DOE Patents [OSTI]

    Leong, Robert

    1993-01-01

    The invention is a receptacle for a three prong electrical plug which has either a tubular or U-shaped grounding prong. The inventive receptacle has a grounding prong socket which is sufficiently spacious to prevent the socket from significantly stretching when a larger, U-shaped grounding prong is inserted into the socket, and having two ridges to allow a snug fit when a smaller tubular shape grounding prong is inserted into the socket. The two ridges are made to prevent the socket from expanding when either the U-shaped grounding prong or the tubular grounding prong is inserted.

  15. Electrical receptacle

    DOE Patents [OSTI]

    Leong, R.

    1993-06-22

    The invention is a receptacle for a three prong electrical plug which has either a tubular or U-shaped grounding prong. The inventive receptacle has a grounding prong socket which is sufficiently spacious to prevent the socket from significantly stretching when a larger, U-shaped grounding prong is inserted into the socket, and having two ridges to allow a snug fit when a smaller tubular shape grounding prong is inserted into the socket. The two ridges are made to prevent the socket from expanding when either the U-shaped grounding prong or the tubular grounding prong is inserted.

  16. 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.

  17. 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.

  18. 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

  19. 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.

  20. 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)

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

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

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  8. Technology Roadmap - Electric and Plug-in Hybrid Electric Vehicles...

    Open Energy Info (EERE)

    Roadmap - Electric and Plug-in Hybrid Electric Vehicles Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Technology Roadmap - Electric and Plug-in Hybrid Electric...

  9. Electric and Hybrid Electric Vehicle Sales: December 2010 - June...

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

    Electric and Hybrid Electric Vehicle Sales: December 2010 - June 2013 Sales data for various models of electric and hybrid electric vehicles from December 2010 through June 2013. ...

  10. Electric Drive Status and Challenges

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

    Leaf * 75 mile electric range * 80 kW electric drive * electric drive cost:1,600 Tesla Model S * 250 mile electric range * 270 kW electric drive * electric drive ...

  11. DOE handbook electrical safety

    SciTech Connect (OSTI)

    1998-01-01

    Electrical Safety Handbook presents the Department of Energy (DOE) safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety guidance and information for DOE installations to effect a reduction or elimination of risks associated with the use of electrical energy. The objectives of this handbook are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

  12. Electrical safety guidelines

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

    The Electrical Safety Guidelines prescribes the DOE safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety standards and guidance for DOE installations in order to affect a reduction or elimination of risks associated with the use of electrical energy. The objectives of these guidelines are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

  13. 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

  14. Electricity Monthly Update

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

    The Electric Power Sector comprises electricity-only and combined heat and power (CHP) plants within the North American Industrial Classification System 22 category whose...

  15. Electricity Monthly Update

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

    See all Electricity Reports Electricity Monthly Update With Data for November 2014 | Release Date: Jan. 26, 2015 | Next Release Date: Feb. 24, 2015 Previous Issues Issue:...

  16. Edison Electric Institute Update

    Broader source: Energy.gov [DOE]

    Presentation—given at the Fall 2011 Federal Utility Partnership Working Group (FUPWG) meeting—discusses the Edison Electric Institute (EEI) and the current electricity landscape.

  17. Ohio Electricity Restructuring Active

    Gasoline and Diesel Fuel Update (EIA)

    Other Links Ohio Electricity Profile Ohio Energy Profile Ohio Web Sites Acronyms for the ... Consumer education programs were available on the Ohio Electric Choice web site, through ...

  18. National Drive Electric Week

    Office of Energy Efficiency and Renewable Energy (EERE)

    Celebrate National Drive Electric Week with ways to make your all-electric or plug-in hybrid cars even greener!

  19. Electricity Monthly Update

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Update November 28, 2012 Map of Electric System Selected for Daily Peak Demand was replaced with the correct map showing Selected Wholesale Electricity and Natural Gas Locations....

  20. Electricity Monthly Update

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

    of electricity. End-use data is the first "data page" based on the assumption that information about retail electricity service is of greatest interest to a general...

  1. Electricity Restructuring by State

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Restructuring Status Status of Electricity Restructuring by State Data as of: September 2010 Next Release Date: None The map below shows information on the electric industry ...

  2. 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.

  3. 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)

  4. 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).

  5. 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.

  6. 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.

  7. Integrated electrical connector (Patent) | DOEPatents

    Office of Scientific and Technical Information (OSTI)

    Integrated electrical connector Title: Integrated electrical connector An electrical ... The opening is also smaller than the diameter of an electrically conductive contact pin. ...

  8. CASL - Westinghouse Electric Company

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

    Westinghouse Electric Company Cranberry Township, PA Westinghouse Electric Company provides fuel, services, technology, plant design and equipment for the commercial nuclear electric power industry. Westinghouse nuclear technology is helping to provide future generations with safe, clean and reliable electricity. Key Contributions Definition of CASL challenge problems Existing codes and expertise Data for validation Computatinoal fluid dynamics modeling and analysis Development of test stand for

  9. Electricity Monthly Update

    Gasoline and Diesel Fuel Update (EIA)

    Methodology and Documentation General The Electricity Monthly Update is prepared by the Electric Power Operations Team, Office of Electricity, Renewables and Uranium Statistics, U.S. Energy Information Administration (EIA), U.S. Department of Energy. Data published in the Electricity Monthly Update are compiled from the following sources: U.S. Energy Information Administration, Form EIA-826,"Monthly Electric Utility Sales and Revenues with State Distributions Report," U.S. Energy

  10. Baltimore Gas & Electric Company (Electric) - Residential Energy...

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

    AC: 30 Recycling RefrigeratorFreezer: 50 ACDehumidifier: 25 Summary The Baltimore Gas & Electric Company (BGE) offers rebates for residential customers to improve the...

  11. 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)

  12. Electric arc saw apparatus

    DOE Patents [OSTI]

    Deichelbohrer, Paul R [Richland, WA

    1986-01-01

    A portable, hand held electric arc saw has a small frame for supporting an electrically conducting rotary blade which serves as an electrode for generating an electric arc to erode a workpiece. Electric current is supplied to the blade by biased brushes and a slip ring which are mounted in the frame. A pair of freely movable endless belts in the form of crawler treads stretched between two pulleys are used to facilitate movement of the electric arc saw. The pulleys are formed of dielectric material to electrically insulate the crawler treads from the frame.

  13. Electric Efficiency Standard

    Broader source: Energy.gov [DOE]

    In December 2009, the Indiana Utility Regulatory Commission's (IURC) ordered utilities to establish demand-side management (DSM) electric savings goals leading to 2.0% reduction of electricity sa...

  14. Renewable Electricity Futures (Presentation)

    SciTech Connect (OSTI)

    Hand, M. M.

    2012-09-01

    This presentation summarizes findings of NREL's Renewable Electricity Futures study, published in June 2012. RE Futures investigated the challenges and impacts of achieving very high renewable electricity generation levels in the contiguous United States by 2050.

  15. Renewable Electricity Futures (Presentation)

    SciTech Connect (OSTI)

    Mai, T.

    2012-11-01

    This presentation summarizes findings of NREL's Renewable Electricity Futures study, published in June 2012. RE Futures investigated the challenges and impacts of achieving very high renewable electricity generation levels in the contiguous United States by 2050.

  16. Renewable Electricity Futures (Presentation)

    SciTech Connect (OSTI)

    Mai, T.

    2013-04-01

    This presentation summarizes findings of NREL's Renewable Electricity Futures study, published in June 2012. RE Futures investigated the challenges and impacts of achieving very high renewable electricity generation levels in the contiguous United States by 2050.

  17. Renewable Electricity Futures (Presentation)

    SciTech Connect (OSTI)

    Mai, T.

    2012-10-01

    This presentation library summarizes findings of NREL's Renewable Electricity Futures study, published in June 2012. RE Futures investigated the challenges and impacts of achieving very high renewable electricity generation levels in the contiguous United States by 2050.

  18. Electricity Monthly Update

    Gasoline and Diesel Fuel Update (EIA)

    sales volumes are presented as a proxy for end-use electricity consumption. Average Revenue per kWh by state Percent Change Per KWh map showing U.S. electric industry percent...

  19. Electricity Monthly Update

    Gasoline and Diesel Fuel Update (EIA)

    cheap price of natural gas reduced coals share of electricity production. Days of Burn Days of burn Coal capacity The average number of days of burn held at electric power...

  20. 2012 National Electricity Forum

    Broader source: Energy.gov [DOE]

    At the 2012 National Electricity Forum, held February 8-9, 2012 and jointly organized by DOE's Office of Electricity Delivery & Energy Reliability (OE) and the National Association of...

  1. Electricity Monthly Update

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

    End Use: August 2015 Retail ratesprices and consumption In this section, we look at what electricity costs and how much is purchased. Charges for retail electric service are based...

  2. Electric Power Monthly

    Gasoline and Diesel Fuel Update (EIA)

    Electric Power Monthly Data for January 2016 | Release Date: March 25, 2016 | Next ... Revisions made to the March 2016 Electric Power Monthly: March 30, 2016 Tables 2.8.A-B ...

  3. Table 2a. Electricity Consumption and Electricity Intensities...

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

    Administration Home Page Home > Commercial Buildings Home > Sq Ft Tables > Table 2a. Electricity Consumption per Sq Ft Table 2a. Electricity Consumption and Electricity...

  4. Panasonic Electric Works Ltd formerly Matsushita Electric Works...

    Open Energy Info (EERE)

    Electric Works Ltd (formerly Matsushita Electric Works) Place: Kadoma-shi, Osaka, Japan Zip: 571-8686 Product: Japanese manufacturer of mainly electric appliances including...

  5. Electric Power Research Institute

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

    Annual Technical Notes This appendix describes how the U.S. Energy Information Administration collects, estimates, and reports electric power data in the Electric Power Annual. Data Quality and Submission The Electric Power Annual (EPA) is prepared by the Office of Electricity, Renewables, and Uranium Statistics (ERUS), U.S. Energy Information Administration (EIA), U.S. Department of Energy (DOE). ERUS performs routine reviews of the data collection respondent frames, survey forms, and reviews

  6. EIA - Electricity Generating Capacity

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

    Electricity Generating Capacity Release Date: January 3, 2013 | Next Release: August 2013 Year Existing Units by Energy Source Unit Additions Unit Retirements 2011 XLS XLS XLS 2010 XLS XLS XLS 2009 XLS XLS XLS 2008 XLS XLS XLS 2007 XLS XLS XLS 2006 XLS XLS XLS 2005 XLS XLS XLS 2004 XLS XLS XLS 2003 XLS XLS XLS Source: Form EIA-860, "Annual Electric Generator Report." Related links Electric Power Monthly Electric Power Annual Form EIA-860 Source Data

  7. Electrical utilities relay settings

    SciTech Connect (OSTI)

    HACHE, J.M.

    1999-02-24

    This document contains the Hanford transmission and distribution system relay settings that are under the control of Electrical Utilities.

  8. Electric arc saw apparatus

    DOE Patents [OSTI]

    Deichelbohrer, P.R.

    1983-08-08

    A portable, hand-held electric arc saw apparatus comprising a small frame for supporting an electrically conducting rotary blade which serves as an electrode for generating an electric arc between the blade and a workpiece of opposite polarity. Electrically conducting means are provided on said frame for transmitting current to said blade. A pair of freely movable endless belts in the form of crawler treads are employed to facilitate movement of the apparatus relative to the workpiece.

  9. Electricity Monthly Update

    Gasoline and Diesel Fuel Update (EIA)

    End Use: June 2016 Retail rates/prices and consumption In this section, we look at what electricity costs and how much is purchased. Charges for retail electric service are based primarily on rates approved by state regulators. However, a number of states have allowed retail marketers to compete to serve customers and these competitive retail suppliers offer electricity at a market-based price. EIA does not directly collect retail electricity rates or prices. However, using data collected on

  10. EIA Electric Power Forms

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

    Electric Power Forms EIA Electric Power Forms Listing of Publicly Available and Confidential Data EIA's statistical surveys encompass each significant electric supply and demand activity in the United States. Most of the electric power survey forms resulting data elements are published, but respondent confidentiality is required. The chart below shows the data elements for each survey form and how each data element is treated in regard to confidentiality. Data Categories Data collection forms

  11. Florida's electric industry and solar electric technologies

    SciTech Connect (OSTI)

    Camejo, N.

    1983-12-01

    The Florida Electric Industry is in a process of diversifying its generation technology and its fuel mix. This is being done in an effort to reduce oil consumption, which in 1981 accounted for 46.5% of the electric generation by fuel type. This does not compare well with the rest of the nation where oil use is lower. New coal and nuclear units are coming on line, and probably more will be built in the near future. However, eventhough conservation efforts may delay their construction, new power plants will have to be built to accomodate the growing demand for electricity. Other alternatives being considered are renewable energy resources. The purpose of this paper is to present the results of a research project in which 10 electric utilities in Florida and the Florida Electric Power Coordinating Group rated six Solar Electric options. The Solar Electric options considered are: 1) Wind, 2) P.V., 3) Solar thermal-electric, 4) OTEC, 5) Ocean current, and 6) Biomass. The questionaire involved rating the economic and technical feasibility, as well as, the potential environmental impact of these options in Florida. It also involved rating the difficulty in overcoming institutional barriers and assessing the status of each option. A copy of the questionaire is included after the references. The combined capacity of the participating utilities represent over 90% of the total generating capacity in Florida. A list of the participating utilities is also included. This research was done in partial fulfillment for the Mater's of Science Degree in Coastal Zone Management. This paper is complementary to another paper (in these condensed conference proceedings) titled COASTAL ZONE ENERGY MANAGEMENT: A multidisciplinary approach for the integration of Solar Electric Systems with Florida's power generation system, which present a summary of the Master's thesis.

  12. DOE Electricity Advisory Committee

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

    Electricity Advisory Committee March 2015 1 MEMORANDUM TO: Honorable Patricia Hoffman, Assistant Secretary for Electricity Delivery and Energy Reliability, U.S. Department of Energy FROM: Electricity Advisory Committee (EAC) Richard Cowart, Chair DATE: March 27, 2015 RE: Recommendations on Smart Grid Research and Development Needs _________________________________________________________________________ Overview The Smart Grid is envisioned to provide the enhancements to ensure higher levels of

  13. Integrating Electricity Subsector

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

    Integrating Electricity Subsector Failure Scenarios into a Risk Assessment Methodology 3002001181 | DEC 2013 Program Leads Jason D. Christopher Technical Lead, Cyber Security Capabilities & Risk Management Department of Energy (DOE), Office of Electricity Delivery and Energy Reliability (OE) Annabelle Lee Senior Technical Executive, Cyber Security Electric Power Research Institute (EPRI) For more information on the DOE's cyber security risk management programs, please contact

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

    SciTech Connect (OSTI)

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

    2012-07-01

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

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

    SciTech Connect (OSTI)

    Hermann, O.W.

    2000-02-01

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

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

    SciTech Connect (OSTI)

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

    1985-11-01

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

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

    SciTech Connect (OSTI)

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

    2013-07-01

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

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

    SciTech Connect (OSTI)

    Viskanta, R.; Mohanty, A.K.

    1986-04-01

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

  19. Epcot Electric | Open Energy Information

    Open Energy Info (EERE)

    Epcot Electric Jump to: navigation, search Name: Epcot Electric Place: Texas Facebook: https:www.facebook.compagesEpcot-Electric108882552477023 References: EIA Form EIA-861...

  20. Lincoln Electric | Open Energy Information

    Open Energy Info (EERE)

    Electric Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner Lincoln Electric Developer Lincoln Electric Energy Purchaser Lincoln...

  1. EWEB- Solar Electric Program (Rebate)

    Broader source: Energy.gov [DOE]

    The Eugene Water & Electric Board's (EWEB) Solar Electric Program offers financial incentives for residential, nonprofit, and government customers that generate electricity solar photovoltaic...

  2. Aging Management Guideline for commercial nuclear power plants: Electrical switchgear. Final report

    SciTech Connect (OSTI)

    Toman, G.; Gazdzinski, R.; Schuler, K.

    1993-07-01

    This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant electrical switchgear important to license renewal. The latent of this AMG to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner which allows personnel responsible for performance analysis and maintenance, to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  3. INTEGRATED ELECTRIC DRIVE WITH HV2 MODULAR ELECTRIC MACHINE AND...

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

    ELECTRIC DRIVE WITH HV2 MODULAR ELECTRIC MACHINE AND SIC BASED POWER CONVERTERS INTEGRATED ELECTRIC DRIVE WITH HV2 MODULAR ELECTRIC MACHINE AND SIC BASED POWER CONVERTERS The Ohio ...

  4. Post-Service Examination of PWR Baffle Bolts, Part I. Examination and Test Plan

    SciTech Connect (OSTI)

    Leonard, Keith J.; Sokolov, Mikhail A.; Gussev, Maxim N.

    2015-04-30

    In support of extended service and current operations of the US nuclear reactor plants, the Oak Ridge National Laboratory (ORNL), through the Department of Energy (DOE), Light Water Reactor Sustainability (LWRS) Program, is coordinating with Ginna Nuclear Power Plant, The Westinghouse Electric Company, LLC, and ATI Consulting, the selective procurement of baffle bolts that were withdrawn from service in 2011 and currently stored on site at Ginna. The goal of this program is to perform detailed microstructural and mechanical property characterization of baffle former bolts following in-service exposures. This report outlines the selection criteria of the bolts and the techniques to be used in this study. The bolts available are the original alloy 347 steel fasteners used in holding the baffle plates to the baffle former structures within the lower portion of the pressurized water reactor vessel. Of the eleven possible bolts made available for this work, none were identified to have specific damage. The bolts, however, did show varying levels of breakaway torque required in their removal. The bolts available for this study varied in peak fluence (highest dose within the head of the bolt) between 9.9 and 27.8x1021 n/cm2 (E>1MeV). As no evidence for crack initiation was determined for the available bolts from preliminary visual examination, two bolts with the higher fluence values were selected for further post-irradiation examination. The two bolts showed different breakaway torque levels necessary in their removal. The information from these bolts will be integral to the LWRS program initiatives in evaluating end of life microstructure and properties. Furthermore, valuable data will be obtained that can be incorporated into model predictions of long-term irradiation behavior and compared to results obtained in high flux experimental reactor conditions. The two bolts selected for the ORNL study will be shipped to Westinghouse with bolts of

  5. Effect of rod bow to partial closure on critical heat flux in PWR fuel assembly

    SciTech Connect (OSTI)

    Macbuff, R.B.; Fighetti, C.F.

    1983-07-01

    The effects of partial closure due to bowed rods on critical heat flux (CHF) in a pressurized water reactor rod bundle were evaluated by conducting tests in an electrically heated test section. The test section consisted of a 5x5 square rod array with 24 heated rods of 9.14 mm (0.360 in) diameter, each with a heated length of 3.66 m (12 ft) with Exxon Nuclear Company spacer grids on a 0.521 m (20.5 in) pitch. The central rod was a 12.2 mm (0.480 in) diameter unheated guide tube. The gap between two centrally located high powered rods was reduced 71% from nominal. The bow was approximately mid-span between two grids in the region in which CHF was observed in unbowed test sections. The results of these tests indicate a reduction in CHF of approximately 5% at 2400 psia and no reduction at 2000 psia when test repeatability is taken into consideration. The reduction in CHF at 2400 psia is substantially smaller than that inferred by linear interpolation of previously reported test results at 50 and 100% reduction of spacing. The local nature of CHF reduction due to rod bow was confirmed.

  6. Experiment data report for Multirod Burst Test (MRBT) bundle B-6. [PWR; BWR

    SciTech Connect (OSTI)

    Chapman, R H; Longest, A W; Crowley, J L

    1984-07-01

    A reference source of MRBT bundle B-6 test data is presented with minimum interpretation. The primary objective of this 8 x 8 multirod burst test was to investigate cladding deformation in the alpha-plus-beta-Zircaloy temperature range under simulated light-water-reactor (LWR) loss-of-coolant accident (LOCA) conditions. B-6 test conditions simulated the adiabatic heatup (reheat) phase of an LOCA and produced very uniform temperature distributions. The fuel pin simulators were electrically heated (average linear power generation of 1.42 kW/m) and were slightly cooled with a very low flow (Re approx. 140) of low-pressure superheated steam. The cladding temperature increased from the initial temperature (330/sup 0/C) to the burst temperature at a rate of 3.5/sup 0/C/s. The simulators burst in a very narrow temperature range, with an average of 930/sup 0/C. Cladding burst strain ranged from 21 to 56%, with an average of 31%. Volumetric expansion over the heated length of the cladding ranged from 16 to 32%, with an average of 23%. 23 references.

  7. Experiment data report for Multirod Burst Test (MRBT) Bundle B-5. [PWR

    SciTech Connect (OSTI)

    Chapman, R H; Crowley, J L; Longest, A W

    1984-08-01

    A reference source of MRBT bundle B-5 test data is presented with interpretation limited to that necessary to understand pertinent features of the test. Primary objectives of this 8 x 8 multirod burst test were to investigate the effects of array size and rod-to-rod interactions on cladding deformation in the high-alpha-Zircaloy temperature range under simulated light-water reactor loss-of-coolant accident (LOCA) conditions. B-5 test conditions, nominally the same as used in an earlier 4 x 4 (B-3) test, simulated the adiabatic heatup (reheat) phase of an LOCA and were conducive to large deformation. The fuel pin simulators were electrically heated (average linear power generation of 3.0 kW/m) and were slightly cooled with a very low flow (Re approx. 140) of low-pressure superheated steam. The cladding temperature increased from the initial temperature (335/sup 0/C) to the burst temperature at a rate of 9.8/sup 0/C/s. The simulators burst in a very narrow temperature range, with an average of 768/sup 0/C. Cladding burst strain ranged from 32% to 95%, with an average of 61%. Volumetric expansion over the heated length of the cladding ranged from 35% to 79%, with an average of 52%. The results clearly show deformation was greater in the bundle interior and suggest rod-to-rod mechanical interactions caused axial propagation of the deformation.

  8. Boundary effects on Zircaloy-4 cladding deformation in LOCA simulation tests. [PWR; BWR

    SciTech Connect (OSTI)

    Longest, A.W.; Chapman, R.H.; Crowley, J.L.

    1982-01-01

    Deformation behavior of Zircaloy-4 cladding under simulated loss-of-coolant accident (LOCA) conditions is being investigated in the Multirod Burst Test (MRBT) program in single rod and multirod tests. In these tests, internally-pressurized unirradiated Zircaloy-4 tubes containing internal electrical heaters are heated to failure in a low-pressure, superheated-steam environment (200 < Re < 800). The results provide a data base for evaluating deformation and blockage models employed with design-basis accident sequences to assess LWR core coolability for licensing purposes. Results of a recent 8 X 8 test indicate that models derived from smaller test arrays may not be representative of the behavior in large arrays, particularly for those temperature ranges in which large deformation can be expected. Two MRBT LOCA simulation tests conducted under the same nominal conditions (approx. 10 K/s heating rate from approx. 340/sup 0/C to failure at approx. 770/sup 0/C) were examined to determine the effects of array size and boundary conditions on deformation.

  9. Feasibility Study of Solar Photovoltaics on Landfills in Puerto Rico (Second Study)

    SciTech Connect (OSTI)

    Salasovich, J.; Mosey, G.

    2011-08-01

    This report presents the results of an assessment of the technical and economic feasibility of deploying a solar photovoltaics (PV) system on landfill sites in Puerto Rico. The purpose of this report is to assess the landfills with the highest potential for possible solar PV installation and estimate cost, performance, and site impacts of three different PV options: crystalline silicon (fixed tilt), crystalline silicon (single-axis tracking), and thin film (fixed tilt). The report outlines financing options that could assist in the implementation of a system. According to the site production calculations, the most cost-effective system in terms of return on investment is the thin-film fixed-tilt technology. The report recommends financing options that could assist in the implementation of such a system. The landfills and sites considered in this report were all determined feasible areas in which to implement solar PV systems.

  10. Electricity 101 | Department of Energy

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

    Resources » Electricity 101 Electricity 101 FREQUENTLY ASKED QUESTIONS Why do other countries use different shaped plugs? Why do outlets have three holes? Why do we have AC electricity? Can we harness lightning as an energy source? Can we have wireless transmission of electricity? SYSTEM What is electricity? Where does electricity come from? What is the "grid"? How much electricity does a typical household use? How did the electric system evolve? What does the future look like? Who

  11. Small Solar Electric Systems | Department of Energy

    Energy Savers [EERE]

    Electricity & Fuel Buying & Making Electricity Small Solar Electric Systems Small Solar Electric Systems A small solar electric or photovoltaic system can be a reliable and ...

  12. Electric power monthly

    SciTech Connect (OSTI)

    1995-08-01

    The Energy Information Administration (EIA) prepares the Electric Power Monthly (EPM) for a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. This publication provides monthly statistics for net generation, fossil fuel consumption and stocks, quantity and quality of fossil fuels, cost of fossil fuels, electricity sales, revenue, and average revenue per kilowatthour of electricity sold. Data on net generation, fuel consumption, fuel stocks, quantity and cost of fossil fuels are also displayed for the North American Electric Reliability Council (NERC) regions. The EIA publishes statistics in the EPM on net generation by energy source, consumption, stocks, quantity, quality, and cost of fossil fuels; and capability of new generating units by company and plant. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead.

  13. Integrated electrical connector

    DOE Patents [OSTI]

    Benett, William J.; Ackler, Harold D.

    2005-05-24

    An electrical connector is formed from a sheet of electrically conductive material that lies in between the two layers of nonconducting material that comprise the casing of an electrical chip. The connector is electrically connected to an electrical element embedded within the chip. An opening in the sheet is concentrically aligned with a pair of larger holes respectively bored through the nonconducting layers. The opening is also smaller than the diameter of an electrically conductive contact pin. However, the sheet is composed flexible material so that the opening adapts to the diameter of the pin when the pin is inserted therethrough. The periphery of the opening applies force to the sides of the pin when the pin is inserted, and thus holds the pin within the opening and in contact with the sheet, by friction. The pin can be withdrawn from the connector by applying sufficient axial force.

  14. Thermoacoustic magnetohydrodynamic electrical generator

    DOE Patents [OSTI]

    Wheatley, John C.; Swift, Gregory W.; Migliori, Albert

    1986-01-01

    A thermoacoustic magnetohydrodynamic electrical generator includes an intrinsically irreversible thermoacoustic heat engine coupled to a magnetohydrodynamic electrical generator. The heat engine includes an electrically conductive liquid metal as the working fluid and includes two heat exchange and thermoacoustic structure assemblies which drive the liquid in a push-pull arrangement to cause the liquid metal to oscillate at a resonant acoustic frequency on the order of 1,000 Hz. The engine is positioned in the field of a magnet and is oriented such that the liquid metal oscillates in a direction orthogonal to the field of the magnet, whereby an alternating electrical potential is generated in the liquid metal. Low-loss, low-inductance electrical conductors electrically connected to opposite sides of the liquid metal conduct an output signal to a transformer adapted to convert the low-voltage, high-current output signal to a more usable higher voltage, lower current signal.

  15. Electrical system architecture

    DOE Patents [OSTI]

    Algrain, Marcelo C.; Johnson, Kris W.; Akasam, Sivaprasad; Hoff, Brian D.

    2008-07-15

    An electrical system for a vehicle includes a first power source generating a first voltage level, the first power source being in electrical communication with a first bus. A second power source generates a second voltage level greater than the first voltage level, the second power source being in electrical communication with a second bus. A starter generator may be configured to provide power to at least one of the first bus and the second bus, and at least one additional power source may be configured to provide power to at least one of the first bus and the second bus. The electrical system also includes at least one power consumer in electrical communication with the first bus and at least one power consumer in electrical communication with the second bus.

  16. Thermoacoustic magnetohydrodynamic electrical generator

    DOE Patents [OSTI]

    Wheatley, J.C.; Swift, G.W.; Migliori, A.

    1984-11-16

    A thermoacoustic magnetohydrodynamic electrical generator includes an intrinsically irreversible thermoacoustic heat engine coupled to a magnetohydrodynamic electrical generator. The heat engine includes an electrically conductive liquid metal as the working fluid and includes two heat exchange and thermoacoustic structure assemblies which drive the liquid in a push-pull arrangement to cause the liquid metal to oscillate at a resonant acoustic frequency on the order of 1000 Hz. The engine is positioned in the field of a magnet and is oriented such that the liquid metal oscillates in a direction orthogonal to the field of the magnet, whereby an alternating electrical potential is generated in the liquid metal. Low-loss, low-inductance electrical conductors electrically connected to opposite sides of the liquid metal conduct an output signal to a transformer adapted to convert the low-voltage, high-current output signal to a more usable higher voltage, lower current signal.

  17. Electric Power Monthly

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

    2015 U.S. Energy Information Administration | Electric Power Monthly Appendix C Technical notes This appendix describes how the U. S. Energy Information Administration (EIA) collects, estimates, and reports electric power data in the EPM. Data quality The EPM is prepared by the Office of Electricity, Renewables & Uranium Statistics (ERUS), Energy Information Administration (EIA), U. S. Department of Energy. Quality statistics begin with the collection of the correct data. To assure this,

  18. Electric Power Monthly

    Gasoline and Diesel Fuel Update (EIA)

    Electric Power Monthly > Electric Power Monthly Back Issues Electric Power Monthly Back Issues Monthly Excel files zipped 2010 January February March April May June July August September October November December 2009 January February March April May June July August September October November December 2008 January February March March Supplement April May June July August September October November December 2007 January February March April May June July August September October November

  19. Electricity Monthly Update

    Gasoline and Diesel Fuel Update (EIA)

    Contact Information and Staff The Electricity Monthly Update is prepared by the Electric Power Operations Team, Office of Electricity, Renewables and Uranium Statistics, U.S. Energy Information Administration (EIA), U.S. Department of Energy. Editorial Lead: Chris Cassar (christopher.cassar@eia.gov) Senior Adviser: Bill Booth Core Team: Paul McCardle, Glenn McGrath, Stephen Scott, Tim Shear, April Lee

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

    SciTech Connect (OSTI)

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

    2012-05-01

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

  1. EIA - Electric Power Data

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

    across forms) Contains electricity generation; fuel consumption; emissions; retail sales, ... and associated revenue by end-use sector, green pricing, net ...

  2. Electric power annual 1992

    SciTech Connect (OSTI)

    Not Available

    1994-01-06

    The Electric Power Annual presents a summary of electric utility statistics at national, regional and State levels. The objective of the publication is to provide industry decisionmakers, government policymakers, analysts and the general public with historical data that may be used in understanding US electricity markets. The Electric Power Annual is prepared by the Survey Management Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); US Department of Energy. ``The US Electric Power Industry at a Glance`` section presents a profile of the electric power industry ownership and performance, and a review of key statistics for the year. Subsequent sections present data on generating capability, including proposed capability additions; net generation; fossil-fuel statistics; retail sales; revenue; financial statistics; environmental statistics; electric power transactions; demand-side management; and nonutility power producers. In addition, the appendices provide supplemental data on major disturbances and unusual occurrences in US electricity power systems. Each section contains related text and tables and refers the reader to the appropriate publication that contains more detailed data on the subject matter. Monetary values in this publication are expressed in nominal terms.

  3. 2015 Electricity Form Proposals

    Gasoline and Diesel Fuel Update (EIA)

    Quarterly Electricity Imports and Exports Report (EIA-111) OMB Clearance Renewal in 2015 ... Report (EIA-111) survey on August 26, 2015. The initial proposals were announced to ...

  4. Energy 101: Electric Vehicles

    K-12 Energy Lesson Plans and Activities Web site (EERE)

    This edition of Energy 101 highlights the benefits of electric vehicles, including improved fuel efficiency, reduced emissions, and lower maintenance costs.

  5. Electricity Advisory Committee

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

    Paula Carmody Maryland People's Council Paul Centolella Centolella and Associates LLC Carlos Coe Millennium Energy Phyllis Currie Pasadena Water and Power Clark Gellings Electric ...

  6. Electricity Distribution System Workshop

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

    ... the Electricity Transmission System (available online). ... or implied, or assumes any legal responsibility for the ... Workforce development and operator training are needed for ...

  7. Electricity Monthly Update

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

    Electric Reliability Council of Texas (ERCOT), and two locations in the California ISO (CAISO). Also shown are wholesale prices at trading hubs in Louisiana (into Entergy),...

  8. Electrical Circuit Tester

    DOE Patents [OSTI]

    Love, Frank

    2006-04-18

    An electrical circuit testing device is provided, comprising a case, a digital voltage level testing circuit with a display means, a switch to initiate measurement using the device, a non-shorting switching means for selecting pre-determined electrical wiring configurations to be tested in an outlet, a terminal block, a five-pole electrical plug mounted on the case surface and a set of adapters that can be used for various multiple-pronged electrical outlet configurations for voltages from 100 600 VAC from 50 100 Hz.

  9. Electrical Utility Materials Handler

    Broader source: Energy.gov [DOE]

    Join the Bonneville Power Administration (BPA) for a challenging and rewarding career, while working, living, and playing in the Pacific Northwest. The Electrical Utility Material Handler (EUMH)...

  10. Electricity Monthly Update

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

    costs, of which fuel costs account for the lion's share. Therefore, we present below, electricity generation output by fuel type and generator type. Since the generatorfuel...

  11. Department of Energy - Electricity

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

    opportunities and challenges that lie ahead. Secretary Moniz headed down to Florida to talk about Grid Modernization. Learn more about our nation's electric grid in this fact...

  12. Electricity Monthly Update

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

    Electricity Monthly Update Explained Highlights The Highlights page features in the center a short article about a major event or an informative topic. The left column contains...

  13. Electric Utility Industry Update

    Broader source: Energy.gov [DOE]

    Presentation—given at the April 2012 Federal Utility Partnership Working Group (FUPWG) meeting—covers significant electric industry trends and industry priorities with federal customers.

  14. Perforation patterned electrical interconnects

    DOE Patents [OSTI]

    Frey, Jonathan

    2014-01-28

    This disclosure describes systems and methods for increasing the usable surface area of electrical contacts within a device, such as a thin film solid state device, through the implementation of electrically conductive interconnects. Embodiments described herein include the use of a plurality of electrically conductive interconnects that penetrate through a top contact layer, through one or more multiple layers, and into a bottom contact layer. The plurality of conductive interconnects may form horizontal and vertical cross-sectional patterns. The use of lasers to form the plurality of electrically conductive interconnects from reflowed layer material further aids in the manufacturing process of a device.

  15. Renewable Electricity Generation

    SciTech Connect (OSTI)

    2012-09-01

    This document highlights DOE's Office of Energy Efficiency and Renewable Energy's advancements in renewable electricity generation technologies including solar, water, wind, and geothermal.

  16. Electricity Monthly Update

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

    Regional Wholesale Markets: May 2015 The United States has many regional wholesale electricity markets. Below we look at monthly and annual ranges of on-peak, daily wholesale...

  17. Electricity Monthly Update

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

    Wholesale Markets: August 2015 The United States has many regional wholesale electricity markets. Below we look at monthly and annual ranges of on-peak, daily wholesale...

  18. Electricity Monthly Update

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

    and fuel consumption In this section, we look at the resources used to produce electricity. Generating units are chosen to run primarily on their operating costs, of which...

  19. Electricity Monthly Update

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    New York ISO (NYISO), PJM Interconnection (PJM), Midwest ISO (MISO), Electric Reliability Council of Texas (ERCOT), and two locations in the California ISO (CAISO). Also...

  20. Electricity Monthly Update

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Wholesale Markets: February 2014 The United States has many regional wholesale electricity markets. Below we look at monthly and annual ranges of on-peak, daily wholesale...

  1. Electricity Advisory Committee

    Office of Environmental Management (EM)

    Indians Robert Gramlich American Wind Energy Association The Honorable Dian Grueneich California Public Utilities Commission Michael Heyeck American Electric Power Hunter Hunt ...

  2. 2013 Electricity Form Proposals

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

    Form EIA-861, "Annual Electric Power Industry Report" The EIA-861 survey has historically collected retail sales, revenue, and a variety of information related to demand response ...

  3. Integrating Electricity Subsector

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

    ... gangs Recreational Criminals Hackers 4 http:www.safetyissues.comsitecybercrimeciarevealshackerattacksonutilities.html?print 4-6 Table 4-1 (Continued) Electric Sector ...

  4. Electrically conductive cellulose composite

    DOE Patents [OSTI]

    Evans, Barbara R.; O'Neill, Hugh M.; Woodward, Jonathan

    2010-05-04

    An electrically conductive cellulose composite includes a cellulose matrix and an electrically conductive carbonaceous material incorporated into the cellulose matrix. The electrical conductivity of the cellulose composite is at least 10 .mu.S/cm at 25.degree. C. The composite can be made by incorporating the electrically conductive carbonaceous material into a culture medium with a cellulose-producing organism, such as Gluconoacetobacter hansenii. The composites can be used to form electrodes, such as for use in membrane electrode assemblies for fuel cells.

  5. Electric Storage Water Heaters

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

    & Events Expand News & Events Skip navigation links Residential Residential Lighting Energy Star Appliances Consumer Electronics Heat Pump Water Heaters Electric Storage Water...

  6. EIA - Electric Power Data

    Gasoline and Diesel Fuel Update (EIA)

    and customer counts, peak load, electric purchases, and energy efficiency and demand-side management programs, green pricing and net metering programs, and distributed ...

  7. 2012 National Electricity Forum

    Energy Savers [EERE]

    and Planning, Arizona Public Service * Jan Strack, Grid Planning, Regulatory & Economics Manager, San Diego Gas & Electric * Mario Villar, Vice President, Transmission, NV ...

  8. Estimating the Value of Electricity Storage Resources in Electricity

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

    Markets - EAC 2011 | Department of Energy Estimating the Value of Electricity Storage Resources in Electricity Markets - EAC 2011 Estimating the Value of Electricity Storage Resources in Electricity Markets - EAC 2011 The purpose of this report is to assist the U.S. Department of Energy (DOE) in 1) establishing a framework for understanding the role electricity storage resources (storage) can play in wholesale and retail electricity markets, 2) assessing the value of electricity storage in a

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

    SciTech Connect (OSTI)

    Eberhardt, A.C.

    1981-09-01

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

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

    SciTech Connect (OSTI)

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

    1981-08-01

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

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

    SciTech Connect (OSTI)

    Eberhardt, A.C.

    1981-06-01

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

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

    SciTech Connect (OSTI)

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

    1980-01-01

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

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

    SciTech Connect (OSTI)

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

    1982-01-01

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

  14. Alternative Fuels Data Center: Electricity

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Electricity Printable Version Share this resource Send a link to Alternative Fuels Data Center: Electricity to someone by E-mail Share Alternative Fuels Data Center: Electricity on Facebook Tweet about Alternative Fuels Data Center: Electricity on Twitter Bookmark Alternative Fuels Data Center: Electricity on Google Bookmark Alternative Fuels Data Center: Electricity on Delicious Rank Alternative Fuels Data Center: Electricity on Digg Find More places to share Alternative Fuels Data Center:

  15. Electrical Circuit Simulation Code

    Energy Science and Technology Software Center (OSTI)

    2001-08-09

    Massively-Parallel Electrical Circuit Simulation Code. CHILESPICE is a massively-arallel distributed-memory electrical circuit simulation tool that contains many enhanced radiation, time-based, and thermal features and models. Large scale electronic circuit simulation. Shared memory, parallel processing, enhance convergence. Sandia specific device models.

  16. Renewable Electricity Futures (Presentation)

    SciTech Connect (OSTI)

    Hand, M.; Mai, T.

    2012-08-01

    This presentation library summarizes findings of NREL's Renewable Electricity Futures study, published in June 2012. RE Futures investigated the challenges and impacts of achieving very high renewable electricity generation levels in the contiguous United States by 2050. It was presented in an Union of Concerned Scientists webinar on June 12, 2012.

  17. Renewable Electricity Futures (Presentation)

    SciTech Connect (OSTI)

    Mai, T.

    2012-08-01

    This presentation summarizes findings of NREL's Renewable Electricity Futures study, published in June 2012. RE Futures investigated the challenges and impacts of achieving very high renewable electricity generation levels in the contiguous United States by 2050. This presentation was presented in a Wind Powering America webinar on August 15, 2012 and is now available through the Wind Powering America website.

  18. Renewable Electricity Futures (Presentation)

    SciTech Connect (OSTI)

    Hand, M. M.

    2012-08-01

    This presentation library summarizes findings of NREL's Renewable Electricity Futures study, published in June 2012. RE Futures investigated the challenges and impacts of achieving very high renewable electricity generation levels in the contiguous United States by 2050. It was presented in a webinar given by the California Energy Commission.

  19. Renewable Electricity Futures (Presentation)

    SciTech Connect (OSTI)

    Mai, T.

    2012-08-01

    This presentation summarizes findings of NREL's Renewable Electricity Futures study, published in June 2012. RE Futures investigated the challenges and impacts of achieving very high renewable electricity generation levels in the contiguous United States by 2050. It was presented in a Power Systems Engineering Research Center webinar on September 4, 2012.

  20. Renewable Electricity Futures (Presentation)

    SciTech Connect (OSTI)

    Hand, M.

    2012-10-01

    This presentation library summarizes findings of NREL's Renewable Electricity Futures study, published in June 2012. RE Futures investigated the challenges and impacts of achieving very high renewable electricity generation levels in the contiguous United States by 2050. It is being presented at the Utility Variable-Generation Integration Group Fall Technical Workshop on October 24, 2012.

  1. Hawaii electric system reliability.

    SciTech Connect (OSTI)

    Silva Monroy, Cesar Augusto; Loose, Verne William

    2012-09-01

    This report addresses Hawaii electric system reliability issues; greater emphasis is placed on short-term reliability but resource adequacy is reviewed in reference to electric consumers' views of reliability %E2%80%9Cworth%E2%80%9D and the reserve capacity required to deliver that value. The report begins with a description of the Hawaii electric system to the extent permitted by publicly available data. Electrical engineering literature in the area of electric reliability is researched and briefly reviewed. North American Electric Reliability Corporation standards and measures for generation and transmission are reviewed and identified as to their appropriateness for various portions of the electric grid and for application in Hawaii. Analysis of frequency data supplied by the State of Hawaii Public Utilities Commission is presented together with comparison and contrast of performance of each of the systems for two years, 2010 and 2011. Literature tracing the development of reliability economics is reviewed and referenced. A method is explained for integrating system cost with outage cost to determine the optimal resource adequacy given customers' views of the value contributed by reliable electric supply. The report concludes with findings and recommendations for reliability in the State of Hawaii.

  2. Electrically conductive diamond electrodes

    DOE Patents [OSTI]

    Swain, Greg; Fischer, Anne ,; Bennett, Jason; Lowe, Michael

    2009-05-19

    An electrically conductive diamond electrode and process for preparation thereof is described. The electrode comprises diamond particles coated with electrically conductive doped diamond preferably by chemical vapor deposition which are held together with a binder. The electrodes are useful for oxidation reduction in gas, such as hydrogen generation by electrolysis.

  3. Energy 101: Electric Vehicles

    ScienceCinema (OSTI)

    None

    2013-05-29

    This edition of Energy 101 highlights the benefits of electric vehicles, including improved fuel efficiency, reduced emissions, and lower maintenance costs. For more information on electric vehicles from the Office of Energy Efficiency and Renewable Energy, visit the Vehicle Technologies Program website: http://www1.eere.energy.gov/vehiclesandfuels/

  4. Electric power monthly

    SciTech Connect (OSTI)

    Smith, Sandra R.; Johnson, Melvin; McClevey, Kenneth; Calopedis, Stephen; Bolden, Deborah

    1992-05-01

    The Electric Power Monthly is prepared by the Survey Management Division; Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), Department of Energy. This publication provides monthly statistics at the national, Census division, and State levels for net generation, fuel consumption, fuel stocks, quantity and quality of fuel, cost of fuel, electricity sales, revenue, and average revenue per kilowatthour of electricity sold. Data on net generation, fuel consumption, fuel stocks, quantity and cost of fuel are also displayed for the North American Electric Reliability Council (NERC) regions. Additionally, statistics by company and plant are published in the EPM on capability of new plants, new generation, fuel consumption, fuel stocks, quantity and quality of fuel, and cost of fuel.

  5. Unbundling electricity: Ancillary services

    SciTech Connect (OSTI)

    Kirby, B.; Hirst, E.

    1996-06-01

    The US electricity industry, dominated by vertically integrated, retail-monopoly, regulated utilities, is undergoing enormous changes. The industry, within the next few years, will evolve into a deintegrated, competitive-market dominated, less regulated industry. Part of this process involves unbundling electric generation from transmission, which raises the issue of ancillary services. Since the Federal Energy Regulatory Commission (FERC) published its March 1995 proposed rule on open-access transmission, ancillary services have been an important topic. Ancillary services are those functions performed by the equipment and people that generate, control, transmit, and distribute electricity to support the basic services of generating capacity, energy supply, and power delivery. These services cost US electricity consumers about $12 billion a year. This article examines the functions performed by the equipment and people that generate, control, transmit, and distribute electricity to support the basic services of generating capacity, energy supply, and power delivery.

  6. Electric turbocompound control system

    DOE Patents [OSTI]

    Algrain, Marcelo C.

    2007-02-13

    Turbocompound systems can be used to affect engine operation using the energy in exhaust gas that is driving the available turbocharger. A first electrical device acts as a generator in response to turbocharger rotation. A second electrical device acts as a motor to put mechanical power into the engine, typically at the crankshaft. Apparatus, systems, steps, and methods are described to control the generator and motor operations to control the amount of power being recovered. This can control engine operation closer to desirable parameters for given engine-related operating conditions compared to actual. The electrical devices can also operate in "reverse," going between motor and generator functions. This permits the electrical device associated with the crankshaft to drive the electrical device associated with the turbocharger as a motor, overcoming deficient engine operating conditions such as associated with turbocharger lag.

  7. Electric Resistance Heating Basics | Department of Energy

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

    Electric Resistance Heating Basics Electric Resistance Heating Basics August 16, 2013 - 3:10pm Addthis Electric resistance heat can be supplied by centralized forced-air electric furnaces or by heaters in each room. Electric resistance heating converts nearly all of the energy in the electricity to heat. Types of Electric Resistance Heaters Electric resistance heat can be provided by electric baseboard heaters, electric wall heaters, electric radiant heat, electric space heaters, electric

  8. EERE FY 2016 Budget Overview -- Renewable Electricity Generation

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

    ... * MHK: Demonstrate component improvements that will allow increase in wave energy conversion system power-to- weight ratio (PWR) of 100 percent (baseline for wave is 0.25kWton). ...

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

    SciTech Connect (OSTI)

    JOHNSON, D.M.

    2000-03-14

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

  10. EIA - State Electricity Profiles

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

    Arkansas Electricity Profile 2014 Table 1. 2014 Summary statistics (Arkansas) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 14,754 30 Electric utilities 11,526 23 IPP & CHP 3,227 29 Net generation (megawatthours) 61,592,137 24 Electric utilities 48,752,895 18 IPP & CHP 12,839,241 28 Emissions Sulfur dioxide (short tons) 89,528 15 Nitrogen oxide (short tons) 47,048 20 Carbon dioxide (thousand metric tons) 37,289 23 Sulfur dioxide (lbs/MWh) 2.9 9 Nitrogen oxide

  11. Chapter 5 - Electricity

    Gasoline and Diesel Fuel Update (EIA)

    1 U.S. Energy Information Administration | International Energy Outlook 2016 Chapter 5 Electricity Overview In the International Energy Outlook 2016 (IEO2016) Reference case, world net electricity generation increases 69% by 2040, from 21.6 trillion kilowatthours (kWh) in 2012 to 25.8 trillion kWh in 2020 and 36.5 trillion kWh in 2040. Electricity is the world's fastest-growing form of end-use energy consumption, as it has been for many decades. Power systems have continued to evolve from

  12. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Connecticut Electricity Profile 2014 Table 1. 2014 Summary statistics (Connecticut) Item Value Rank Primary energy source Nuclear Net summer capacity (megawatts) 8,832 35 Electric utilities 161 45 IPP & CHP 8,671 12 Net generation (megawatthours) 33,676,980 38 Electric utilities 54,693 45 IPP & CHP 33,622,288 11 Emissions Sulfur dioxide (short tons) 1,897 47 Nitrogen oxide (short tons) 8,910 45 Carbon dioxide (thousand metric tons) 7,959 41 Sulfur dioxide (lbs/MWh) 0.1 46 Nitrogen oxide

  13. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Delaware Electricity Profile 2014 Table 1. 2014 Summary statistics (Delaware) Item Value U.S. rank Primary energy source Natural gas Net summer capacity (megawatts) 3,086 46 Electric utilities 102 46 IPP & CHP 2,984 31 Net generation (megawatthours) 7,703,584 47 Electric utilities 49,050 46 IPP & CHP 7,654,534 35 Emissions Sulfur dioxide (short tons) 824 48 Nitrogen oxide (short tons) 2,836 48 Carbon dioxide (thousand metric tons) 4,276 43 Sulfur dioxide (lbs/MWh) 0.2 45 Nitrogen oxide

  14. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Idaho Electricity Profile 2014 Table 1. 2014 Summary statistics (Idaho) Item Value Rank Primary energy source Hydroelectric Net summer capacity (megawatts) 4,944 42 Electric utilities 3,413 37 IPP & CHP 1,531 39 Net generation (megawatthours) 15,184,417 43 Electric utilities 9,628,016 37 IPP & CHP 5,556,400 39 Emissions Sulfur dioxide (short tons) 5,777 42 Nitrogen oxide (short tons) 20,301 37 Carbon dioxide (thousand metric tons) 1,492 49 Sulfur dioxide (lbs/MWh) 0.8 36 Nitrogen oxide

  15. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Massachusetts Electricity Profile 2014 Table 1. 2014 Summary statistics (Massachusetts) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 13,128 32 Electric utilities 971 42 IPP & CHP 12,157 9 Net generation (megawatthours) 31,118,591 40 Electric utilities 679,986 43 IPP & CHP 30,438,606 12 Emissions Sulfur dioxide (short tons) 6,748 41 Nitrogen oxide (short tons) 13,831 43 Carbon dioxide (thousand metric tons) 12,231 39 Sulfur dioxide (lbs/MWh) 0.4 40

  16. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Michigan Electricity Profile 2014 Table 1. 2014 Summary statistics (Michigan) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 30,435 12 Electric utilities 22,260 9 IPP & CHP 8,175 14 Net generation (megawatthours) 106,816,991 14 Electric utilities 84,075,322 12 IPP & CHP 22,741,669 13 Emissions Sulfur dioxide (short tons) 173,521 7 Nitrogen oxide (short tons) 77,950 9 Carbon dioxide (thousand metric tons) 64,062 11 Sulfur dioxide (lbs/MWh) 3.2 7 Nitrogen oxide

  17. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Missouri Electricity Profile 2014 Table 1. 2014 Summary statistics (Missouri) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 21,790 19 Electric utilities 20,538 13 IPP & CHP 1,252 42 Net generation (megawatthours) 87,834,468 18 Electric utilities 85,271,253 11 IPP & CHP 2,563,215 46 Emissions Sulfur dioxide (short tons) 149,842 9 Nitrogen oxide (short tons) 77,749 10 Carbon dioxide (thousand metric tons) 75,735 8 Sulfur dioxide (lbs/MWh) 3.4 6 Nitrogen oxide

  18. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Montana Electricity Profile 2014 Table 1. 2014 Summary statistics (Montana) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 6,330 41 Electric utilities 3,209 38 IPP & CHP 3,121 30 Net generation (megawatthours) 30,257,616 41 Electric utilities 12,329,411 35 IPP & CHP 17,928,205 16 Emissions Sulfur dioxide (short tons) 14,426 34 Nitrogen oxide (short tons) 20,538 36 Carbon dioxide (thousand metric tons) 17,678 36 Sulfur dioxide (lbs/MWh) 1.0 34 Nitrogen oxide

  19. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Nebraska Electricity Profile 2014 Table 1. 2014 Summary statistics (Nebraska) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 8,732 36 Electric utilities 7,913 30 IPP & CHP 819 46 Net generation (megawatthours) 39,431,291 34 Electric utilities 36,560,960 30 IPP & CHP 2,870,331 45 Emissions Sulfur dioxide (short tons) 63,994 22 Nitrogen oxide (short tons) 27,045 30 Carbon dioxide (thousand metric tons) 26,348 31 Sulfur dioxide (lbs/MWh) 3.2 8 Nitrogen oxide

  20. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Nevada Electricity Profile 2014 Table 1. 2014 Summary statistics (Nevada) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 10,485 34 Electric utilities 8,480 29 IPP & CHP 2,006 35 Net generation (megawatthours) 36,000,537 37 Electric utilities 27,758,728 33 IPP & CHP 8,241,809 33 Emissions Sulfur dioxide (short tons) 10,229 40 Nitrogen oxide (short tons) 18,606 39 Carbon dioxide (thousand metric tons) 16,222 37 Sulfur dioxide (lbs/MWh) 0.4 38 Nitrogen

  1. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Hampshire Electricity Profile 2013 Table 1. 2013 Summary statistics (New Hampshire) Item Value Rank Primary energy source Nuclear Net summer capacity (megawatts) 4,413 44 Electric utilities 1,121 41 IPP & CHP 3,292 30 Net generation (megawatthours) 19,778,520 42 Electric utilities 2,266,903 41 IPP & CHP 17,511,617 20 Emissions Sulfur dioxide (short tons) 3,733 44 Nitrogen oxide (short tons) 5,057 47 Carbon dioxide (thousand metric tons) 3,447 46 Sulfur dioxide (lbs/MWh) 0.4 45 Nitrogen

  2. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Jersey Electricity Profile 2014 Table 1. 2014 Summary statistics (New Jersey) Item Value Rank Primary energy source Nuclear Net summer capacity (megawatts) 19,399 22 Electric utilities 544 43 IPP & CHP 18,852 7 Net generation (megawatthours) 68,051,086 23 Electric utilities -117,003 50 IPP & CHP 68,168,089 7 Emissions Sulfur dioxide (short tons) 3,369 44 Nitrogen oxide (short tons) 15,615 41 Carbon dioxide (thousand metric tons) 17,905 35 Sulfur dioxide (lbs/MWh) 0.1 47 Nitrogen oxide

  3. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Mexico Electricity Profile 2014 Table 1. 2014 Summary statistics (New Mexico) Item Value U.S. Rank Primary energy source Coal Net summer capacity (megawatts) 8,072 39 Electric utilities 6,094 33 IPP & CHP 1,978 37 Net generation (megawatthours) 32,306,210 39 Electric utilities 26,422,867 34 IPP & CHP 5,883,343 38 Emissions Sulfur dioxide (short tons) 12,064 37 Nitrogen oxide (short tons) 46,192 22 Carbon dioxide (thousand metric tons) 24,712 32 Sulfur dioxide (lbs/MWh) 0.7 37 Nitrogen

  4. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    York Electricity Profile 2014 Table 1. 2014 Summary statistics (New York) Item Value Rank Primary energy source Natural Gas Net summer capacity (megawatts) 40,404 6 Electric utilities 10,989 27 IPP & CHP 29,416 5 Net generation (megawatthours) 137,122,202 7 Electric utilities 34,082 31 IPP & CHP 103,039,347 5 Emissions Sulfur dioxide (short tons) 31,878 28 Nitrogen oxide (short tons) 46,971 21 Carbon dioxide (thousand metric tons) 33,240 26 Sulfur dioxide (lbs/MWh) 0.5 39 Nitrogen oxide

  5. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Carolina Electricity Profile 2013 Table 1. 2013 Summary statistics (North Carolina) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 30,048 12 Electric utilities 26,706 6 IPP & CHP 3,342 29 Net generation (megawatthours) 125,936,293 9 Electric utilities 116,317,050 2 IPP & CHP 9,619,243 31 Emissions Sulfur dioxide (short tons) 71,293 20 Nitrogen oxide (short tons) 62,397 12 Carbon dioxide (thousand metric tons) 56,940 14 Sulfur dioxide (lbs/MWh) 1.1 32 Nitrogen

  6. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Dakota Electricity Profile 2013 Table 1. 2013 Summary statistics (North Dakota) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 6,566 40 Electric utilities 5,292 34 IPP & CHP 1,274 41 Net generation (megawatthours) 35,021,673 39 Electric utilities 31,044,374 32 IPP & CHP 3,977,299 42 Emissions Sulfur dioxide (short tons) 56,854 23 Nitrogen oxide (short tons) 48,454 22 Carbon dioxide (thousand metric tons) 30,274 28 Sulfur dioxide (lbs/MWh) 3.2 11 Nitrogen oxide

  7. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Oregon Electricity Profile 2014 Table 1. 2014 Summary statistics (Oregon) Item Value Rank Primary energy source Hydroelectric Net summer capacity (megawatts) 15,884 27 Electric utilities 11,175 25 IPP & CHP 4,709 19 Net generation (megawatthours) 60,119,907 26 Electric utilities 44,565,239 24 IPP & CHP 15,554,668 21 Emissions Sulfur dioxide (short tons) 10,595 39 Nitrogen oxide (short tons) 14,313 42 Carbon dioxide (thousand metric tons) 8,334 40 Sulfur dioxide (lbs/MWh) 0.4 42 Nitrogen

  8. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Pennsylvania Electricity Profile 2014 Table 1. 2014 Summary statistics (Pennsylvania) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 42,723 5 Electric utilities 39 48 IPP & CHP 42,685 3 Net generation (megawatthours) 221,058,365 3 Electric utilities 90,994 44 IPP & CHP 220,967,371 2 Emissions Sulfur dioxide (short tons) 297,598 4 Nitrogen oxide (short tons) 141,486 2 Carbon dioxide (thousand metric tons) 101,361 4 Sulfur dioxide (lbs/MWh) 2.7 11 Nitrogen oxide

  9. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Rhode Island Electricity Profile 2014 Table 1. 2014 Summary statistics (Rhode Island) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 1,810 49 Electric utilities 8 50 IPP & CHP 1,803 38 Net generation (megawatthours) 6,281,748 49 Electric utilities 10,670 48 IPP & CHP 6,271,078 36 Emissions Sulfur dioxide (short tons) 100 49 Nitrogen oxide (short tons) 1,224 49 Carbon dioxide (thousand metric tons) 2,566 48 Sulfur dioxide (lbs/MWh) 0.0 48 Nitrogen oxide

  10. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Carolina Electricity Profile 2014 Table 1. 2014 Summary statistics (South Carolina) Item Value Rank Primary energy source Nuclear Net summer capacity (megawatts) 22,824 18 Electric utilities 20,836 12 IPP & CHP 1,988 36 Net generation (megawatthours) 97,158,465 16 Electric utilities 93,547,004 9 IPP & CHP 3,611,461 43 Emissions Sulfur dioxide (short tons) 43,659 25 Nitrogen oxide (short tons) 21,592 34 Carbon dioxide (thousand metric tons) 33,083 27 Sulfur dioxide (lbs/MWh) 0.9 35

  11. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    South Dakota Electricity Profile 2014 Table 1. 2014 Summary statistics (South Dakota) Item Value Rank Primary energy source Hydroelectric Net summer capacity (megawatts) 3,948 45 Electric utilities 3,450 36 IPP & CHP 499 48 Net generation (megawatthours) 10,995,240 45 Electric utilities 9,344,872 38 IPP & CHP 1,650,368 48 Emissions Sulfur dioxide (short tons) 13,852 35 Nitrogen oxide (short tons) 10,638 44 Carbon dioxide (thousand metric tons) 3,093 47 Sulfur dioxide (lbs/MWh) 2.5 15

  12. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Washington Electricity Profile 2014 Table 1. 2014 Summary statistics (Washington) Item Value Rank Primary energy source Hydroelectric Net summer capacity (megawatts) 30,949 10 Electric utilities 27,376 5 IPP & CHP 3,573 26 Net generation (megawatthours) 116,334,363 11 Electric utilities 102,294,256 5 IPP & CHP 14,040,107 24 Emissions Sulfur Dioxide (short tons) 13,716 36 Nitrogen Oxide (short tons) 18,316 40 Carbon Dioxide (thousand metric tons) 12,427 398 Sulfur Dioxide (lbs/MWh) 0.2 44

  13. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    West Virginia Electricity Profile 2014 Table 1. 2014 Summary statistics (West Virginia) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 16,276 25 Electric utilities 11,981 21 IPP & CHP 4,295 21 Net generation (megawatthours) 81,059,577 19 Electric utilities 63,331,833 15 IPP & CHP 17,727,743 17 Emissions Sulfur Dioxide (short tons) 102,406 12 Nitrogen Oxide (short tons) 72,995 11 Carbon Dioxide (thousand metric tons) 73,606 9 Sulfur Dioxide (lbs/MWh) 2.5 14

  14. EIA - State Electricity Profiles

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

    Alaska Electricity Profile 2014 Table 1. 2014 Summary statistics (Alaska) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 2,464 48 Electric utilities 2,313 39 IPP & CHP 151 50 Net generation (megawatthours) 6,042,830 50 Electric utilities 5,509,991 40 IPP & CHP 532,839 50 Emissions Sulfur dioxide (short tons) 4,129 43 Nitrogen oxide (short tons) 19,281 38 Carbon dioxide (thousand metric tons) 3,558 44 Sulfur dioxide (lbs/MWh) 1.4 28 Nitrogen oxide

  15. EIA - State Electricity Profiles

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

    Arizona Electricity Profile 2014 Table 1. 2014 Summary statistics (Arizona) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 28,249 13 Electric utilities 21,311 11 IPP & CHP 6,938 17 Net generation (megawatthours) 112,257,187 13 Electric utilities 94,847,135 8 IPP & CHP 17,410,053 19 Emissions Sulfur dioxide (short tons) 22,597 32 Nitrogen oxide (short tons) 56,726 17 Carbon dioxide (thousand metric tons) 53,684 16 Sulfur dioxide (lbs/MWh) 0.4 41 Nitrogen oxide

  16. EIA - State Electricity Profiles

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

    California Electricity Profile 2014 Table 1. 2014 Summary statistics (California) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 74,646 2 Electric utilities 28,201 4 IPP & CHP 46,446 2 Net generation (megawatthours) 198,807,622 5 Electric utilities 71,037,135 14 IPP & CHP 127,770,487 4 Emissions Sulfur dioxide (short tons) 3,102 46 Nitrogen oxide (short tons) 98,348 5 Carbon dioxide (thousand metric tons) 57,223 14 Sulfur dioxide (lbs/MWh) 0.0 49

  17. EIA - State Electricity Profiles

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

    Colorado Electricity Profile 2014 Table 1. 2014 Summary statistics (Colorado) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 14,933 29 Electric utilities 10,204 28 IPP & CHP 4,729 18 Net generation (megawatthours) 53,847,386 30 Electric utilities 43,239,615 26 IPP & CHP 10,607,771 30 Emissions Sulfur dioxide (short tons) 28,453 30 Nitrogen oxide (short tons) 44,349 24 Carbon dioxide (thousand metric tons) 38,474 22 Sulfur dioxide (lbs/MWh) 1.1 32 Nitrogen

  18. EIA - State Electricity Profiles

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

    Connecticut Electricity Profile 2014 Table 1. 2014 Summary statistics (Connecticut) Item Value Rank Primary energy source Nuclear Net summer capacity (megawatts) 8,832 35 Electric utilities 161 45 IPP & CHP 8,671 12 Net generation (megawatthours) 33,676,980 38 Electric utilities 54,693 45 IPP & CHP 33,622,288 11 Emissions Sulfur dioxide (short tons) 1,897 47 Nitrogen oxide (short tons) 8,910 45 Carbon dioxide (thousand metric tons) 7,959 41 Sulfur dioxide (lbs/MWh) 0.1 46 Nitrogen oxide

  19. EIA - State Electricity Profiles

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

    Delaware Electricity Profile 2014 Table 1. 2014 Summary statistics (Delaware) Item Value U.S. rank Primary energy source Natural gas Net summer capacity (megawatts) 3,086 46 Electric utilities 102 46 IPP & CHP 2,984 31 Net generation (megawatthours) 7,703,584 47 Electric utilities 49,050 46 IPP & CHP 7,654,534 35 Emissions Sulfur dioxide (short tons) 824 48 Nitrogen oxide (short tons) 2,836 48 Carbon dioxide (thousand metric tons) 4,276 43 Sulfur dioxide (lbs/MWh) 0.2 45 Nitrogen oxide

  20. EIA - State Electricity Profiles

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

    District of Columbia Electricity Profile 2014 Table 1. 2014 Summary statistics (District of Columbia) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 9 51 Electric utilities IPP & CHP 9 51 Net generation (megawatthours) 67,612 51 Electric utilities IPP & CHP 67,612 51 Emissions Sulfur dioxide (short tons) 0 51 Nitrogen oxide (short tons) 147 51 Carbon dioxide (thousand metric tons) 48 50 Sulfur dioxide (lbs/MWh) 0.0 51 Nitrogen oxide (lbs/MWh) 4.3 3

  1. EIA - State Electricity Profiles

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

    Florida Electricity Profile 2014 Table 1. 2014 Summary statistics (Florida) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 59,440 3 Electric utilities 51,775 1 IPP & CHP 7,665 15 Net generation (megawatthours) 230,015,937 2 Electric utilities 211,970,587 1 IPP & CHP 18,045,350 15 Emissions Sulfur dioxide (short tons) 126,600 10 Nitrogen oxide (short tons) 91,356 6 Carbon dioxide (thousand metric tons) 111,549 2 Sulfur dioxide (lbs/MWh) 1.1 30 Nitrogen

  2. EIA - State Electricity Profiles

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

    Georgia Electricity Profile 2014 Table 1. 2014 Summary statistics (Georgia) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 38,250 7 Electric utilities 28,873 3 IPP & CHP 9,377 10 Net generation (megawatthours) 125,837,224 10 Electric utilities 109,523,336 4 IPP & CHP 16,313,888 20 Emissions Sulfur dioxide (short tons) 105,998 11 Nitrogen oxide (short tons) 58,144 14 Carbon dioxide (thousand metric tons) 62,516 12 Sulfur dioxide (lbs/MWh) 1.7 24 Nitrogen oxide

  3. EIA - State Electricity Profiles

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

    Hawaii Electricity Profile 2014 Table 1. 2014 Summary statistics (Hawaii) Item Value Rank Primary energy source Petroleum Net summer capacity (megawatts) 2,672 47 Electric utilities 1,732 40 IPP & CHP 939 45 Net generation (megawatthours) 10,204,158 46 Electric utilities 5,517,389 39 IPP & CHP 4,686,769 40 Emissions Sulfur dioxide (short tons) 21,670 33 Nitrogen oxide (short tons) 26,928 31 Carbon dioxide (thousand metric tons) 7,313 42 Sulfur dioxide (lbs/MWh) 4.2 4 Nitrogen oxide

  4. EIA - State Electricity Profiles

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

    Idaho Electricity Profile 2014 Table 1. 2014 Summary statistics (Idaho) Item Value Rank Primary energy source Hydroelectric Net summer capacity (megawatts) 4,944 42 Electric utilities 3,413 37 IPP & CHP 1,531 39 Net generation (megawatthours) 15,184,417 43 Electric utilities 9,628,016 37 IPP & CHP 5,556,400 39 Emissions Sulfur dioxide (short tons) 5,777 42 Nitrogen oxide (short tons) 20,301 37 Carbon dioxide (thousand metric tons) 1,492 49 Sulfur dioxide (lbs/MWh) 0.8 36 Nitrogen oxide

  5. EIA - State Electricity Profiles

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

    Illinois Electricity Profile 2014 Table 1. 2014 Summary statistics (Illinois) Item Value Rank Primary energy source Nuclear Net summer capacity (megawatts) 44,727 4 Electric utilities 5,263 35 IPP & CHP 39,464 4 Net generation (megawatthours) 202,143,878 4 Electric utilities 10,457,398 36 IPP & CHP 191,686,480 3 Emissions Sulfur dioxide (short tons) 187,536 6 Nitrogen oxide (short tons) 58,076 15 Carbon dioxide (thousand metric tons) 96,624 6 Sulfur dioxide (lbs/MWh) 1.9 20 Nitrogen

  6. EIA - State Electricity Profiles

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

    Indiana Electricity Profile 2014 Table 1. 2014 Summary statistics (Indiana) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 27,499 14 Electric utilities 23,319 7 IPP & CHP 4,180 23 Net generation (megawatthours) 115,395,392 12 Electric utilities 100,983,285 6 IPP & CHP 14,412,107 22 Emissions Sulfur dioxide (short tons) 332,396 3 Nitrogen oxide (short tons) 133,412 3 Carbon dioxide (thousand metric tons) 103,391 3 Sulfur dioxide (lbs/MWh) 5.8 1 Nitrogen oxide

  7. EIA - State Electricity Profiles

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

    Iowa Electricity Profile 2014 Table 1. 2014 Summary statistics (Iowa) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 16,507 24 Electric utilities 12,655 20 IPP & CHP 3,852 25 Net generation (megawatthours) 56,853,282 28 Electric utilities 43,021,954 27 IPP & CHP 13,831,328 25 Emissions Sulfur dioxide (short tons) 74,422 19 Nitrogen oxide (short tons) 41,793 25 Carbon dioxide (thousand metric tons) 39,312 21 Sulfur dioxide (lbs/MWh) 2.6 13 Nitrogen oxide

  8. EIA - State Electricity Profiles

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

    Kansas Electricity Profile 2014 Table 1. 2014 Summary statistics (Kansas) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 14,227 31 Electric utilities 11,468 24 IPP & CHP 2,759 33 Net generation (megawatthours) 49,728,363 31 Electric utilities 39,669,629 29 IPP & CHP 10,058,734 31 Emissions Sulfur dioxide (short tons) 31,550 29 Nitrogen oxide (short tons) 29,014 29 Carbon dioxide (thousand metric tons) 31,794 29 Sulfur dioxide (lbs/MWh) 1.3 29 Nitrogen oxide

  9. EIA - State Electricity Profiles

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

    Kentucky Electricity Profile 2014 Table 1. 2014 Summary statistics (Kentucky) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 20,878 21 Electric utilities 19,473 15 IPP & CHP 1,405 40 Net generation (megawatthours) 90,896,435 17 Electric utilities 90,133,403 10 IPP & CHP 763,032 49 Emissions Sulfur dioxide (short tons) 204,873 5 Nitrogen oxide (short tons) 89,253 7 Carbon dioxide (thousand metric tons) 85,795 7 Sulfur dioxide (lbs/MWh) 4.5 3 Nitrogen oxide

  10. EIA - State Electricity Profiles

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

    Louisiana Electricity Profile 2014 Table 1. 2014 Summary statistics (Louisiana) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 26,657 15 Electric utilities 18,120 16 IPP & CHP 8,537 13 Net generation (megawatthours) 104,229,402 15 Electric utilities 58,518,271 17 IPP & CHP 45,711,131 8 Emissions Sulfur dioxide (short tons) 96,240 14 Nitrogen oxide (short tons) 83,112 8 Carbon dioxide (thousand metric tons) 57,137 15 Sulfur dioxide (lbs/MWh) 1.8 21

  11. EIA - State Electricity Profiles

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

    Maine Electricity Profile 2014 Table 1. 2014 Summary statistics (Maine) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 4,470 43 Electric utilities 10 49 IPP & CHP 4,460 20 Net generation (megawatthours) 13,248,710 44 Electric utilities 523 49 IPP & CHP 13,248,187 27 Emissions Sulfur dioxide (short tons) 10,990 38 Nitrogen oxide (short tons) 8,622 46 Carbon dioxide (thousand metric tons) 3,298 46 Sulfur dioxide (lbs/MWh) 1.7 25 Nitrogen oxide (lbs/MWh)

  12. EIA - State Electricity Profiles

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

    Maryland Electricity Profile 2014 Table 1. 2014 Summary statistics (Maryland) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 12,264 33 Electric utilities 85 47 IPP & CHP 12,179 8 Net generation (megawatthours) 37,833,652 35 Electric utilities 20,260 47 IPP & CHP 37,813,392 9 Emissions Sulfur dioxide (short tons) 41,370 26 Nitrogen oxide (short tons) 20,626 35 Carbon dioxide (thousand metric tons) 20,414 34 Sulfur dioxide (lbs/MWh) 2.2 18 Nitrogen oxide

  13. EIA - State Electricity Profiles

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

    Massachusetts Electricity Profile 2014 Table 1. 2014 Summary statistics (Massachusetts) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 13,128 32 Electric utilities 971 42 IPP & CHP 12,157 9 Net generation (megawatthours) 31,118,591 40 Electric utilities 679,986 43 IPP & CHP 30,438,606 12 Emissions Sulfur dioxide (short tons) 6,748 41 Nitrogen oxide (short tons) 13,831 43 Carbon dioxide (thousand metric tons) 12,231 39 Sulfur dioxide (lbs/MWh) 0.4 40

  14. EIA - State Electricity Profiles

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

    Michigan Electricity Profile 2014 Table 1. 2014 Summary statistics (Michigan) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 30,435 12 Electric utilities 22,260 9 IPP & CHP 8,175 14 Net generation (megawatthours) 106,816,991 14 Electric utilities 84,075,322 12 IPP & CHP 22,741,669 13 Emissions Sulfur dioxide (short tons) 173,521 7 Nitrogen oxide (short tons) 77,950 9 Carbon dioxide (thousand metric tons) 64,062 11 Sulfur dioxide (lbs/MWh) 3.2 7 Nitrogen oxide

  15. EIA - State Electricity Profiles

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

    Minnesota Electricity Profile 2014 Table 1. 2014 Summary statistics (Minnesota) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 15,621 28 Electric utilities 11,557 22 IPP & CHP 4,064 24 Net generation (megawatthours) 56,998,330 27 Electric utilities 45,963,271 22 IPP & CHP 11,035,059 29 Emissions Sulfur dioxide (short tons) 39,272 27 Nitrogen oxide (short tons) 38,373 28 Carbon dioxide (thousand metric tons) 32,399 28 Sulfur dioxide (lbs/MWh) 1.4 27 Nitrogen

  16. EIA - State Electricity Profiles

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

    Mississippi Electricity Profile 2014 Table 1. 2014 Summary statistics (Mississippi) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 16,090 26 Electric utilities 13,494 19 IPP & CHP 2,597 34 Net generation (megawatthours) 55,127,092 29 Electric utilities 47,084,382 21 IPP & CHP 8,042,710 34 Emissions Sulfur dioxide (short tons) 101,093 13 Nitrogen oxide (short tons) 23,993 32 Carbon dioxide (thousand metric tons) 24,037 33 Sulfur dioxide (lbs/MWh) 3.7 5

  17. EIA - State Electricity Profiles

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

    Missouri Electricity Profile 2014 Table 1. 2014 Summary statistics (Missouri) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 21,790 19 Electric utilities 20,538 13 IPP & CHP 1,252 42 Net generation (megawatthours) 87,834,468 18 Electric utilities 85,271,253 11 IPP & CHP 2,563,215 46 Emissions Sulfur dioxide (short tons) 149,842 9 Nitrogen oxide (short tons) 77,749 10 Carbon dioxide (thousand metric tons) 75,735 8 Sulfur dioxide (lbs/MWh) 3.4 6 Nitrogen oxide

  18. EIA - State Electricity Profiles

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

    Montana Electricity Profile 2014 Table 1. 2014 Summary statistics (Montana) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 6,330 41 Electric utilities 3,209 38 IPP & CHP 3,121 30 Net generation (megawatthours) 30,257,616 41 Electric utilities 12,329,411 35 IPP & CHP 17,928,205 16 Emissions Sulfur dioxide (short tons) 14,426 34 Nitrogen oxide (short tons) 20,538 36 Carbon dioxide (thousand metric tons) 17,678 36 Sulfur dioxide (lbs/MWh) 1.0 34 Nitrogen oxide

  19. EIA - State Electricity Profiles

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

    Nebraska Electricity Profile 2014 Table 1. 2014 Summary statistics (Nebraska) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 8,732 36 Electric utilities 7,913 30 IPP & CHP 819 46 Net generation (megawatthours) 39,431,291 34 Electric utilities 36,560,960 30 IPP & CHP 2,870,331 45 Emissions Sulfur dioxide (short tons) 63,994 22 Nitrogen oxide (short tons) 27,045 30 Carbon dioxide (thousand metric tons) 26,348 31 Sulfur dioxide (lbs/MWh) 3.2 8 Nitrogen oxide

  20. EIA - State Electricity Profiles

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

    Nevada Electricity Profile 2014 Table 1. 2014 Summary statistics (Nevada) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 10,485 34 Electric utilities 8,480 29 IPP & CHP 2,006 35 Net generation (megawatthours) 36,000,537 37 Electric utilities 27,758,728 33 IPP & CHP 8,241,809 33 Emissions Sulfur dioxide (short tons) 10,229 40 Nitrogen oxide (short tons) 18,606 39 Carbon dioxide (thousand metric tons) 16,222 37 Sulfur dioxide (lbs/MWh) 0.4 38 Nitrogen

  1. EIA - State Electricity Profiles

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

    Hampshire Electricity Profile 2013 Table 1. 2013 Summary statistics (New Hampshire) Item Value Rank Primary energy source Nuclear Net summer capacity (megawatts) 4,413 44 Electric utilities 1,121 41 IPP & CHP 3,292 30 Net generation (megawatthours) 19,778,520 42 Electric utilities 2,266,903 41 IPP & CHP 17,511,617 20 Emissions Sulfur dioxide (short tons) 3,733 44 Nitrogen oxide (short tons) 5,057 47 Carbon dioxide (thousand metric tons) 3,447 46 Sulfur dioxide (lbs/MWh) 0.4 45 Nitrogen

  2. EIA - State Electricity Profiles

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

    Jersey Electricity Profile 2014 Table 1. 2014 Summary statistics (New Jersey) Item Value Rank Primary energy source Nuclear Net summer capacity (megawatts) 19,399 22 Electric utilities 544 43 IPP & CHP 18,852 7 Net generation (megawatthours) 68,051,086 23 Electric utilities -117,003 50 IPP & CHP 68,168,089 7 Emissions Sulfur dioxide (short tons) 3,369 44 Nitrogen oxide (short tons) 15,615 41 Carbon dioxide (thousand metric tons) 17,905 35 Sulfur dioxide (lbs/MWh) 0.1 47 Nitrogen oxide

  3. EIA - State Electricity Profiles

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

    Mexico Electricity Profile 2014 Table 1. 2014 Summary statistics (New Mexico) Item Value U.S. Rank Primary energy source Coal Net summer capacity (megawatts) 8,072 39 Electric utilities 6,094 33 IPP & CHP 1,978 37 Net generation (megawatthours) 32,306,210 39 Electric utilities 26,422,867 34 IPP & CHP 5,883,343 38 Emissions Sulfur dioxide (short tons) 12,064 37 Nitrogen oxide (short tons) 46,192 22 Carbon dioxide (thousand metric tons) 24,712 32 Sulfur dioxide (lbs/MWh) 0.7 37 Nitrogen

  4. EIA - State Electricity Profiles

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

    York Electricity Profile 2014 Table 1. 2014 Summary statistics (New York) Item Value Rank Primary energy source Natural Gas Net summer capacity (megawatts) 40,404 6 Electric utilities 10,989 27 IPP & CHP 29,416 5 Net generation (megawatthours) 137,122,202 7 Electric utilities 34,082 31 IPP & CHP 103,039,347 5 Emissions Sulfur dioxide (short tons) 31,878 28 Nitrogen oxide (short tons) 46,971 21 Carbon dioxide (thousand metric tons) 33,240 26 Sulfur dioxide (lbs/MWh) 0.5 39 Nitrogen oxide

  5. EIA - State Electricity Profiles

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

    Carolina Electricity Profile 2013 Table 1. 2013 Summary statistics (North Carolina) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 30,048 12 Electric utilities 26,706 6 IPP & CHP 3,342 29 Net generation (megawatthours) 125,936,293 9 Electric utilities 116,317,050 2 IPP & CHP 9,619,243 31 Emissions Sulfur dioxide (short tons) 71,293 20 Nitrogen oxide (short tons) 62,397 12 Carbon dioxide (thousand metric tons) 56,940 14 Sulfur dioxide (lbs/MWh) 1.1 32 Nitrogen

  6. EIA - State Electricity Profiles

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

    Dakota Electricity Profile 2013 Table 1. 2013 Summary statistics (North Dakota) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 6,566 40 Electric utilities 5,292 34 IPP & CHP 1,274 41 Net generation (megawatthours) 35,021,673 39 Electric utilities 31,044,374 32 IPP & CHP 3,977,299 42 Emissions Sulfur dioxide (short tons) 56,854 23 Nitrogen oxide (short tons) 48,454 22 Carbon dioxide (thousand metric tons) 30,274 28 Sulfur dioxide (lbs/MWh) 3.2 11 Nitrogen oxide

  7. EIA - State Electricity Profiles

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

    Ohio Electricity Profile 2014 Table 1. 2014 Summary statistics (Ohio) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 31,507 9 Electric utilities 11,134 26 IPP & CHP 20,372 6 Net generation (megawatthours) 134,476,405 8 Electric utilities 43,290,512 25 IPP & CHP 91,185,893 7 Emissions Sulfur dioxide (short tons) 355,108 1 Nitrogen oxide (short tons) 105,688 4 Carbon dioxide (thousand metrictons) 98,650 5 Sulfur dioxide (lbs/MWh) 5.3 2 Nitrogen oxide (lbs/MWh)

  8. EIA - State Electricity Profiles

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

    Oklahoma Electricity Profile 2014 Table 1. 2014 Summary statistics (Oklahoma) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 24,048 17 Electric utilities 17,045 17 IPP & CHP 7,003 16 Net generation (megawatthours) 70,155,504 22 Electric utilities 48,096,026 19 IPP & CHP 22,059,478 14 Emissions Sulfur dioxide 78,556 18 Nitrogen oxide 44,874 23 Carbon dioxide (thousand metric tons) 43,994 18 Sulfur dioxide (lbs/MWh) 2.2 17 Nitrogen oxide (lbs/MWh) 1.3 26

  9. EIA - State Electricity Profiles

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

    Pennsylvania Electricity Profile 2014 Table 1. 2014 Summary statistics (Pennsylvania) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 42,723 5 Electric utilities 39 48 IPP & CHP 42,685 3 Net generation (megawatthours) 221,058,365 3 Electric utilities 90,994 44 IPP & CHP 220,967,371 2 Emissions Sulfur dioxide (short tons) 297,598 4 Nitrogen oxide (short tons) 141,486 2 Carbon dioxide (thousand metric tons) 101,361 4 Sulfur dioxide (lbs/MWh) 2.7 11 Nitrogen oxide

  10. EIA - State Electricity Profiles

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

    Carolina Electricity Profile 2014 Table 1. 2014 Summary statistics (South Carolina) Item Value Rank Primary energy source Nuclear Net summer capacity (megawatts) 22,824 18 Electric utilities 20,836 12 IPP & CHP 1,988 36 Net generation (megawatthours) 97,158,465 16 Electric utilities 93,547,004 9 IPP & CHP 3,611,461 43 Emissions Sulfur dioxide (short tons) 43,659 25 Nitrogen oxide (short tons) 21,592 34 Carbon dioxide (thousand metric tons) 33,083 27 Sulfur dioxide (lbs/MWh) 0.9 35

  11. EIA - State Electricity Profiles

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

    Tennessee Electricity Profile 2014 Table 1. 2014 Summary statistics (Tennessee) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 20,998 20 Electric utilities 20,490 14 IPP & CHP 508 47 Net generation (megawatthours) 79,506,886 20 Electric utilities 76,986,629 13 IPP & CHP 2,520,257 47 Emissions Sulfur dioxide (short tons) 89,357 16 Nitrogen oxide (short tons) 23,913 33 Carbon dioxide (thousand metric tons) 41,405 20 Sulfur dioxide (lbs/MWh) 2.2 16 Nitrogen oxide

  12. EIA - State Electricity Profiles

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

    Texas Electricity Profile 2014 Table 1. 2014 Summary statistics (Texas) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 112,914 1 Electric utilities 29,113 2 IPP & CHP 83,800 1 Net generation (megawatthours) 437,629,668 1 Electric utilities 94,974,953 7 IPP & CHP 342,654,715 1 Emissions Sulfur Dioxide (short tons) 349,245 2 Nitrogen Oxide short tons) 229,580 1 Carbon Dioxide (thousand metric tons) 254,488 1 Sulfur Dioxide (lbs/MWh) 1.6 26 Nitrogen Oxide

  13. EIA - State Electricity Profiles

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

    Utah Electricity Profile 2014 Table 1. 2014 Summary statistics (Utah) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 8,325 38 Electric utilities 7,296 31 IPP & CHP 1,029 44 Net generation (megawatthours) 43,784,526 33 Electric utilities 40,741,425 28 IPP & CHP 3,043,101 44 Emissions Sulfur Dioxide (short tons) 23,646 31 Nitrogen Oxide (short tons) 57,944 16 Carbon Dioxide (thousand metric tons) 35,179 24 Sulfur Dioxide (lbs/MWh) 1.1 31 Nitrogen Oxide (lbs/MWh)

  14. EIA - State Electricity Profiles

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

    Vermont Electricity Profile 2014 Table 1. 2014 Summary statistics (Vermont) Item Value Rank Primary energy source Nuclear Net summer capacity (megawatts) 650 50 Electric utilities 337 44 IPP & CHP 313 49 Net generation (megawatthours) 7,031,394 48 Electric utilities 868,079 42 IPP & CHP 6,163,315 37 Emissions Sulfur Dioxide (short tons) 71 50 Nitrogen Oxide (short tons) 737 50 Carbon Dioxide (thousand metric tons) 14 51 Sulfur Dioxide (lbs/MWh) 0.0 50 Nitrogen Oxide (lbs/MWh) 0.2 51

  15. EIA - State Electricity Profiles

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

    Virginia Electricity Profile 2014 Table 1. 2014 Summary statistics (Virginia) Item Value Rank Primary energy source Nuclear Net summer capacity (megawatts) 26,292 16 Electric utilities 22,062 10 IPP & CHP 4,231 22 Net generation (megawatthours) 77,137,438 21 Electric utilities 62,966,914 16 IPP & CHP 14,170,524 23 Emissions Sulfur Dioxide (short tons) 68,550 20 Nitrogen Oxide (short tons) 40,656 26 Carbon Dioxide (thousand metric tons) 33,295 25 Sulfur Dioxide (lbs/MWh) 1.8 23 Nitrogen

  16. EIA - State Electricity Profiles

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

    Wisconsin Electricity Profile 2014 Table 1. 2014 Summary statistics (Wisconsin) Item Value Rank Primary Energy Source Coal Net summer capacity (megawatts) 17,166 23 Electric utilities 14,377 18 IPP & CHP 2,788 32 Net generation (megawatthours) 61,064,796 25 Electric utilities 47,301,782 20 IPP & CHP 13,763,014 26 Emissions Sulfur Dioxide (short tons) 81,239 17 Nitrogen Oxide (short tons) 39,597 27 Carbon Dioxide (thousand metric tons) 43,750 19 Sulfur Dioxide (lbs/MWh) 2.7 12 Nitrogen

  17. EIA - State Electricity Profiles

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

    Wyoming Electricity Profile 2014 Table 1. 2014 Summary statistics (Wyoming) Item Value Rank Primary energy source Coal Net summer capacity (megawatts) 8,458 37 Electric utilities 7,233 32 IPP & CHP 1,225 43 Net generation (megawatthours) 49,696,183 32 Electric utilities 45,068,982 23 IPP & CHP 4,627,201 41 Emissions Sulfur Dioxide (short tons) 45,704 24 Nitrogen Oxide (short tons) 49,638 18 Carbon Dioxide (thousand metric tons) 47,337 17 Sulfur Dioxide (lbs/MWh) 1.8 22 Nitrogen Oxide

  18. BEEST: Electric Vehicle Batteries

    SciTech Connect (OSTI)

    2010-07-01

    BEEST Project: The U.S. spends nearly a $1 billion per day to import petroleum, but we need dramatically better batteries for electric and plug-in hybrid vehicles (EV/PHEV) to truly compete with gasoline-powered cars. The 10 projects in ARPA-E’s BEEST Project, short for “Batteries for Electrical Energy Storage in Transportation,” could make that happen by developing a variety of rechargeable battery technologies that would enable EV/PHEVs to meet or beat the price and performance of gasoline-powered cars, and enable mass production of electric vehicles that people will be excited to drive.

  19. Plug-In Electric Vehicle Handbook for Electrical Contractors (Brochure)

    SciTech Connect (OSTI)

    Not Available

    2012-04-01

    This handbook answers basic questions about plug-in electric vehicles, charging stations, charging equipment, charging equipment installation, and training for electrical contractors.

  20. March 2012 Electrical Safety Occurrences

    Energy Savers [EERE]

    - Electrical Wiring 08J--OSHA ReportableIndustrial Hygiene - Near Miss (Electrical) 11G--Other - Subcontractor 12C--EH Categories - Electrical Safety 14D--Quality Assurance -...

  1. Electric Vehicles | Argonne National Laboratory

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

    2015 Chevrolet Spark EV 2015 Kia Soul Electric 2014 BMW i3 BEV 2014 Smart Electric Drive 2013 Ford Focus Electric 2013 Nissan Leaf SV 2012 Mitsubishi I-MiEV 2012 Nissan Leaf ...

  2. EV Everywhere: All-Electric and Plug-in Hybrid Electric Cars...

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

    and Plug-in Hybrid Electric Cars Find Electric Vehicle Models Vehicle Charging Saving Fuel & Vehicle Costs Electric Vehicle Stories Benefits of Electric Vehicles Electric ...

  3. Generating electricity from viruses

    SciTech Connect (OSTI)

    Lee, Seung-Wuk

    2013-10-31

    Berkeley Lab's Seung-Wuk Lee discusses "Generating electricity from viruses" in this Oct. 28, 2013 talk, which is part of a Science at the Theater event entitled Eight Big Ideas.

  4. Electricity Monthly Update

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

    California (CAISO) due to very low natural gas prices. Hawaii's retail electricity revenue per kilowatthour fell the most of any state for the fifth month in a row, down 24%...

  5. Micromachined electrical cauterizer

    DOE Patents [OSTI]

    Lee, A.P.; Krulevitch, P.A.; Northrup, M.A.

    1999-08-31

    A micromachined electrical cauterizer is disclosed. Microstructures are combined with microelectrodes for highly localized electro cauterization. Using boron etch stops and surface micromachining, microneedles with very smooth surfaces are made. Micromachining also allows for precision placement of electrodes by photolithography with micron sized gaps to allow for concentrated electric fields. A microcauterizer is fabricated by bulk etching silicon to form knife edges, then parallelly placed microelectrodes with gaps as small as 5 {mu}m are patterned and aligned adjacent the knife edges to provide homeostasis while cutting tissue. While most of the microelectrode lines are electrically insulated from the atmosphere by depositing and patterning silicon dioxide on the electric feedthrough portions, a window is opened in the silicon dioxide to expose the parallel microelectrode portion. This helps reduce power loss and assist in focusing the power locally for more efficient and safer procedures. 7 figs.

  6. Generating electricity from viruses

    ScienceCinema (OSTI)

    Lee, Seung-Wuk

    2014-06-23

    Berkeley Lab's Seung-Wuk Lee discusses "Generating electricity from viruses" in this Oct. 28, 2013 talk, which is part of a Science at the Theater event entitled Eight Big Ideas.

  7. Electricity Monthly Update

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Electric Power Sector Coal Stocks: February 2014 Stocks Extreme cold throughout the winter continued in February, leading to a 13.4 million ton decline in coal inventories from...

  8. Biomass for Electricity Generation

    Reports and Publications (EIA)

    2002-01-01

    This paper examines issues affecting the uses of biomass for electricity generation. The methodology used in the National Energy Modeling System to account for various types of biomass is discussed, and the underlying assumptions are explained.

  9. Conserving Electric Energy

    Broader source: Energy.gov [DOE]

    A classroom activity whereby students participate in two experiments in which they gain an appreciation for their dependency on electricity, and learn how regulating the rate of energy consumption...

  10. Activity: Conserving Electric Energy

    Broader source: Energy.gov [DOE]

    Students participate in two experiments in which they (1) gain an appreciation for their dependency on electricity and (2) learn how regulating the rate of energy consumption makes the energy...

  11. Solar Electric Incentive Program

    Broader source: Energy.gov [DOE]

    Energy Trust of Oregon’s Solar Electric Incentive Program, launched in May 2003, is available to customers of Pacific Power and PGE who install new photovoltaic (PV) systems on new or existing...

  12. Electric Transmission System Workshop

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

    Lauren Azar Senior Advisor to Secretary Chu November 2, 2012 Electric Transmission System ... Can we agree on several key design attributes for the future grid? Taking Action in the ...

  13. Electricity Transmission, A Primer

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

    ... the power from low-cost, mine- mouth coal power plants and wind generators in Wyoming. ... As a result, the transmission system helps to insulate electricity consumers from the ...

  14. Annual Power Electric

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Electric Power Annual Update Revision Data for 2014 updated: February 16, 2016 February ... Table 8.11.A. U.S. Transmission Circuit Outages by Type and NERC region Table 8.11.B. ...

  15. Micromachined electrical cauterizer

    DOE Patents [OSTI]

    Lee, Abraham P.; Krulevitch, Peter A.; Northrup, M. Allen

    1999-01-01

    A micromachined electrical cauterizer. Microstructures are combined with microelectrodes for highly localized electro cauterization. Using boron etch stops and surface micromachining, microneedles with very smooth surfaces are made. Micromachining also allows for precision placement of electrodes by photolithography with micron sized gaps to allow for concentrated electric fields. A microcauterizer is fabricated by bulk etching silicon to form knife edges, then parallelly placed microelectrodes with gaps as small as 5 .mu.m are patterned and aligned adjacent the knife edges to provide homeostasis while cutting tissue. While most of the microelectrode lines are electrically insulated from the atmosphere by depositing and patterning silicon dioxide on the electric feedthrough portions, a window is opened in the silicon dioxide to expose the parallel microelectrode portion. This helps reduce power loss and assist in focusing the power locally for more efficient and safer procedures.

  16. Electrically conductive material

    DOE Patents [OSTI]

    Singh, Jitendra P.; Bosak, Andrea L.; McPheeters, Charles C.; Dees, Dennis W.

    1993-01-01

    An electrically conductive material for use in solid oxide fuel cells, electrochemical sensors for combustion exhaust, and various other applications possesses increased fracture toughness over available materials, while affording the same electrical conductivity. One embodiment of the sintered electrically conductive material consists essentially of cubic ZrO.sub.2 as a matrix and 6-19 wt. % monoclinic ZrO.sub.2 formed from particles having an average size equal to or greater than about 0.23 microns. Another embodiment of the electrically conductive material consists essentially at cubic ZrO.sub.2 as a matrix and 10-30 wt. % partially stabilized zirconia (PSZ) formed from particles having an average size of approximately 3 microns.

  17. Electrically conductive material

    DOE Patents [OSTI]

    Singh, J.P.; Bosak, A.L.; McPheeters, C.C.; Dees, D.W.

    1993-09-07

    An electrically conductive material is described for use in solid oxide fuel cells, electrochemical sensors for combustion exhaust, and various other applications possesses increased fracture toughness over available materials, while affording the same electrical conductivity. One embodiment of the sintered electrically conductive material consists essentially of cubic ZrO[sub 2] as a matrix and 6-19 wt. % monoclinic ZrO[sub 2] formed from particles having an average size equal to or greater than about 0.23 microns. Another embodiment of the electrically conductive material consists essentially at cubic ZrO[sub 2] as a matrix and 10-30 wt. % partially stabilized zirconia (PSZ) formed from particles having an average size of approximately 3 microns. 8 figures.

  18. Electric current locator

    DOE Patents [OSTI]

    King, Paul E.; Woodside, Charles Rigel

    2012-02-07

    The disclosure herein provides an apparatus for location of a quantity of current vectors in an electrical device, where the current vector has a known direction and a known relative magnitude to an input current supplied to the electrical device. Mathematical constants used in Biot-Savart superposition equations are determined for the electrical device, the orientation of the apparatus, and relative magnitude of the current vector and the input current, and the apparatus utilizes magnetic field sensors oriented to a sensing plane to provide current vector location based on the solution of the Biot-Savart superposition equations. Description of required orientations between the apparatus and the electrical device are disclosed and various methods of determining the mathematical constants are presented.

  19. Electricity | Department of Energy

    Energy Savers [EERE]

    And we see how the city of Hoboken, New Jersey is preparing for electric emergencies. March 17, 2016 Dr. Imre Gyuk -- pictured speaking at a Green Mountain Power energy storage ...

  20. National Electricity Delivery Division

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

    Electricity Delivery Division Julie Ann Smith, PhD September 24, 2015 The Federal Indian ... Tradition Thank you Julie Ann Smith, PhD U.S. Department of Energy ...

  1. EIA - State Electricity Profiles

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    538,800 35 Average retail price (centskWh) 33.43 1 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  2. EIA - State Electricity Profiles

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

    684,481 33 Average retail price (centskWh) 8.68 39 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  3. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    20,316,681 2 Average retail price (centskWh) 8.09 46 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  4. EIA - State Electricity Profiles

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

    28,310 49 Average retail price (centskWh) 15.41 5 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  5. EIA - State Electricity Profiles

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    1,576,943 20 Average retail price (centskWh) 9.17 33 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  6. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    34,883,315 1 Average retail price (centskWh) 8.94 37 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  7. EIA - State Electricity Profiles

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    1,255,974 22 Average retail price (centskWh) 8.18 43 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  8. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    3,151,592 10 Average retail price (centskWh) 12.65 11 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  9. EIA - State Electricity Profiles

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    33,870 48 Average retail price (centskWh) 12.11 12 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  10. EIA - State Electricity Profiles

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

    696,6330 32 Average retail price (centskWh) 7.65 50 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  11. EIA - State Electricity Profiles

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    1,763,652 19 Average retail price (centskWh) 9.60 27 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  12. EIA - State Electricity Profiles

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    2,364,746 13 Average retail price (centskWh) 8.15 44 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  13. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    1,181,447 24 Average retail price (centskWh) 9.73 23 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  14. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    138,573,884 Average retail price (centskWh) 10.44 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  15. EIA - State Electricity Profiles

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    1,227,421 23 Average retail price (centskWh) 8.35 42 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  16. EIA - State Electricity Profiles

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    253,513 39 Average retail price (centskWh) 17.46 2 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  17. EIA - State Electricity Profiles

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

    201,071 40 Average retail price (centskWh) 10.18 19 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  18. EIA - State Electricity Profiles

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    11,180,448 3 Average retail price (centskWh) 15.15 8 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  19. EIA - State Electricity Profiles

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

    60,865 47 Average retail price (centskWh) 10.16 20 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  20. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    1,388,386 21 Average retail price (centskWh) 7.76 49 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  1. EIA - State Electricity Profiles

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

    844,760 29 Average retail price (centskWh) 12.10 13 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  2. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    2,463,339 11 Average retail price (centskWh) 9.40 29 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  3. EIA - State Electricity Profiles

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

    944,590 27 Average retail price (centskWh) 7.13 51 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  4. EIA - State Electricity Profiles

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

    1,123,692 25 Average retail price (centskWh) 9.52 28 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  5. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    use 7,958,621 4 Average retail price (centskWh) 9.06 35 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  6. EIA - State Electricity Profiles

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

    89 51 Average retail price (centskWh) 9.05 36 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  7. Electric Power Annual 2014

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Electric industry sales to ultimate customers statistics by state State Sales to ultimate customers (million kWh) Revenue (thousand dollars) Customers Alabama 90,494 8,386,390 ...

  8. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    4,565,846 8 Average retail price (centskWh) 10.03 22 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  9. EIA - State Electricity Profiles

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    2,117,420 17 Average retail price (centskWh) 10.57 17 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  10. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    83,636 46 Average retail price (centskWh) 10.06 21 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  11. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    391,720 37 Average retail price (centskWh) 8.15 45 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  12. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    5,462 50 Average retail price (centskWh) 14.57 9 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  13. EIA - State Electricity Profiles

    Gasoline and Diesel Fuel Update (EIA)

    5,375,185 5 Average retail price (centskWh) 10.77 16 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  14. EIA - State Electricity Profiles

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    3,439,427 9 Average retail price (centskWh) 9.36 30 kWh Kilowatthours. Sources: U.S. Energy Information Administration, Form EIA-860, "Annual Electric Generator Report." ...

  15. Schlumberger Electricity Metering | Open Energy Information

    Open Energy Info (EERE)

    Electricity Metering Jump to: navigation, search Name: Schlumberger Electricity Metering Place: Oconee, South Carolina Product: Manufacturer of electricity meters. Coordinates:...

  16. PNNL Electricity Infrastructure Operations Center | Open Energy...

    Open Energy Info (EERE)

    Electricity Infrastructure Operations Center Jump to: navigation, search Logo: Electricity Infrastructure Operations Center Name Electricity Infrastructure Operations Center...

  17. PNNL Electricity Infrastructure Operations Center | Open Energy...

    Open Energy Info (EERE)

    PNNL Electricity Infrastructure Operations Center (Redirected from Electricity Infrastructure Operations Center) Jump to: navigation, search Logo: Electricity Infrastructure...

  18. Electric Power Annual 2014

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

    Electric Power Annual 2014 February 2016 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | Electric Power Annual This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States Government. U.S.

  19. Renewable Electricity Futures (Presentation)

    SciTech Connect (OSTI)

    Hand, M. M.

    2012-08-01

    This presentation library summarizes findings of NREL's Renewable Electricity Futures study, published in June 2012. RE Futures investigated the challenges and impacts of achieving very high renewable electricity generation levels in the contiguous United States by 2050. It was presented to the 2012 Western Conference of Public Service Commissioners, during their June, 2012, meeting. The Western Conference of Public Service Commissioners is a regional association within the National Association of Regulatory Utility Commissioners (NARUC).

  20. Ion electric propulsion unit

    DOE Patents [OSTI]

    Light, Max E; Colestock, Patrick L

    2014-01-28

    An electron cyclotron resonance (ECR) thruster is disclosed having a plasma chamber which is electrically biased with a positive voltage. The chamber bias serves to efficiently accelerate and expel the positive ions from the chamber. Electrons follow the exiting ions, serving to provide an electrically neutral exhaust plume. In a further embodiment, a downstream shaping magnetic field serves to further accelerate and/or shape the exhaust plume.

  1. Electrically charged targets

    DOE Patents [OSTI]

    Goodman, Ronald K.; Hunt, Angus L.

    1984-01-01

    Electrically chargeable laser targets and method for forming such charged targets in order to improve their guidance along a predetermined desired trajectory. This is accomplished by the incorporation of a small amount of an additive to the target material which will increase the electrical conductivity thereof, and thereby enhance the charge placed upon the target material for guidance thereof by electrostatic or magnetic steering mechanisms, without adversely affecting the target when illuminated by laser energy.

  2. Electricity Monthly Update

    Gasoline and Diesel Fuel Update (EIA)

    Resource Use: June 2016 Supply and fuel consumption In this section, we look at the resources used to produce electricity. Generating units are chosen to run primarily on their operating costs, of which fuel costs account for the lion's share. Therefore, we present below, electricity generation output by fuel type and generator type. Since the generator/fuel mix of utilities varies significantly by region, we also present generation output by region. Generation output by region By fuel type By

  3. Electricity Monthly Update

    Gasoline and Diesel Fuel Update (EIA)

    Regional Wholesale Markets: June 2016 The United States has many regional wholesale electricity markets. Below we look at monthly and annual ranges of on-peak, daily wholesale prices at selected pricing locations and daily peak demand for selected electricity systems in the Nation. The range of daily prices and demand data is shown for the report month and for the year ending with the report month. Prices and demand are shown for six Regional Transmission Operator (RTO) markets: ISO New England

  4. 2012 National Electricity Forum

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

    U.S. Department of Energy U.S. Department of Energy National Electric Transmission Congestion Study Workshop - December 6, 2011 National Electric Transmission Congestion Study Workshop - December 6, 2011 Hilton Philadelphia Airport, 4509 Island Avenue, Philadelphia, PA 19153 Hilton Philadelphia Airport, 4509 Island Avenue, Philadelphia, PA 19153 Agenda Agenda 8:00 am - 9:00 am Registration 9:00 am - 9:20 am DOE Welcome and Presentation David Meyer, US Department of Energy, Session Moderator

  5. Electric power annual 1993

    SciTech Connect (OSTI)

    Not Available

    1994-12-08

    This report presents a summary of electric power industry statistics at national, regional, and state levels: generating capability and additions, net generation, fossil-fuel statistics, retail sales and revenue, finanical statistics, environmental statistics, power transactions, demand side management, nonutility power producers. Purpose is to provide industry decisionmakers, government policymakers, analysts, and the public with historical data that may be used in understanding US electricity markets.

  6. Salem Electric | Open Energy Information

    Open Energy Info (EERE)

    Electric Place: Oregon Phone Number: (503) 362-3601 Website: www.salemelectric.com Facebook: https:www.facebook.compagesSalem-Electric117577414968337 Outage Hotline: (503)...

  7. Rural Utilities Service Electric Program

    Broader source: Energy.gov [DOE]

    The Rural Utilities Service Electric Program’s loans and loan guarantees finance the construction of electric distribution, transmission, and generation facilities, including system improvements...

  8. NREL: Electricity Integration Research - Facilities

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

    Facilities NREL's electricity integration research is conducted in state-of-the-art ... reliable integration of renewable electricity, fuel production, storage, and building ...

  9. Electricity Delivery and Energy Reliability

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

    Delivery and Energy Reliability The Office of Electricity Delivery and Energy Reliability ... to energy supply disruptions, such as electricity and fuel outages. * Smart Grid (14.4 ...

  10. Tidal Electric | Open Energy Information

    Open Energy Info (EERE)

    Tidal Electric Place: London, Greater London, United Kingdom Zip: SW19 8UY Product: Developed a technology named 'tidal lagoons' to build tidal electric projects. Coordinates:...

  11. Electrical Techniques | Open Energy Information

    Open Energy Info (EERE)

    fluid type and phase state of the pore water Thermal: Resistivity influenced by temperature Dictionary.png Electrical Techniques: Electrical techniques aim to image the...

  12. Electric Metering | Department of Energy

    Office of Environmental Management (EM)

    and comparison of data on electricity consumption for overhead lighting and power outlets. ... reducing user controlled electricity consumption at Forrestal by 1,000,000 KWh per year ...

  13. Fortune Electric | Open Energy Information

    Open Energy Info (EERE)

    Fortune Electric Jump to: navigation, search Name: Fortune Electric Place: Taoyuan,Taiwan, Taiwan Product: Taiwanese transformer manufacturer is also engaged in the development of...

  14. Hartford Electric | Open Energy Information

    Open Energy Info (EERE)

    Electric Jump to: navigation, search Name: Hartford Electric Place: Wisconsin Phone Number: (262) 670-3700 Website: hartfordelectric.org Outage Hotline: (262) 670-3710 or (262)...

  15. Electric-Drive Vehicle Basics (Brochure)

    SciTech Connect (OSTI)

    Not Available

    2011-04-01

    Describes the basics of electric-drive vehicles, including hybrid electric vehicles, plug-in hybrid electric vehicles, all-electric vehicles, and the various charging options.

  16. Lakes, Electricity and You | Department of Energy

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

    Lakes, Electricity and You Lakes, Electricity and You Why It's So Important That Lakes Are Used To Generate Electricity PDF icon Lakes, Electricity and You More Documents & ...

  17. Methane flux from mangrove sediments along the southwestern coast of Puerto Rico

    SciTech Connect (OSTI)

    Sotomayor, D.; Corredor, J.E.; Morell, J.M. )

    1994-03-01

    Although the sediments of coastal marine mangrove forests have been considered a minor source of atmospheric methane, these estimate have been based on sparse data from similar areas. We have gathered evidence that shows that external nutrient and freshwater loading in mangrove sediments may have a significant effect on methane flux. Experiments were performed to examine methane fluxes from anaerobic sediments in a mangrove forest subjected to secondary sewage effluents on the southwestern coast of Puerto Rico. Emission rates were measured in situ using a static chamber technique, and subsequent laboratory analysis of samples was by gas chromatography using a flame ionization detector. Results indicate that methane flux rates were lowest at the landward fringe nearest to the effluent discharge, higher in the seaward fringe occupied by red mangroves, and highest in the transition zone between black and red mangrove communities, with average values of 4 mg CH[sub 4] m[sup [minus]2] d[sup [minus]1], 42 mg CH[sub 4] m[sup [minus]2] d[sup [minus]1], and 82 mg CH[sub 4] m[sup [minus]2] d[sup [minus]1], respectively. Overall mean values show these sediments may emit as much as 40 times more methane than unimpacted pristine areas. Pneumatophores of Aviciennia germinans have been found to serve as conduits to the atmosphere for this gas. Fluctuating water level overlying the mangrove sediment is an important environmental factor controlling seasonal and interannual CH[sub 4] flux variations. Environmental controls such as freshwater inputs and increased nutrient loading influence in situ methane emissions from these environments. 34 refs., 3 figs., 3 tabs.

  18. Probing the deep critical zone beneath the Luquillo Experimental Forest, Puerto Rico

    SciTech Connect (OSTI)

    Buss, Heather; Brantley, S. L.; Scatena, Fred; Bazilevskaya, Ekaterina; Blum, Alex; Schulz, M; Jimenez, M; White, Art; Rother, Gernot; Cole, David

    2013-01-01

    Recent work has suggested that weathering processes occurring in the subsurface produce the majority of silicate weathering products discharged to the world s oceans, thereby exerting a primary control on global temperature via the well-known positive feedback between silicate weathering and CO2. In addition, chemical and physical weathering processes deep within the critical zone create aquifers and control groundwater chemistry, watershed geometry and regolith formation rates. Despite this, most weathering studies are restricted to the shallow critical zone (e.g., soils, outcrops). Here we investigate the chemical weathering, fracturing and geomorphology of the deep critical zone in the Bisley watershed in the Luquillo Critical Zone Observatory, Puerto Rico, from two boreholes drilled to 37.2 and 27.0 m depth, from which continuous core samples were taken. Corestones exposed aboveground were also sampled. Weathered rinds developed on exposed corestones and along fracture surfaces on subsurface rocks slough off of exposed corestones once rinds attain a thickness up to ~1 cm, preventing the corestones from rounding due to diffusion limitation. Such corestones at the land surface are assumed to be what remains after exhumation of similar, fractured bedrock pieces that were observed in the drilled cores between thick layers of regolith. Some of these subsurface corestones are massive and others are highly fractured, whereas aboveground corestones are generally massive with little to no apparent fracturing. Subsurface corestones are larger and less fractured in the borehole drilled on a road where it crosses a ridge compared to the borehole drilled where the road crosses the stream channel. Both borehole profiles indicate that the weathering zone extends to well below the stream channel in this upland catchment; hence weathering depth is not controlled by the stream level within the catchment and not all of the water in the watershed is discharged to the stream.

  19. In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis. Final report, volume 1. Development of experimental flow control loop, data analysis and plant monitoring

    SciTech Connect (OSTI)

    Upadhyaya, Belle; Hines, J. Wesley; Damiano, Brian; Mehta, Chaitanya; Collins, Price; Lish, Matthew; Cady, Brian; Lollar, Victor; de Wet, Dane; Bayram, Duygu

    2015-12-15

    The research and development under this project was focused on the following three major objectives: Objective 1: Identification of critical in-vessel SMR components for remote monitoring and development of their low-order dynamic models, along with a simulation model of an integral pressurized water reactor (iPWR). Objective 2: Development of an experimental flow control loop with motor-driven valves and pumps, incorporating data acquisition and on-line monitoring interface. Objective 3: Development of stationary and transient signal processing methods for electrical signatures, machinery vibration, and for characterizing process variables for equipment monitoring. This objective includes the development of a data analysis toolbox. The following is a summary of the technical accomplishments under this project: - A detailed literature review of various SMR types and electrical signature analysis of motor-driven systems was completed. A bibliography of literature is provided at the end of this report. Assistance was provided by ORNL in identifying some key references. - A review of literature on pump-motor modeling and digital signal processing methods was performed. - An existing flow control loop was upgraded with new instrumentation, data acquisition hardware and software. The upgrading of the experimental loop included the installation of a new submersible pump driven by a three-phase induction motor. All the sensors were calibrated before full-scale experimental runs were performed. - MATLAB-Simulink model of a three-phase induction motor and pump system was completed. The model was used to simulate normal operation and fault conditions in the motor-pump system, and to identify changes in the electrical signatures. - A simulation model of an integral PWR (iPWR) was updated and the MATLAB-Simulink model was validated for known transients. The pump-motor model was interfaced with the iPWR model for testing the impact of primary flow perturbations (upsets) on

  20. Electric sales and revenue 1996

    SciTech Connect (OSTI)

    1997-12-01

    Information is provided on electricity sales, associated revenue, average revenue per kilowatthour sold, and number of consumers throughout the US. The data provided in the Electric Sales and Revenue are presented at the national, Census division, State, and electric utility levels. The information is based on annual data reported by electric utilities for the calendar year ending December 31, 1996. 16 figs., 20 tabs.

  1. Reliability of Electrical Interconnects (Presentation)

    SciTech Connect (OSTI)

    Devoto, D.

    2014-06-01

    This presentation discusses the status of NREL's research on the reliability of electrical interconnects.

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

    SciTech Connect (OSTI)

    Ade, Brian J; Gauld, Ian C

    2011-10-01

    in MOX fuel is generally obtained from reprocessed irradiated nuclear fuel, whereas weapons-grade plutonium is obtained from decommissioned nuclear weapons material and thus has a different plutonium (and other actinides) concentration. Using MOX fuel instead of UOX fuel has potential impacts on the neutronic performance of the nuclear fuel and the design of the nuclear fuel must take these differences into account. Each of the plutonium sources (RG and WG) has different implications on the neutronic behavior of the fuel because each contains a different blend of plutonium nuclides. The amount of heat and the number of neutrons produced from fission of plutonium nuclides is different from fission of {sup 235}U. These differences in UOX and MOX do not end at discharge of the fuel from the reactor core - the short- and long-term storage of MOX fuel may have different requirements than UOX fuel because of the different discharged fuel decay heat characteristics. The research documented in this report compares MOX and UOX fuel during storage and disposal of the fuel by comparing decay heat rates for typical pressurized water reactor (PWR) and boiling water reactor (BWR) fuel assemblies with and without weapons-grade (WG) and reactor-grade (RG) MOX fuel.

  3. Electric sales and revenue 1994

    SciTech Connect (OSTI)

    1995-11-01

    The Electric Sales and Revenue is prepared by the Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); US Department of Energy. Information is provided on electricity sales, associated revenue, average revenue per kilowatthour sold, and number of consumers throughout the United States. The data provided in the Electric Sales and Revenue are presented at the national, Census division, State, and electric utility levels. The information is based on annual data reported by electric utilities for the calendar year ending December 31, 1994.

  4. Electric sales and revenue 1997

    SciTech Connect (OSTI)

    1998-10-01

    The Electric Sales and Revenue is prepared by the Electric Power Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); US Department of Energy. Information is provided on electricity sales, associated revenue, average revenue per kilowatthour sold, and number of consumers throughout the US. The data provided in the Electric Sales and Revenue are presented at the national, Census division, State, and electric utility levels. The information is based on annual data reported by electric utilities for the calendar year ending December 31, 1997. 16 figs., 17 tabs.

  5. Electric fluid pump

    DOE Patents [OSTI]

    Van Dam, Jeremy Daniel; Turnquist, Norman Arnold; Raminosoa, Tsarafidy; Shah, Manoj Ramprasad; Shen, Xiaochun

    2015-09-29

    An electric machine is presented. The electric machine includes a hollow rotor; and a stator disposed within the hollow rotor, the stator defining a flow channel. The hollow rotor includes a first end portion defining a fluid inlet, a second end portion defining a fluid outlet; the fluid inlet, the fluid outlet, and the flow channel of the stator being configured to allow passage of a fluid from the fluid inlet to the fluid outlet via the flow channel; and wherein the hollow rotor is characterized by a largest cross-sectional area of hollow rotor, and wherein the flow channel is characterized by a smallest cross-sectional area of the flow channel, wherein the smallest cross-sectional area of the flow channel is at least about 25% of the largest cross-sectional area of the hollow rotor. An electric fluid pump and a power generation system are also presented.

  6. Fluid cooled electrical assembly

    DOE Patents [OSTI]

    Rinehart, Lawrence E.; Romero, Guillermo L.

    2007-02-06

    A heat producing, fluid cooled assembly that includes a housing made of liquid-impermeable material, which defines a fluid inlet and a fluid outlet and an opening. Also included is an electrical package having a set of semiconductor electrical devices supported on a substrate and the second major surface is a heat sink adapted to express heat generated from the electrical apparatus and wherein the second major surface defines a rim that is fit to the opening. Further, the housing is constructed so that as fluid travels from the fluid inlet to the fluid outlet it is constrained to flow past the opening thereby placing the fluid in contact with the heat sink.

  7. Simple Electric Vehicle Simulation

    Energy Science and Technology Software Center (OSTI)

    1993-07-29

    SIMPLEV2.0 is an electric vehicle simulation code which can be used with any IBM compatible personal computer. This general purpose simulation program is useful for performing parametric studies of electric and series hybrid electric vehicle performance on user input driving cycles.. The program is run interactively and guides the user through all of the necessary inputs. Driveline components and the traction battery are described and defined by ASCII files which may be customized by themore » user. Scaling of these components is also possible. Detailed simulation results are plotted on the PC monitor and may also be printed on a printer attached to the PC.« less

  8. Electric power emergency handbook

    SciTech Connect (OSTI)

    Labadie, J.R.

    1980-09-01

    The Emergency Electric Power Administration's Emergency Operations Handbook is designed to provide guidance to the EEPA organization. It defines responsibilities and describes actions performed by the government and electric utilities in planning for, and in operations during, national emergencies. The EEPA Handbook is reissued periodically to describe organizational changes, to assign new duties and responsibilities, and to clarify the responsibilities of the government to direct and coordinate the operations of the electric utility industry under emergencies declared by the President. This Handbook is consistent with the assumptions, policies, and procedures contained in the National Plan for Emergency Preparedness. Claimancy and restoration, communications and warning, and effects of nuclear weapons are subjects covered in the appendices.

  9. Thermoacoustic magnetohydrodynamic electrical generator

    SciTech Connect (OSTI)

    Wheatley, J.C.; Swift, G.W.; Migliori, A.

    1986-07-08

    A thermoacoustic magnetohydrodynamic electrical generator is described comprising a magnet having a magnetic field, an elongate hollow housing containing an electrically conductive liquid and a thermoacoustic structure positioned in the liquid, heat exchange means thermally connected to the thermoacoustic structure for inducing the liquid to oscillate at an acoustic resonant frequency within the housing. The housing is positioned in the magnetic field and oriented such that the direction of the magnetic field and the direction of oscillatory motion of the liquid are substantially orthogonal to one another, first and second electrical conductor means connected to the liquid on opposite sides of the housing along an axis which is substantially orthogonal to both the direction of the magnetic field and the direction of oscillatory motion of the liquid, an alternating current output signal is generated in the conductor means at a frequency corresponding to the frequency of the oscillatory motion of the liquid.

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

    SciTech Connect (OSTI)

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

    1993-10-01

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

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

    SciTech Connect (OSTI)

    Hillner, E.

    1980-01-01

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

  12. EIA - State Electricity Profiles

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

    Alabama Table 1. 2014 Summary statistics (Alabama) Item Value Rank Primary energy source Natural gas Net summer capacity (megawatts) 31,953 8 Electric utilities 23,050 8 IPP & CHP 8,903 11 Net generation (megawatthours) 149,340,447 6 Electric utilities 112,340,555 3 IPP & CHP 36,999,892 10 Emissions Sulfur dioxide (short tons) 152,225 8 Nitrogen oxide (short tons) 61,909 13 Carbon dioxide (thousand metric tons) 67,635 10 Sulfur dioxide (lbs/MWh) 2.0 19 Nitrogen oxide (lbs/MWh) 0.8 38

  13. Renewable Electricity Futures (Presentation)

    SciTech Connect (OSTI)

    DeMeo, E.

    2012-08-01

    This presentation library summarizes findings of NREL's Renewable Electricity Futures study, published in June 2012. RE Futures investigated the challenges and impacts of achieving very high renewable electricity generation levels in the contiguous United States by 2050. It was presented at Wind Powering America States Summit. The Summit, which follows the American Wind Energy Association's (AWEA's) annual WINDPOWER Conference and Exhibition, provides state Wind Working Groups, state energy officials, U.S. Energy Department and national laboratory representatives, and professional and institutional partners an opportunity to review successes, opportunities, and challenges for wind energy and plan future collaboration.

  14. Renewable Electricity Futures (Presentation)

    SciTech Connect (OSTI)

    Mai, T.

    2012-08-01

    This presentation library summarizes findings of NREL's Renewable Electricity Futures study, published in June 2012. RE Futures investigated the challenges and impacts of achieving very high renewable electricity generation levels in the contiguous United States by 2050. It was presented at the 2012 RE AMP Annual Meeting. RE-AMP is an active network of 144 nonprofits and foundations across eight Midwestern states working on climate change and energy policy with the goal of reducing global warming pollution economy-wide 80% by 2050.

  15. Liquid metal electric pump

    DOE Patents [OSTI]

    Abbin, J.P.; Andraka, C.E.; Lukens, L.L.; Moreno, J.B.

    1992-01-14

    An electrical pump for pumping liquid metals to high pressures in high temperature environments without the use of magnets or moving mechanical parts. The pump employs a non-porous solid electrolyte membrane, typically ceramic, specific to the liquid metal to be pumped. A DC voltage is applied across the thickness of the membrane causing ions to form and enter the membrane on the electrically positive surface, with the ions being neutralized on the opposite surface. This action provides pumping of the liquid metal from one side of the non-porous solid electrolyte membrane to the other. 3 figs.

  16. Electrically conductive composite material

    DOE Patents [OSTI]

    Clough, Roger L.; Sylwester, Alan P.

    1989-01-01

    An electrically conductive composite material is disclosed which comprises a conductive open-celled, low density, microcellular carbon foam filled with a non-conductive polymer or resin. The composite material is prepared in a two-step process consisting of first preparing the microcellular carbon foam from a carbonizable polymer or copolymer using a phase separation process, then filling the carbon foam with the desired non-conductive polymer or resin. The electrically conductive composites of the present invention has a uniform and consistant pattern of filler distribution, and as a result is superior over prior art materials when used in battery components, electrodes, and the like.

  17. Electric Adsorption Heat Pump for Electric Vehicles: Electric-Powered Adsorption Heat Pump for Electric Vehicles

    SciTech Connect (OSTI)

    2011-11-21

    HEATS Project: PNNL is developing a new class of advanced nanomaterial called an electrical metal organic framework (EMOF) for EV heating and cooling systems. The EMOF would function similar to a conventional heat pump, which circulates heat or cold to the cabin as needed. However, by directly controlling the EMOF's properties with electricity, the PNNL design is expected to use much less energy than traditional heating and cooling systems. The EMOF-based heat pumps would be light, compact, efficient, and run using virtually no moving parts.

  18. Electricity Monthly Update

    Gasoline and Diesel Fuel Update (EIA)

    Electric Power Sector Coal Stocks: June 2016 Stocks In June, U.S. coal stockpiles decreased to 185 million tons, down 5.2% from the previous month. As a whole, U.S. coal stockpiles are still at relatively high levels due to the mild winter experienced earlier in the year and also becaue coal continues to lose market share to natural gas in most regions of the country. Days of burn Days of burn by coal rank Capacity by days of burn The average number of days of burn held at electric power plants

  19. Electricity Monthly Update

    Gasoline and Diesel Fuel Update (EIA)

    Electricity Monthly Update Explained Highlights The Highlights page features in the center a short article about a major event or an informative topic. The left column contains bulleted highlights at the top and key indicators in a table and graphics - data you might be interested in at a glance. The right column is used for navigation. End-Use: Retail Rates/Prices and Consumption The second section presents statistics on end-use: retail rates/prices and consumption of electricity. End-use data

  20. 2012 National Electricity Forum

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

    1 U.S. Department of Energy U.S. Department of Energy National Electric Transmission Congestion Study Workshop - December 8, 2011 National Electric Transmission Congestion Study Workshop - December 8, 2011 Hilton St. Louis Airport, 10330 Natural Bridge Road, St. Louis, Missouri 63134 Hilton St. Louis Airport, 10330 Natural Bridge Road, St. Louis, Missouri 63134 Agenda Agenda 8:00 am - 9:00 am Registration 9:00 am - 9:20 am DOE Welcome and Presentation David Meyer, US Department of Energy,

  1. Liquid metal electric pump

    DOE Patents [OSTI]

    Abbin, Joseph P.; Andraka, Charles E.; Lukens, Laurance L.; Moreno, James B.

    1992-01-01

    An electrical pump for pumping liquid metals to high pressures in high temperature environments without the use of magnets or moving mechanical parts. The pump employs a non-porous solid electrolyte membrane, typically ceramic, specific to the liquid metal to be pumped. A DC voltage is applied across the thickness of the membrane causing ions to form and enter the membrane on the electrically positive surface, with the ions being neutralized on the opposite surface. This action provides pumping of the liquid metal from one side of the non-porous solid electrolyte membrane to the other.

  2. Electrically conductive composite material

    DOE Patents [OSTI]

    Clough, R.L.; Sylwester, A.P.

    1989-05-23

    An electrically conductive composite material is disclosed which comprises a conductive open-celled, low density, microcellular carbon foam filled with a non-conductive polymer or resin. The composite material is prepared in a two-step process consisting of first preparing the microcellular carbon foam from a carbonizable polymer or copolymer using a phase separation process, then filling the carbon foam with the desired non-conductive polymer or resin. The electrically conductive composites of the present invention has a uniform and consistent pattern of filler distribution, and as a result is superior over prior art materials when used in battery components, electrodes, and the like. 2 figs.

  3. Electrically conductive composite material

    DOE Patents [OSTI]

    Clough, R.L.; Sylwester, A.P.

    1988-06-20

    An electrically conductive composite material is disclosed which comprises a conductive open-celled, low density, microcellular carbon foam filled with a non-conductive polymer or resin. The composite material is prepared in a two-step process consisting of first preparing the microcellular carbon foam from a carbonizable polymer or copolymer using a phase separation process, then filling the carbon foam with the desired non-conductive polymer or resin. The electrically conductive composites of the present invention has a uniform and consistent pattern of filler distribution, and as a result is superior over prior art materials when used in battery components, electrodes, and the like. 2 figs.

  4. Liquid metal thermal electric converter

    DOE Patents [OSTI]

    Abbin, Joseph P.; Andraka, Charles E.; Lukens, Laurance L.; Moreno, James B.

    1989-01-01

    A liquid metal thermal electric converter which converts heat energy to electrical energy. The design of the liquid metal thermal electric converter incorporates a unique configuration which directs the metal fluid pressure to the outside of the tube which results in the structural loads in the tube to be compressive. A liquid metal thermal electric converter refluxing boiler with series connection of tubes and a multiple cell liquid metal thermal electric converter are also provided.

  5. Electric Metering | Department of Energy

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

    Electric Metering Electric Metering Saving Money by Saving Energy The Department of Energy has installed meters in the James Forrestal Building that will enable DOE to measure electricity use and costs in its headquarters facility. You may explore this data further by visiting our Forrestal Metering Dashboard at the following website: http://forrestal.nrel.gov The Forrestal electric meters provide daily read-outs and comparison of data on electricity consumption for overhead lighting and power

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

    SciTech Connect (OSTI)

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

    2008-05-05

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

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

    SciTech Connect (OSTI)

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

    2015-09-01

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

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

    SciTech Connect (OSTI)

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

    1981-06-01

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

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

    SciTech Connect (OSTI)

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

    1987-08-01

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

  10. Electricity Portfolio Simulation Model

    Energy Science and Technology Software Center (OSTI)

    2005-09-01

    Stakeholders often have competing interests when selecting or planning new power plants. The purpose of developing this preliminary Electricity Portfolio Simulation Model (EPSim) is to provide a first cut, dynamic methodology and approach to this problem, that can subsequently be refined and validated, that may help energy planners, policy makers, and energy students better understand the tradeoffs associated with competing electricity portfolios. EPSim allows the user to explore competing electricity portfolios annually from 2002 tomore » 2025 in terms of five different criteria: cost, environmental impacts, energy dependence, health and safety, and sustainability. Four additional criteria (infrastructure vulnerability, service limitations, policy needs and science and technology needs) may be added in future versions of the model. Using an analytic hierarchy process (AHP) approach, users or groups of users apply weights to each of the criteria. The default energy assumptions of the model mimic Department of Energy’s (DOE) electricity portfolio to 2025 (EIA, 2005). At any time, the user can compare alternative portfolios to this reference case portfolio.« less

  11. Recirculating electric air filter

    DOE Patents [OSTI]

    Bergman, Werner

    1986-01-01

    An electric air filter cartridge has a cylindrical inner high voltage eleode, a layer of filter material, and an outer ground electrode formed of a plurality of segments moveably connected together. The outer electrode can be easily opened to remove or insert filter material. Air flows through the two electrodes and the filter material and is exhausted from the center of the inner electrode.

  12. Recirculating electric air filter

    DOE Patents [OSTI]

    Bergman, W.

    1985-01-09

    An electric air filter cartridge has a cylindrical inner high voltage electrode, a layer of filter material, and an outer ground electrode formed of a plurality of segments moveably connected together. The outer electrode can be easily opened to remove or insert filter material. Air flows through the two electrodes and the filter material and is exhausted from the center of the inner electrode.

  13. Wind farm electrical system

    DOE Patents [OSTI]

    Erdman, William L.; Lettenmaier, Terry M.

    2006-07-04

    An approach to wind farm design using variable speed wind turbines with low pulse number electrical output. The output of multiple wind turbines are aggregated to create a high pulse number electrical output at a point of common coupling with a utility grid network. Power quality at each individual wind turbine falls short of utility standards, but the aggregated output at the point of common coupling is within acceptable tolerances for utility power quality. The approach for aggregating low pulse number electrical output from multiple wind turbines relies upon a pad mounted transformer at each wind turbine that performs phase multiplication on the output of each wind turbine. Phase multiplication converts a modified square wave from the wind turbine into a 6 pulse output. Phase shifting of the 6 pulse output from each wind turbine allows the aggregated output of multiple wind turbines to be a 24 pulse approximation of a sine wave. Additional filtering and VAR control is embedded within the wind farm to take advantage of the wind farm's electrical impedence characteristics to further enhance power quality at the point of common coupling.

  14. Electric Power Annual 2010

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

    A. Summer Net Internal Demand, Capacity Resources, and Capacity Margins by North American Electric Reliability Corporation Region, 1999 through 2010" ,"(Megawatts and Percent)" ,"Interconnection","NERC Regional Assesment Area","Net Internal Demand (MW)[1] -- Summer" ,,,"Actual",,,,,,,,,,,,,,,,,,,,,"Projected"

  15. Electric vehicle climate control

    SciTech Connect (OSTI)

    Dauvergne, J.

    1994-04-01

    EVs have insufficient energy sources for a climatic comfort system. The heat rejection of the drivetrain is dispersed in the vehicle (electric motor, batteries, electronic unit for power control). Its level is generally low (no more than 2-kW peaks) and variable according to the trip profile, with no heat rejection at rest and a maximum during regenerative braking. Nevertheless, it must be used for heating. It is not realistic to have the A/C compressor driven by the electric traction motor: the motor does not operate when the vehicle is at rest, precisely when maximum cooling power is required. The same is true for hybrid vehicles during electric operation. It is necessary to develop solutions that use stored onboard energy either from the traction batteries or specific storage source. In either case, it is necessary to design the climate control system to use the energy efficiently to maximize range and save weight. Heat loss through passenger compartment seals and the walls of the passenger compartment must be limited. Plastic body panes help to reduce heat transfer, and heat gain is minimized with insulating glazing. This article describes technical solutions to solve the problem of passenger thermal comfort. However, the heating and A/C systems of electrically operated vehicles may have marginal performance at extreme outside temperatures.

  16. Geothermal Electricity Production Basics

    Broader source: Energy.gov [DOE]

    Heat from the earth—geothermal energy—heats water that has seeped into underground reservoirs. These reservoirs can be tapped for a variety of uses, depending on the temperature of the water. The energy from high-temperature reservoirs (225°-600°F) can be used to produce electricity.

  17. Electric sales and revenue 1991

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    The Electric Sales and Revenue is prepared by the Survey Management Division, Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); US Department of Energy. This publication provides information about sales of electricity, its associated revenue, and the average revenue per kilowatthour sold to residential, commercial, industrial, and other consumers throughout the United States. Previous publications presented data on typical electric bills at specified consumption levels as well as sales, revenue, and average revenue. The sales of electricity, associated revenue, and average revenue per kilowatthour provided in this report are presented at the national, Census division, State, and electric utility levels.

  18. Electrical Generation for More-Electric Aircraft using Solid...

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

    Aircraft using Solid Oxide Fuel Cells GA Whyatt LA Chick April 2012 PNNL-XXXXX Electrical Generation for More- Electric Aircraft using Solid Oxide Fuel Cells GA Whyatt LA Chick ...

  19. Power Conversion Apparatus and Method for Hybrid Electric and Electric

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

    Vehicle Engines - Energy Innovation Portal Power Conversion Apparatus and Method for Hybrid Electric and Electric Vehicle Engines Oak Ridge National Laboratory Contact ORNL About This Technology Technology Marketing SummaryORNL researchers developed a solution to power source problems in hybrid electric vehicle (HEV) and electric vehicle (EV) engines. These engines typically use voltage source inverters. The conventional type of converter requires costly capacitors, has trouble with high

  20. Fact #874: May 25, 2015 Number of Electric Stations and Electric...

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

    4: May 25, 2015 Number of Electric Stations and Electric Charging Units Increasing - Dataset Fact 874: May 25, 2015 Number of Electric Stations and Electric Charging Units ...