Книги з теми "BWR1"
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Jones, Bethan Wyn. Bwrw blwyddyn. Caernarfon: Gwasg Gwynedd, 1997.
Знайти повний текст джерелаEtherton, Roy. Bwrw lliwiau. Aberystwyth: Gwasg Cambria, 1991.
Знайти повний текст джерела1935-, Owen William, and Ysgol Carreg-lefn, eds. Bwrw cyfrif 'rôl canrif. Carreg-lefn: Corff Llywodraethol Ysgol Gymuned Carreg-lefn, 1999.
Знайти повний текст джерелаKikō, Genshiryoku Anzen Kiban. Teishiji reberu 2PSA no kentō (BWR). [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2005.
Знайти повний текст джерелаTheofanous, T. G. Performance of the liquid reactivity control system in BWRs. Washington, DC: Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
Знайти повний текст джерелаKikō, Genshiryoku Anzen Kiban. Reberu 2 PSA shuhō no seibi (BWR). [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2005.
Знайти повний текст джерелаKikō, Genshiryoku Anzen Kiban, ed. Jishinji reberu 2 PSA no kaiseki (BWR). [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2008.
Знайти повний текст джерелаKikō, Genshiryoku Anzen Kiban, ed. Jishinji reberu 2 PSA no kaiseki (BWR). [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2008.
Знайти повний текст джерелаU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Licensee Performance and Quality Evaluation., ed. BWR and PWR off-normal event descriptions. Washington, DC: Division of Licensee Performance and Quality Evaluation, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1987.
Знайти повний текст джерелаU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Licensee Performance and Quality Evaluation., ed. BWR and PWR off-normal event descriptions. Washington, DC: Division of Licensee Performance and Quality Evaluation, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1987.
Знайти повний текст джерелаChristensen, P. la Cour. A BWR power plant simulator for Barseback. Roskilde, Denmark: Riso National Laboratory, 1985.
Знайти повний текст джерелаU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Licensee Performance and Quality Evaluation, ed. BWR and PWR off-normal event descriptions. Washington, DC: Division of Licensee Performance and Quality Evaluation, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1987.
Знайти повний текст джерелаU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Licensee Performance and Quality Evaluation, ed. BWR and PWR off-normal event descriptions. Washington, DC: Division of Licensee Performance and Quality Evaluation, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1987.
Знайти повний текст джерелаU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs., ed. Standard technical specifications: General Electric Plants, BWR/4. 2nd ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.
Знайти повний текст джерелаU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs., ed. Standard technical specifications: General Electric Plants, BWR/6. 2nd ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.
Знайти повний текст джерелаR, Greene Sherrell, U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution., and Oak Ridge National Laboratory, eds. BWR Mark II ex-vessel corium interaction analyses. Washington, DC: Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1991.
Знайти повний текст джерелаDuce, S. W. Radionuclide buildup in BWR reactor coolant recirculation piping. Washington, D.C: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
Знайти повний текст джерелаU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Standard technical specifications: General Electric plants, BWR/6. Washington, DC: The Office, 1992.
Знайти повний текст джерелаU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs, ed. Standard technical specifications: General Electric Plants, BWR/6. 2nd ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.
Знайти повний текст джерелаU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs., ed. Standard technical specifications: General Electric Plants, BWR/4. 2nd ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.
Знайти повний текст джерелаR, Greene Sherrell, U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution., and Oak Ridge National Laboratory, eds. BWR Mark II ex-vessel corium interaction analyses. Washington, DC: Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1991.
Знайти повний текст джерелаO, Harris D., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Safety., Failure Analysis Associates, and NTS/Structural Mechanics Associates, eds. Probability of failure in BWR reactor coolant piping. Washington, DC: Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986.
Знайти повний текст джерелаU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs, ed. Standard technical specifications: General Electric Plants, BWR/4. 2nd ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.
Знайти повний текст джерелаU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs., ed. Standard technical specifications: General Electric Plants, BWR/6. 2nd ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.
Знайти повний текст джерелаD, Buckley G., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering., and Pacific Northwest Laboratory, eds. Aging assessment of BWR standby liquid control systems. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.
Знайти повний текст джерелаR, Greene Sherrell, U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution., and Oak Ridge National Laboratory, eds. BWR Mark II ex-vessel corium interaction analyses. Washington, DC: Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1991.
Знайти повний текст джерелаSaito, Kiyohide. Tomb F, tomb of BWLH and BWRP: Southeast necropolis Palmyra, Syria. Nara, Japan: Research Center for Silk Roadology, 2001.
Знайти повний текст джерелаWolfgang, Wulff, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and Brookhaven National Laboratory, eds. BWR stability analysis with the BNL engineering plant analyzer. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.
Знайти повний текст джерелаE, Claiborne, Science and Engineering Associates, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Regulatory Applications., eds. Cost analysis for potential BWR Mark I containment improvements. Washington, DC: Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
Знайти повний текст джерелаMirkovic, D. Boron flushing during a BWR anticipated transient without scram. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatroy Commission, 1990.
Знайти повний текст джерелаB, Scott W., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Pacific Northwest Laboratory, and Battelle Memorial Institute, eds. Recriticality in a BWR following a core damage event. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
Знайти повний текст джерелаK, Kirk H., Yakle J, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Sandia National Laboratories, and Science Applications International Corporation, eds. Risk impact of BWR technical specifications requirements during shutdown. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1994.
Знайти повний текст джерелаWagner, K. C. An overview of BWR Mark-I containment venting risk implications. Washington, DC: Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.
Знайти повний текст джерелаWagner, K. C. An overview of BWR Mark-I containment venting risk implications. Washington, DC: Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.
Знайти повний текст джерелаKikō, Genshiryoku Anzen Kiban, ed. Akushidento manejimentso chishiki bēsu seibi ni kansuru hōkokusho: Dētabēsu (BWR). [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2007.
Знайти повний текст джерелаKing, D. B. Beta and gamma dose calculations for PWR and BWR containments. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
Знайти повний текст джерелаKikō, Genshiryoku Anzen Kiban. Kakunō yōki kenzensei ni kansuru kiki no jūyōdo hyōka (BWR). [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2005.
Знайти повний текст джерелаPowers, D. A. A simplified model of decontamination by BWR steam suppression pools. Washington, D.C: Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1997.
Знайти повний текст джерелаL, Humphries L., Sandia National Laboratories, Science Applications International Corporation, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., eds. Final results of the XR2-1 BWR metallic melt relocation experiment. Washington, D.C: Division of Systems Technology, Office of Nuclear regulatory Research, U.S. Nuclear Regulatory Commission, 1997.
Знайти повний текст джерелаLaboratory, Brookhaven National, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., eds. PWR and BWR pressure vessel fluence calculation benchmark problems and solutions. Washington, DC: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2001.
Знайти повний текст джерелаA, Hodge S., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and Oak Ridge National Laboratory, eds. Identification and assessment of BWR in-vessel severe accident mitigation strategies. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.
Знайти повний текст джерелаHowes, John. Ironstone: An international exhibition of contemporary cast iron sculpture = arddangosfa ryngwladol o gerfluniau haearn bwrw. Swansea: Sculpture Cymru, 2010.
Знайти повний текст джерелаDean, R. S. Closeout of IE bulletin 79-26: Boron loss from BWR control blades. Washington, DC: Division of Operational Events Assessment, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1988.
Знайти повний текст джерелаRegulation, U. S. Nuclear Regulatory Commission Office of Nuclear Reactor. Standard technical specifications: General Electric plants, BWR/4 : draft report for comment. [Washington, DC]: The Office, 1991.
Знайти повний текст джерелаU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Standard technical specifications: General Electric plants, BWR/6 : draft report for comment. [Washington, DC]: The Office, 1991.
Знайти повний текст джерелаS, Lee B., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Brookhaven National Laboratory, eds. Aging assessment of Westinghouse PWR and General Electric BWR containment isolation functions. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1996.
Знайти повний текст джерелаKikō, Genshiryoku Anzen Kiban. Kokunai BWR puranto no mizu kagaku no dōkō ni kansuru chōsa hōkokusho. [Tōkyō-to Minato-ku]: Genshiryoku Anzen Kiban Kikō, 2012.
Знайти повний текст джерелаUnited Engineers & Constructors, inc., Oak Ridge National Laboratory, and U.S. Nuclear Regulatory Commission. Office of Resource Management. Cost Analysis Group., eds. Energy economic data base (EEDB) program: Phase VIII update (1986), BWR supplement. Washington, DC: Cost and Statistical Analysis Staff, Office of Resource Management, U.S. Nuclear Regulatory Commission, 1986.
Знайти повний текст джерелаKikō, Genshiryoku Anzen Kiban. Jishinji no reberu 3-PSA no kentō (PWR oyobi BWR): Heisei 20-nendo. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2009.
Знайти повний текст джерелаR, Greene Sherrell, U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution., and Oak Ridge National Laboratory, eds. The Response of BWR Mark II containments to station blackout severe accident sequences. Washington, DC: Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1991.
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