Safety system consideration of a supercritical-water cooled fast reactor with simplified PSA

Reliability Engineering and System Safety

Volumn 64, Issue 3, 1999, Pages 327-338

  Lee, J H ^a   Oka, Y ^a   Koshizuka, S ^a  

^a UNIVERSITY OF TOKYO   (Japan)

Author keywords

Core damage frequency; Probabilistic safety assessment; Safety system; Supercritical water cooled reactor

Indexed keywords

COOLING WATER; CORE DISRUPTIVE ACCIDENTS; NUCLEAR REACTOR ACCIDENTS; PROBABILITY; RISK ASSESSMENT; SAFETY FACTOR;

PROBABILISTIC ESTIMATION; REACTOR SAFETY SYSTEMS; SUPERCRITICAL-WATER COOLED FAST REACTORS;

FAST REACTORS;

EID: 0033150010     PISSN: 09518320     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0951-8320(98)00080-5     Document Type: Article

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