Livros sobre o tema "Nuclear boiling"
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J, Moody F., ed. The thermal-hydraulics of a boiling water nuclear reactor. 2a ed. La Grange Park, Ill., USA: American Nuclear Society, 1993.
Encontre o texto completo da fonte(Bonn, Germany) Kerntechnische Gesellschaft. SWR 1000: Ein zukunftsweisendes Reaktorkonzept : Tagungsbericht = SWR 1000 : a reactor concept for the future : proceedings. Bonn: INFORUM, 1998.
Encontre o texto completo da fonteHawthorne, J. R. Experimental assessments of Gundremmingen RPV archive material for fluence rate effects studies. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.
Encontre o texto completo da fonteShih, Chunkuan, e K. Tien. The development and application of Kuosheng (BWR/6) nuclear power plant TRACE/SNAP model. Washington, DC: U.S. Nuclear Regulatory Commission, Division of Systems Analysis, Office of Nuclear Regulatory Research, 2014.
Encontre o texto completo da fonteNikolaevich, Andreenko Sergeĭ, ed. Peregruzochnye mashiny kanalʹnykh i͡a︡dernykh ėnergeticheskikh reaktorov. Moskva: Ėnergoatomizdat, 1986.
Encontre o texto completo da fonteHawthorne, J. R. Experimental assessments of Gundremmingen RPV archive material for fluence rate effects studies. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering. e Oak Ridge National Laboratory, eds. Boiling-water reactor internals aging degradation study: Phase 1. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering. e Oak Ridge National Laboratory, eds. Boiling-water reactor internals aging degradation study: Phase 1. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering. e Oak Ridge National Laboratory, eds. Boiling-water reactor internals aging degradation study: Phase 1. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Division of Reactor Controls and Human Factors, ed. Knowledge and abilities catalog for nuclear power plant operators: Boiling water reactors. Washington, DC: Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1995.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Division of Human Factors Technology, ed. Knowledge and abilities catalog for nuclear power plant operators: Boiling water reactors. Washington, DC: Division of Human Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1986.
Encontre o texto completo da fonteL, Edson Jerald, Fineman C. F, Idaho National Engineering Laboratory e U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering., eds. Aging study of boiling water reactor high pressure injection systems. Washington, DC: U.S. Nuclear Regulatory Commission, 1995.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs, ed. Standard technical specifications: General Electric Plants, BWR/4. 2a ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs., ed. Standard technical specifications: General Electric Plants, BWR/6. 2a ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.
Encontre o texto completo da fonteGauntt, Randall Owen. The DF-4 fuel damage experiment in ACRR with a BWR control blade and channel box. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
Encontre o texto completo da fonteS, Rohatgi Upendra, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology. e Brookhaven National Laboratory, eds. RAMONA-4B, a computer code with three-dimensional neutron kinetics for BWR and SBWR system transients. Washington, DC: Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs, ed. Standard technical specifications: General Electric Plants, BWR/6. 2a ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs., ed. Standard technical specifications: General Electric Plants, BWR/4. 2a ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.
Encontre o texto completo da fonteGauntt, Randall Owen. The DF-4 fuel damage experiment in ACRR with a BWR control blade and channel box. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission, ed. The establishment and assessment of Chinshan (BWR/4) Nuclear Power Plant TRACE/SNAP model. Washington, DC: U.S. Nuclear Regulatory Commission, 2014.
Encontre o texto completo da fonteA, Gomez, Gallego I, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. e Unidad Eléctrica S. A, eds. Assessment of the turbine trip transient in Cofrentes NPP with TRAC-BF1. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.
Encontre o texto completo da fonteKikō, Genshiryoku Anzen Kiban. BWR puranto tōkeiteki anzen hyōka shuhō no seibi: Futashikasa kaiseki kinō no kumikomi to jikki benchi māku mondai kaiseki : Heisei 21-nendo. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2010.
Encontre o texto completo da fonteH, Yan, Theofanous T. G, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research. e University of California, Santa Barbara. Center for Risk Studies and Safety., eds. The management of ATWS by boron injection. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Integrated plant safety assessment, systematic evaluation program, La Crosse Boiling Water Reactor, Dairyland Power Cooperative, docket no. 50-409. Washington, D.C: U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, 1986.
Encontre o texto completo da fonteKikō, Genshiryoku Anzen Kiban. CCDP to CLERP o kōryoshita EPRI shuhō ni yoru BWR no RI-ISI shihyōka ni kansuru hōkokusho: Report on trial assessment of RI-ISI program by EPRI method for BWR evaluating CCDP and CLERP. Tōkyō-to Minato-ku: Dokuritsu Gyōsei Hōjin Genshiryoku Anzen Kiban Kikō, 2013.
Encontre o texto completo da fonteH, Yan, Theofanous T. G, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research. e University of California, Santa Barbara. Center for Risk Studies and Safety., eds. The management of ATWS by boron injection. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.
Encontre o texto completo da fonteKikō, Genshiryoku Anzen Kiban. Kairyōgata futtōsuigata keisuiro no kanensei gasu nōdo seigyokei ni kakaru seinō hyōka kaiseki hōkokusho. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2011.
Encontre o texto completo da fonteThieme, M. Validation of the CHAN-component in TRACE using BWR full-size fine-mesh bundle tests. Washington, DC: U.S. Nuclear Regulatory Commission, 2010.
Encontre o texto completo da fonteJ, García García, López Montero J. V, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. e NUCLENOR S. A, eds. Assessment of single recirculation pump trip transient in Santa Maria de Garona Nuclear Power Plant with TRAC-BF1/MOD1, version 0.4. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Idaho National Engineering Laboratory e EG & G Idaho., eds. TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Idaho National Engineering Laboratory e EG & G Idaho., eds. TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Idaho National Engineering Laboratory e EG & G Idaho., eds. TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.
Encontre o texto completo da fonteGreene, Richard Henry. Aging and service wear of control rod drive mechanisms for BWR nuclear plants. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.
Encontre o texto completo da fonteGraves, C. C. Regulatory analysis for the resolution of generic issue C-8, "main steam isolation valve leakage and LCS failure". Washington, DC: Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Regulatory Applications. e Pacific Northwest National Laboratory (U.S.), eds. Estimating boiling water reactor decommissioning costs: A user's manual for the BWR Cost Estimating Computer Program (CECP) software : final report. Washington, DC: Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commssion, 1996.
Encontre o texto completo da fontePittiglio, C. L. Standard review plan for decommissioning cost estimates for nuclear power reactors: Final report. Washington, DC: U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Regulatory Improvement Programs, 2004.
Encontre o texto completo da fonteA, Fernández R., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. e Universidad de Cantabria, eds. Assessment of MSIV full closure for Santa Maria De Garoña nuclear power plant using TRAC-BF1 (G1J1). Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.
Encontre o texto completo da fonteHolman, Garry S. Application of reliability techniques to prioritize BWR recirculation loop welds for in-service inspection. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
Encontre o texto completo da fontePowers, 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.
Encontre o texto completo da fonteLehner, J. R. Estimated safety significance of generic safety issue 61. Washington, D.C: Division of Safety Review and Oversight, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1986.
Encontre o texto completo da fonteR, Lehner J., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research. e Brookhaven National Laboratory, eds. Identification and assessment of containment and release management strategies for a BWR Mark I containment. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1991.
Encontre o texto completo da fonteU.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Technology. e Oak Ridge National Laboratory, eds. LAPUR benchmark against in-phase and out-of-phase stability tests. Washington, DC: Division of Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1990.
Encontre o texto completo da fonteWeingardt, Jay J. TAC2D studies of Mark I containment drywell shell melt-through. Washington, DC: Division of Reactor Accident Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.
Encontre o texto completo da fonteJ, Vandenkieboom J., Lehner J. R, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research. e Brookhaven National Laboratory, eds. Identification and assessment of containment and release management strategies for a BWR Mark III containment. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.
Encontre o texto completo da fonteRidgely, J. N. Resolution of Generic Issue C-8: An evaluation of boiling water reactor main stream isolation valve leakage and the effectiveness of leakage treatment methods. Washington, DC: Division of Boiling Water Reactor Licensing, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1986.
Encontre o texto completo da fonteK, Kirk H., Yakle J, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Sandia National Laboratories e 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.
Encontre o texto completo da fonteJ, Vandenkieboom J., Lehner J. R, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research. e Brookhaven National Laboratory, eds. Identification and assessment of containment and release management strategies for a BWR Mark III containment. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.
Encontre o texto completo da fonteLehner, J. R. Estimated safety significance of generic safety issue 61. Washington, D.C: Division of Safety Review and Oversight, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1986.
Encontre o texto completo da fonteJ, Mumaw R., Westinghouse Electric Corporation e U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., eds. Cognitive skill training for nuclear power plant operational decision making. Washington, D.C: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1994.
Encontre o texto completo da fonteBierschbach, M. C. Estimating boiling water reactor decommissioning costs: A user's manual for the BWR cost estimating computer program (CECP) software : draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1994.
Encontre o texto completo da fonte