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Volumn 186, Issue 1-2, 1998, Pages 279-301

Application of the W + (combining low line)COBRA/TRAC best-estimate methodology to the AP600 large-break LOCA analysis

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; APPROXIMATION THEORY; BOUNDARY CONDITIONS; COMPUTER SIMULATION; COMPUTER SOFTWARE; COOLING; HEAT TRANSFER; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; PRESSURIZED WATER REACTORS; REACTOR CORES; STATISTICAL METHODS;

EID: 0032206536     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/s0029-5493(98)00279-9     Document Type: Article
Times cited : (28)

References (16)
  • 5
    • 0347593359 scopus 로고    scopus 로고
    • WCOBRA/TRAC applicability to AP600 large-break loss-of-coolant accident
    • Westinghouse Electric Corporation, Pittsburgh, PA
    • Hochreiter, L.E., Kemper, R.M., Bajorek, S.M., Zhang, J., 1996. WCOBRA/TRAC applicability to AP600 large-break loss-of-coolant accident, Topic Report WCAP14171, rev. 1. Westinghouse Electric Corporation, Pittsburgh, PA.
    • (1996) Topic Report WCAP14171, Rev. 1
    • Hochreiter, L.E.1    Kemper, R.M.2    Bajorek, S.M.3    Zhang, J.4
  • 6
    • 0348223154 scopus 로고
    • AP600 design certification - Thermal hydraulics testing and analysis
    • Hochreiter, L.E., and Piplica, E.J., 1995. AP600 design certification - thermal hydraulics testing and analysis, Proc. NURETH-7 Conf., vol. 1, pp. 43-48.
    • (1995) Proc. NURETH-7 Conf. , vol.1 , pp. 43-48
    • Hochreiter, L.E.1    Piplica, E.J.2
  • 7
    • 0342716960 scopus 로고
    • Loss-of-coolant accident performance of the Westinghouse 600-MWe advanced pressurized water reactor
    • Kemper, R.M., Vertes, C.M., 1990. Loss-of-coolant accident performance of the Westinghouse 600-MWe advanced pressurized water reactor. Nucl. Technol. 91, 118-128.
    • (1990) Nucl. Technol. , vol.91 , pp. 118-128
    • Kemper, R.M.1    Vertes, C.M.2
  • 10
    • 0026768547 scopus 로고
    • Westinghouse advanced passive 600 plant
    • McIntyre, B.A., Beck, R.K., 1992. Westinghouse advanced passive 600 plant. Nucl. Safety 33 (1), 36-46.
    • (1992) Nucl. Safety , vol.33 , Issue.1 , pp. 36-46
    • McIntyre, B.A.1    Beck, R.K.2
  • 13
    • 0346962279 scopus 로고    scopus 로고
    • Westinghouse code qualification document for best-estimate loss-of-coolant analysis
    • WCAP-12945 (P). Letter to Westinghouse
    • U.S. Nuclear Regulatory Commission (USNRC), 1996. Acceptance for referencing of the topical report, WCAP-12945 (P). Westinghouse code qualification document for best-estimate loss-of-coolant analysis, Letter to Westinghouse.
    • (1996) Acceptance for Referencing of the Topical Report
  • 14
    • 0348223151 scopus 로고
    • Loss of coolant accident resulting from a spectrum of postulated piping breaks within the reactor coolant pressure boundary
    • Section 15.6.5, DE-AC03-90SF18495, rev.0-12
    • Westinghouse Electric Corporation, 1992-1997. Simplified Passive Advanced Light Water Reactor Plant Program: AP600 Standard Safety Analysis Report, Section 15.6.5, Loss of coolant accident resulting from a spectrum of postulated piping breaks within the reactor coolant pressure boundary. DE-AC03-90SF18495, rev.0-12.
    • (1992) Simplified Passive Advanced Light Water Reactor Plant Program: AP600 Standard Safety Analysis Report
  • 16
    • 0348223152 scopus 로고
    • Acceptance criteria for emergency core cooling systems for light water nuclear power reactors, and Appendix K
    • 10 CFR Part 50, Section 50.46
    • 10 CFR Part 50, Section 50.46, 1992. Acceptance criteria for emergency core cooling systems for light water nuclear power reactors, and Appendix K, ECCS evaluation models.
    • (1992) ECCS Evaluation Models


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.