Analysis of BWR station blackout accident: Thermal-hydraulic behavior up to severe core damage in Fukushima Daiichi power plant unit 2

Transactions of the Atomic Energy Society of Japan

Volumn 10, Issue 4, 2011, Pages 240-244

  Watanabe, Tadashi ^a   Ishigaki, Masahiro ^a   Sato, Akira ^a   Nakamura, Hideo ^a  

^a Safety Research Center   (Japan)

Author keywords

BWR; Fukushima daiichi; RCIC; Station blackout; TRAC BF1

Indexed keywords

BWR; FUKUSHIMA DAIICHI; RCIC; STATION BLACKOUT; TRAC-BF1;

ACCIDENTS; POWER PLANTS;

BOILING WATER REACTORS;

EID: 84863012415     PISSN: 13472879     EISSN: None     Source Type: Journal    
DOI: 10.3327/taesj.J11.022     Document Type: Article

References (4)

1. M. M. Giles, G. A. Jayne, S. Z. Rouhani et al., TRAC-BF1/ MOD1: An Advanced Best-Estimate Computer Program for BWR Accident Analysis, NUREG/CR-4356 (1992).
2. J. Ishikawa, K. Muramatsu, T. Sakamoto, Systematic Source Tem Analysis for Level 3 PSA of a BWR with Mark-II Type Containment with THALES-2 Code, JAERI-Research 2005-021, Japan Atomic Energy Research Institute (JAERI) (2005), [in Japanese].
3. http://www.tepco.co.jp, Tokyo Electric Power Co. (TEPCO) (2011).
4. D. D. Yue, W. A. Condon, Severe-Accident-Sequence Assessment of Hypothetical Complete Station Blackout at the Browns Ferry Nuclear Plant, CONF-810905-9 (1981).