Improvement of the Simplified Hybrid Method for Seismic Risk Assessment of Nuclear Fuel Facilities

Author:

MORI Kenji12

Affiliation:

1. Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority

2. Cooperative Major in Nuclear Energy, Graduate School of Integrative Science and Engineering, Tokyo City University

Publisher

Atomic Energy Society of Japan

Subject

Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference13 articles.

1. 7) Y. Tamauchi, T. Shoji, K. Takebe et al., “Application of probabilistic safety assessment to Rokkasho Reprocessing Plant, (I), The occurrence frequency of loss of hydrogen scavenging function in plutonium solution vessel,” Trans. At. Energy Soc. Jpn., 5[4], 334-346 (2006), [in Japanese].

2. 8) Japan Atomic Energy Agency, Nuclear Safety Research Center, Review of Technical Basis for Formulating Goals for Nuclear Fuel Facilities, JAEA–Review 2010-028, (Oct. 2010), [in Japanese].

3. 9) U. S. Nuclear Regulatory Commission, Draft Regulatory Basis for Licensing and Regulating Reprocessing Facilities, SECY–11–0163 (Nov. 2011).

4. 11) R. P. Kennedy, “Overview of Methods for Seismic PRA and Margin Analysis Including Recent Innovations,” Proc. OECD–NEA Workshop on Seismic Risk, Tokyo Japan, Aug. 10-12, 1999, p33-p63.

5. 12) R. P. Kennedy, “Performance-goal based (risk informed) approach for establishing the SSE site specific response spectrum for future nuclear power plants,” Nucl. Eng. Des., 241, 648-656 (2011).

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