Libros sobre el tema "BWR1"

Jones, Bethan Wyn. Bwrw blwyddyn. Caernarfon: Gwasg Gwynedd, 1997.

Etherton, Roy. Bwrw lliwiau. Aberystwyth: Gwasg Cambria, 1991.

1935-, Owen William y Ysgol Carreg-lefn, eds. Bwrw cyfrif 'rôl canrif. Carreg-lefn: Corff Llywodraethol Ysgol Gymuned Carreg-lefn, 1999.

Kikō, Genshiryoku Anzen Kiban. Teishiji reberu 2PSA no kentō (BWR). [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2005.

Theofanous, 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.

Kikō, Genshiryoku Anzen Kiban. Reberu 2 PSA shuhō no seibi (BWR). [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2005.

Kikō, Genshiryoku Anzen Kiban, ed. Jishinji reberu 2 PSA no kaiseki (BWR). [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2008.

Kikō, Genshiryoku Anzen Kiban, ed. Jishinji reberu 2 PSA no kaiseki (BWR). [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2008.

U.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.

U.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.

Christensen, P. la Cour. A BWR power plant simulator for Barseback. Roskilde, Denmark: Riso National Laboratory, 1985.

U.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.

U.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.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs., ed. Standard technical specifications: General Electric Plants, BWR/4. 2^a 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. 2^a ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.

R, Greene Sherrell, U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution. y 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.

Duce, 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.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Standard technical specifications: General Electric plants, BWR/6. Washington, DC: The Office, 1992.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs, ed. Standard technical specifications: General Electric Plants, BWR/6. 2^a 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. 2^a ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.

R, Greene Sherrell, U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution. y 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.

O, Harris D., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Safety., Failure Analysis Associates y 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.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Regulatory Improvement Programs, ed. Standard technical specifications: General Electric Plants, BWR/4. 2^a 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. 2^a ed. Washington, DC: Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2001.

D, Buckley G., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering. y 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.

R, Greene Sherrell, U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution. y 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.

Saito, Kiyohide. Tomb F, tomb of BWLH and BWRP: Southeast necropolis Palmyra, Syria. Nara, Japan: Research Center for Silk Roadology, 2001.

Wolfgang, Wulff, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research. y 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.

E, Claiborne, Science and Engineering Associates y 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.

Mirkovic, 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.

B, Scott W., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Pacific Northwest Laboratory y 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.

K, Kirk H., Yakle J, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Sandia National Laboratories y 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.

Wagner, 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.

Wagner, 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.

Kikō, Genshiryoku Anzen Kiban, ed. Akushidento manejimentso chishiki bēsu seibi ni kansuru hōkokusho: Dētabēsu (BWR). [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2007.

King, 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.

Kikō, Genshiryoku Anzen Kiban. Kakunō yōki kenzensei ni kansuru kiki no jūyōdo hyōka (BWR). [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2005.

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.

L, Humphries L., Sandia National Laboratories, Science Applications International Corporation y 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.

Laboratory, Brookhaven National y 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.

A, Hodge S., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research. y 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.

Howes, John. Ironstone: An international exhibition of contemporary cast iron sculpture = arddangosfa ryngwladol o gerfluniau haearn bwrw. Swansea: Sculpture Cymru, 2010.

Dean, 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.

Regulation, 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.

U.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.

S, Lee B., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology. y 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.

Kikō, Genshiryoku Anzen Kiban. Kokunai BWR puranto no mizu kagaku no dōkō ni kansuru chōsa hōkokusho. [Tōkyō-to Minato-ku]: Genshiryoku Anzen Kiban Kikō, 2012.

United Engineers & Constructors, inc., Oak Ridge National Laboratory y 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.

Kikō, Genshiryoku Anzen Kiban. Jishinji no reberu 3-PSA no kentō (PWR oyobi BWR): Heisei 20-nendo. [Tokyo]: Genshiryoku Anzen Kiban Kikō, 2009.

R, Greene Sherrell, U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution. y 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.