3213 リスクインフォームド ISI の日本における適用可能性と今後の方向性

概要

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Risk Informed-ISI utilizes PSA for streamlining the maintenance of nuclear power plants. In RI-ISI, maintenance requirements focus on high-safety-significant components and are relieved for low safety significant ones. This is expected to reduce plant cost as well as maintain safety. Quantitative and qualitative RI-ISI methods have been developed by ASME/Westinghouse Owners Group and EPRI, respectively. These methods have been incorporated in the ASME Sec. XI Code Cases and endorsed by the U.S. NRC. The quantitative method evaluates component segment risks in terms of pipe failure probability calculated with probabilistic failure mechanics (PFM) models and core damage frequency (CDF) calculated with PSA. The qualitative method uses pipe failure potential categorization derived from the plant service experiences and pipe failure impact on CDF derived from the PSA insight. The PFM models do not cover all the significant failure mechanisms, and the qualitative method is based on the U.S. service experiences. Therefore appropriate categorization rules must be developed on the Japanese service experiences. For this purpose, we have devised a framework of computer-aided system for the selection of risk significant elements.
一般社団法人日本機械学会の論文
2000-07-31