Books on the topic 'Nuclear boiling'

J, Moody F., ed. The thermal-hydraulics of a boiling water nuclear reactor. 2nd ed. La Grange Park, Ill., USA: American Nuclear Society, 1993.

(Bonn, Germany) Kerntechnische Gesellschaft. SWR 1000: Ein zukunftsweisendes Reaktorkonzept : Tagungsbericht = SWR 1000 : a reactor concept for the future : proceedings. Bonn: INFORUM, 1998.

Hawthorne, 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.

Shih, Chunkuan, and 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.

Nikolaevich, Andreenko Sergeĭ, ed. Peregruzochnye mashiny kanalʹnykh i͡a︡dernykh ėnergeticheskikh reaktorov. Moskva: Ėnergoatomizdat, 1986.

Hawthorne, 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.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering. and 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.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering. and 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.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering. and 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.

U.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.

U.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.

L, Edson Jerald, Fineman C. F, Idaho National Engineering Laboratory, and 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.

U.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.

U.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.

Gauntt, 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.

S, Rohatgi Upendra, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., and 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.

U.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.

U.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.

Gauntt, 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.

U.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.

A, Gomez, Gallego I, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., and 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.

Kikō, 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.

H, Yan, Theofanous T. G, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and 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.

U.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.

Kikō, 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.

H, Yan, Theofanous T. G, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and 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.

Kikō, Genshiryoku Anzen Kiban. Kairyōgata futtōsuigata keisuiro no kanensei gasu nōdo seigyokei ni kakaru seinō hyōka kaiseki hōkokusho. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2011.

Thieme, M. Validation of the CHAN-component in TRACE using BWR full-size fine-mesh bundle tests. Washington, DC: U.S. Nuclear Regulatory Commission, 2010.

J, García García, López Montero J. V, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., and 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.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Idaho National Engineering Laboratory, and 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.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Idaho National Engineering Laboratory, and 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.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Idaho National Engineering Laboratory, and 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.

Greene, 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.

Graves, 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.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Regulatory Applications. and 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.

Pittiglio, 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.

A, Fernández R., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., and 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.

Holman, 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.

Powers, 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.

Lehner, 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.

R, Lehner J., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and 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.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Technology. and 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.

Weingardt, 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.

J, Vandenkieboom J., Lehner J. R, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and 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.

Ridgely, 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.

K, 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.

J, Vandenkieboom J., Lehner J. R, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and 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.

Lehner, 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.

J, Mumaw R., Westinghouse Electric Corporation, and 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.

Bierschbach, 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.