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Maruyama, Yu; Kita, Toshinobu*; Kuramoto, Takahiro*
Nihon Genshiryoku Gakkai-Shi ATOMO
, 62(6), p.328 - 333, 2020/06
no abstracts in English
Watanabe, Norio; Muramatsu, Ken; Ogura, Katsunori*; Mori, Junichi*
Proceedings of 5th International Conference on Probabilistic Safety Assessment and Management (PSAM-5), p.1809 - 1816, 2000/00
no abstracts in English
Sobajima, Makoto
Nihon Genshiryoku Gakkai-Shi, 40(5), p.372 - 374, 1998/00
no abstracts in English
Narumiya, Yoshiyuki*; Miyano, Hiroshi*; Noguchi, Kazuhiko*; Muramatsu, Ken*; Takata, Takashi; Muta, Hitoshi*; Itoi, Tatsuya*; Matsumoto, Masaaki*; Matsunaga, Yoko*
no journal, ,
Target of PRA is not calculating PRA to get CDF/CFF, but providing significant and useful information from PRA results for risk-informed activities. Lot of risk applications have been implemented these about 20 years in US. After Fukushima Dai-ichi accidents, Japanese Nuclear Regulation Authority provided new regulatory requirements about external events and beyond design events. And Risk Application faces full-scale implementation. In this report, several methods of risk application are showed with adequate risk indexes. Two examples of risk application, risk-informed shutdown management and RI-ISI, are provided. The explanation about Risk Informed Decision-Making Process is made.
Takata, Takashi
no journal, ,
Standard committee of Atomic Energy Society of Japan (AESJ) have issued various publications and standards, such as a principle of nuclear safety and codes for each requirement, which consists of a hierarchical structure. An absolute and effective application of the new inspection system is quite important to enhance level of the nuclear safety in Japan and risk-informed application plays an important role for that. In the publication of standards related to Probability Risk Assessment (PRA), the Standard committee have focused on the quality of level and kind of application that is necessary for risk-informed application. In this paper, a satisfaction level of PRA standards' requirements, which will be required in the new inspection system, has been discussed.
Yamano, Hidemasa
no journal, ,
In the United States, the development of small module reactors (SMR) and new non-light water reactors has become active thanks to aggressive private investment. In November 2020, the U.S. Nuclear Regulatory Commission (NRC) started public comments on a draft new rule of a technology inclusive, risk-informed and performance-based framework toward advanced reactor licensing. This lecture will report on the status of safety regulation efforts for new reactors, mainly in the United States.
Zheng, X.; Tamaki, Hitoshi; Maruyama, Yu; Takada, Tsuyoshi; Narukawa, Takafumi*; Takata, Takashi*
no journal, ,
The dynamic probabilistic risk assessment (dynamic PRA) methodology explicitly treats the dynamics of event progression, enabling risk assessment that does not require predefined scenarios or success criteria. Based on these characteristics, from the perspective of risk triplet, we investigated the concept and measures of risk importance in dynamic PRA. Furthermore, the importance measures were applied to a dynamic PRA to evaluate their effectiveness. In this presentation, the authors provide a review on the application status of traditional risk importance measures in nuclear regulatory activities, and by using quantities such as release amount (consequence) of time-dependent source term to the environment and associated containment failure frequency (CFF), they confirm the applicability of the proposed risk importance measure to dynamic Level 2 PRA.