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Volumn 241, Issue 8, 2011, Pages 2942-2947

Evaluating the core damage frequency of a TRIGA research reactor using risk assessment tool software

Author keywords

[No Author keywords available]

Indexed keywords

CDS; CORE DAMAGE; CORE DAMAGE FREQUENCY; EVENT TREES; FAULT-TREES; NUCLEAR RESEARCH REACTOR; PROBABILISTIC SAFETY ASSESSMENT; RESIDUAL RISK; RISK ASSESSMENT TOOL; SAFETY RESEARCH; TEHRAN RESEARCH REACTORS; TRIGA RESEARCH REACTOR;

EID: 79961024359     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2011.06.023     Document Type: Article
Times cited : (9)

References (14)
  • 2
    • 0004269078 scopus 로고
    • U.S. Nuclear Regulatory Commission Washington, DC
    • Fault Tree Handbook, NUREG-0492 1981 U.S. Nuclear Regulatory Commission Washington, DC
    • (1981) Fault Tree Handbook, NUREG-0492
  • 5
    • 67649464623 scopus 로고    scopus 로고
    • International Atomic Energy Agency
    • IAEA Safety Glossary 2007 International Atomic Energy Agency
    • (2007) IAEA Safety Glossary
  • 8
    • 0033150010 scopus 로고    scopus 로고
    • Safety system consideration of a supercritical-water cooled fast reactor with simplified PSA
    • J.H. Lee, Y. Oka, and S. Koshizuka Safety system consideration of a supercritical-water cooled fast reactor with simplified PSA Reliability Engineering & Systems Safety 64 1999 327 338
    • (1999) Reliability Engineering & Systems Safety , vol.64 , pp. 327-338
    • Lee, J.H.1    Oka, Y.2    Koshizuka, S.3
  • 11
    • 41149132367 scopus 로고    scopus 로고
    • Risk analysis in engineering
    • Taylor & Francis USA
    • M. Modarres Risk analysis in engineering Engineering 2006 Taylor & Francis USA
    • (2006) Engineering
    • Modarres, M.1
  • 13
    • 73649143482 scopus 로고    scopus 로고
    • Coupling CFAST fire modeling and SAPHIRE probabilistic assessment software for internal fire safety evaluation of a typical TRIGA research reactor
    • S. Safaei Arshi, M. Nematollahi, and K. Sepanloo Coupling CFAST fire modeling and SAPHIRE probabilistic assessment software for internal fire safety evaluation of a typical TRIGA research reactor Reliability Engineering & Systems Safety 95 2010 166 172
    • (2010) Reliability Engineering & Systems Safety , vol.95 , pp. 166-172
    • Safaei Arshi, S.1    Nematollahi, M.2    Sepanloo, K.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.