Development of Level 2 PSA Methodology for Sodium-Cooled Fast Reactors (1) Overview of Evaluation Technology Development
(0) A Probabilistic Safety Assessment (Level 2 PSA) is indispensable to the comprehensive safety assessment of Sodium-cooled Fast Reactors (SFRs). For this purpose, the analytical methodologies for all phases/sequences to be evaluated in the Level 2 PSA should be established, and the technical basis for constructing the phenomenological event trees should also be developed. With regard to the analytical methodologies for Level 2 PSA of SFRs, computational tools such as SAS4A, SIMMER-III, DEBNET, ARGO and APPLOHS have already been developed. However, these tools are not sufficient for systematically assessing the whole sequence of core disruptive accidents because the evaluation technologies for the material-relocation phase and the ex-vessel accident sequences have been lacking. Concerning the technical basis, the dominant factors in all phases/sequences should be identified through parametric analyses, and the information obtained from these analyses and related past experiments should be compiled so as to quantify the branch probabilities in the phenomenological event trees. In the present paper, the development of the evaluation technology for the Level 2 PSA of SFRs is described, focusing on the computational tools MUTRAN and SIMMER-LT for the material-relocation phase and CONTAIN/LMR for the ex-vessel accident sequence. In addition, the compilation of the technical basis to be utilized in the Level 2 PSA of SFRs is overviewed. The particular development of the technical basis and the details of event-tree constructions for ATWS (Anticipated Transient without Scram), LOHRS (Loss of Heat Removal System) and ex-vessel accident sequences are discussed in the relevant papers of this series.
Sodium-cooled Fast Reactors (SFRs) Core Disruptive Accident (CDA) Probabilistic SafetyAssessment (PSA) Material-relocation phase Ex-vessel accident sequence
Ryodai Nakai Tohru Suzuki Kenji Kamiyama Hiroshi Seino Kazuya Koyama Koji Morita
Japan Atomic Energy Agency 4002 Narita-cho, O-arai, Ibaraki, 311-1393, Japan Mitsubishi FBR Systems, Inc.2-34-17 Jingumae, Shibuya-ku, Tokyo, 150-0001, Japan Kyushu University 744 Motooka, Nishi-ku, Fukuoka, 819-0395, Japan
国际会议
上海
英文
526-537
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）