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Volumn 52, Issue 3 SPEC. ISS., 1996, Pages 297-314

The development and application of the accident dynamic simulator for dynamic probabilistic risk assessment of nuclear power plants

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; NUCLEAR REACTOR ACCIDENTS; PERSONAL COMPUTERS; PROBABILITY; RELIABILITY THEORY; RISK ASSESSMENT;

EID: 0030173811     PISSN: 09518320     EISSN: None     Source Type: Journal    
DOI: 10.1016/0951-8320(95)00140-9     Document Type: Article
Times cited : (178)

References (13)
  • 1
    • 0028197894 scopus 로고
    • Risk assessment for dynamic systems: An overview
    • Siu, N., Risk assessment for dynamic systems: an overview. Reliab. Engng System Safety, 43 (1994) 43-73.
    • (1994) Reliab. Engng System Safety , vol.43 , pp. 43-73
    • Siu, N.1
  • 2
    • 0024134757 scopus 로고
    • Accident sequence dynamic simulation vs event trees
    • Amendola, A., Accident sequence dynamic simulation vs event trees. Reliab. Engng System Safety, 22 (1988).
    • (1988) Reliab. Engng System Safety , vol.22
    • Amendola, A.1
  • 3
    • 0041968770 scopus 로고
    • Dynamic event tree analysis method (DETAM) for accident sequence analysis
    • prepared for US Nuclear Regulatory Commission
    • Acosta, C. G. & Siu, N., Dynamic event tree analysis method (DETAM) for accident sequence analysis. NUREG/CR-5608, prepared for US Nuclear Regulatory Commission, 1992.
    • (1992) NUREG/CR-5608
    • Acosta, C.G.1    Siu, N.2
  • 4
    • 0041467593 scopus 로고
    • Dynamic accident sequence simulator for probabilistic safety assessment
    • 1993, Florida, 26-29 January
    • Hsueh, K. S. & Mosleh, A., Dynamic accident sequence simulator for probabilistic safety assessment. In 1993 PSA Int. Topical Meeting, Florida, 26-29 January 1993.
    • (1993) PSA Int. Topical Meeting
    • Hsueh, K.S.1    Mosleh, A.2
  • 5
    • 0026884986 scopus 로고
    • Probabilistic reactor dynamics-I: The theory of continuous event trees
    • Devooght, J. & Smidts, C., Probabilistic reactor dynamics-I: the theory of continuous event trees. Nucl. Sci. Engng, 111 (1992) 229-240.
    • (1992) Nucl. Sci. Engng , vol.111 , pp. 229-240
    • Devooght, J.1    Smidts, C.2
  • 6
    • 0041968769 scopus 로고
    • MSAS: Description and how-to-use commission of the European Communities
    • ISPRA, Italy
    • Smidts, C., MSAS: description and how-to-use commission of the European Communities. Technical reports ISEI/SER 2318/92, ISPRA, Italy, 1992.
    • (1992) Technical Reports ISEI/SER 2318/92
    • Smidts, C.1
  • 7
    • 0010735276 scopus 로고
    • US Nuclear Regulator Commission, NUREG/CR-4312, EGG-2396
    • Ransom, V. H. et al., RELAP/MOD2 Code Manual, US Nuclear Regulator Commission, NUREG/CR-4312, EGG-2396, 1985.
    • (1985) RELAP/MOD2 Code Manual
    • Ransom, V.H.1
  • 8
    • 0041467580 scopus 로고
    • RETRANS-02: A program for transient thermal-hydraulic analysis of complex fluid flow systems
    • Paulsen, M. P., et al., RETRANS-02: a program for transient thermal-hydraulic analysis of complex fluid flow systems. ERPI NP-1850-CCM, 1984.
    • (1984) ERPI NP-1850-CCM
    • Paulsen, M.P.1
  • 9
    • 85029974726 scopus 로고
    • Categorization of operator errors in the context of symptom-based emergency operating procedures
    • Tokyo, August
    • Hsueh, K. S. & Mosleh, A., Categorization of operator errors in the context of symptom-based emergency operating procedures. In SMiRT, Tokyo, August, 1991.
    • (1991) SMiRT
    • Hsueh, K.S.1    Mosleh, A.2
  • 10
    • 0041467579 scopus 로고
    • Hydrodynamic models for the treatment of reactor thermal transients
    • Meyer, J.E. Hydrodynamic models for the treatment of reactor thermal transients. Nucl. Sci. Engng, 19 (1961).
    • (1961) Nucl. Sci. Engng , vol.19
    • Meyer, J.E.1
  • 11
    • 0004109341 scopus 로고
    • Hemisphere Publishing Corporation, New York
    • Todreas, N. & Kazimi, M., Nuclear System, Hemisphere Publishing Corporation, New York, 1990.
    • (1990) Nuclear System
    • Todreas, N.1    Kazimi, M.2
  • 12
    • 33748145541 scopus 로고
    • Seabrook simulator model upgrade: Implementation and validation of two-phase, nonequilibrium RCS and steam generator models
    • EPRI GS/NP-6670
    • Kao, K., Seabrook simulator model upgrade: implementation and validation of two-phase, nonequilibrium RCS and steam generator models. In Proc. Conf. Power Plant Simulators and Modelling, EPRI GS/NP-6670, 1988.
    • (1988) Proc. Conf. Power Plant Simulators and Modelling
    • Kao, K.1
  • 13
    • 0042970464 scopus 로고
    • PLG-0300, prepared for Public Service Company of New Hampshire and Yankee Atomic Electric Company by Pickard Lowe and Garrick, Inc., California
    • Seabrook station probabilistic safety assessment. PLG-0300, prepared for Public Service Company of New Hampshire and Yankee Atomic Electric Company by Pickard Lowe and Garrick, Inc., California, 1983.
    • (1983) Seabrook Station Probabilistic Safety Assessment


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.