Abstract
To assure the structural integrity of a reactor pressure vessel (RPV) is one of the most critical issues to maintain the safe long-term operation of a nuclear power plant. In Japan, the assessment methods for RPV integrity using deterministic fracture mechanics, provided in the codes and standards, have been endorsed by the regulatory body. Meanwhile, a regulation on the fracture toughness requirements against PTS events with a probabilistic approach has been established in the U.S. In this paper, we describe preliminary research results obtained from the second-year activity of five-year project. Refering to the approach in the U.S., the through-wall cracking frequency (TWCF) for aging RPV in Japan against PTS events was calculated using a probabilistic fracture mechanics analysis code PASCAL3.
Published Version
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