Study on construction of loss of component cooling water system initiating event fault tree for fire event PSA-Reference-Cited by-同舟云学术

Study on construction of loss of component cooling water system initiating event fault tree for fire event PSA

Published:2019-08-26 Issue:1 Volume:57 Page:79-89
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Kang Dae Il¹

Affiliation:

1. Risk Assessment Research Department, KAERI, Daejeon, South Korea

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2019.1659871

Reference8 articles.

1. Yang J, Kang D, Hahm D, et al. Development of site risk assessment and management technology including extreme external events. Korea Atomic Energy Research Institute; 2017. (KAERI/RR-4225/2016(in Korean)).

2. ASME/ANS. Addenda to ASME/ANS RA-S-2008, standard for level 1/large early release frequency probabilistic risk assessment for nuclear power plant applications. New York, U.S.: The American Society of Mechanical Engineers; 2009 Feb. (ASME/ANS RA-Sa-2009).

3. Julius J, Schroeder J Support system initiating events: identification and quantification guideline, Electric Power Research Institute (EPRI), Palo Alto, CA, and U.S. Washington, D.C: Nuclear Regulatory Commission; 2008. (2008 EPRI Report No. 1016741).

4. Najafi B, Nowlen SP, Joglar F, et al. EPRI/NRC-RES fire PRA methodology for nuclear power facilities: volume 2: detailed methodology. Palo Alto, CA, and U.S: Electric Power Research Institute (EPRI); 2005. (Nuclear Regulatory Commission, Office of Nuclear Regulatory Research (RES), Rockville, MD: 2005, EPRI TR-1011989 and NUREG/CR-6850).

5. Comparative study on the construction of support system initiating event fault trees for a fire probabilistic safety assessment

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