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Oral presentation

Analysis of seismically induced core damage at two BWRs in the same site

Muramatsu, Ken; Liu, Q.; Uchiyama, Tomoaki*

no journal, , 

Aming at proposing effective applications of seismic PSAs for design and risk management of nuclear facilities, a scoping study was conducted for seismic PSA of a multi-unit site to examine core damage frequency (CDF) and potential combinations of core damage sequences and the effectiveness of an accident management measure, namely, the cross connection of emergency diesel generators (EDGs) between adjacent units. Twin hypothetical units (BWR-5 with Mark-II Containment) located in the same site were taken as an example. The system model of these two units was constructed based on the Model plant (JAERI-Research 99-035). The CDF as well as the accident sequences was calculated by using SECOM2, a system reliability analysis code for seismic PSA study. In addition, since the frequency of an accident sequence was affected by the correlation of component failure, sensitivity analysis of the effect of correlation failure was performed. As a result on the accident sequences that cause core damage at this two-unit site, the contribution fraction of the cases of core damage at only one unit was higher than the fraction of cases of simultaneous core damage of both units. Further, it was suggested from the sensitivity analysis of cross-connection of EDGs between these two units that the cross connection would be an effective measure to reduce CDF of this two-unit site since the emergency power for the damaged unit could be supplied from the intact one.

Oral presentation

Calculations using a Level 3PSA code in support of deriving performance goals

Homma, Toshimitsu; Matsubara, Takeshi

no journal, , 

no abstracts in English

Oral presentation

Uncertainty analyses of source terms for BWR-5/Mark-II with THALES2 code

Ishikawa, Jun; Muramatsu, Ken; Watanabe, Norio

no journal, , 

no abstracts in English

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