Development of level-1 PSA method applicable to Japan Sodium-cooled Fast Reactor-Reference-Cited by-同舟云学术

Development of level-1 PSA method applicable to Japan Sodium-cooled Fast Reactor

Published:2014-04 Issue: Volume:269 Page:268-280
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kurisaka K.,Sakai T.,Yamano H.,Fujita S.,Minagawa K.,Yamaguchi A.,Takata T.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference11 articles.

1. A Standard for Procedures of Probabilistic Safety Assessment of Nuclear Power Plants during Power Operation (Level 1 PSA): 2008, AESJ-SC-P008:2008, March;Atomic Energy Society of Japan,2009

2. Handbook of Parameter Estimation for Probabilistic Risk Assessment, NUREG/CR-6823, USNRC, September;Atwood,2003

3. Reliability Study: Westinghouse Reactor Protection System, 1984-1995, NUREG/CR-5500, vol. 2;Eide,1999

4. Fragility evaluation of base-isolated building: Part2: Evaluation of fragility curve considering bumping against retaining wall;Endo,2007

5. Japan Electric Association Guide 4614-2000;Japan Electric Association,2000

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