A preliminary site risk assessment

References

• International Atomic Energey Agency. The Fukushima Daiichi accident. Vienna: International Atomic Energy Agency; 2015.
   Google Scholar
• Coman O, Poghosyan S. IAEA project: multiunit probabilistic safety assessment. Probabilistic Safety Assessment and Management (PSAM 14); 2018.
   Google Scholar
• Modarres M, Zhou T, Massoud M. Advances in multi-unit nuclear power plant probabilistic risk assessment. Reliab Eng Syst Saf. 2017;157:87–100.
   Web of Science ®Google Scholar
• Hakata T. Seismic PSA method for multiple nuclear power plants in a site. Reliab Eng Syst Saf. 2007;92(7):883–894.
   Web of Science ®Google Scholar
• Kim D-S, Han SH, Park JH, et al. Multi-unit Level 1 probabilistic safety assessment: approaches and their application to a six-unit nuclear power plant site. Nucl Eng Technol. 2018;50(8):1217–1233.
   Web of Science ®Google Scholar
• Cho J, Han SH, Kim D-S, et al. Multi-unit Level 2 probabilistic safety assessment: approaches and their application to a six-unit nuclear power plant site. Nucl Eng Technol. 2018;50(8):1234–1245.
   Web of Science ®Google Scholar
• Kim S-Y, Jung YH, Han SH, et al. Multi-unit Level 3 probabilistic safety assessment: approaches and their application to a six-unit nuclear power plant site. Nucl Eng Technol. 2018;50(8):1246–1254.
   Web of Science ®Google Scholar
• Commission CNS. Summary report of the international workshop on multi-unit probabilistic safety assessment; 2015.
   Google Scholar
• Le Duy TD, Vasseur D, Serdet E. Probabilistic safety assessment of twin-unit nuclear sites: methodological elements. Reliab Eng Syst Saf. 2016;145:250–261.
   Web of Science ®Google Scholar
• Lim H-G, Kim D-S, Han SH, et al. Development of logical structure for multi-unit probabilistic safety assessment. Nucl Eng Technol. 2018;50(8):1210–1216.
   Web of Science ®Google Scholar
• Pikard Lowe and Garrick, Inc. Seabrook station probabilistic safety assessment – section 13.3 risk of two unit station. Prepared for Public Service Company of New Hampshire; PLG-0300; 1983.
   Google Scholar
• Prasad M, Vinod G, Gaikwad V, et al. Site core damage frequency for multi-unit nuclear power plants site. Prog Nucl Energy. 2017;96:56–61.
   Web of Science ®Google Scholar
• Yang J-E. Multi-unit risk assessment of nuclear power plants: current status and issues. Nucl Eng Technol. 2018;50(8):1199–1209.
   Web of Science ®Google Scholar
• Stutzke MA. Scoping estimates of multiunit accident risk. Probabilistic Safety Assessment and Management PSAM; 2014. p. 12.
   Google Scholar
• Yang J, Kang D, Kim K, et al. Development of site risk assessment and management technology including extreme external events. Korea Atomic Energy Research Institute; 2017. Korean.
   Google Scholar
• Lee S, Kim AR, Cho N, et al. A study for identifying multi-unit initiating event and estimating frequency. Probabilistic Safety Assessment and Management PSAM 14. Los Angeles (CA): PSAM; 2018.
   Google Scholar
• Ahn B, inventor; Hanyang University, assignee. Bayesian data bunsuk program [Bayesian data analysis program]. Republic of Korea patent C-2017-025345. 2017.
   Google Scholar
• Song W, Seo Y, Jae M. Initiating event frequency analysis using a Bayesian computer code. ASRAM 2017. Yokohama, Japan; 2017.
   Google Scholar
• Seo Y, Shin H, Jae M. Modeling of the Off-site power recovery in the multi-unit PSA. Transactions of the Korea Nuclear Society Autumn Meeting. Yeosu, Korea; 2018.
   Google Scholar
• Han SH, Lim H-G. Fault tree modeling of AAC power source in multi-unit nuclear power plants PSA. Transactions of the Korean Nuclear Society Autumn Meeting. Gyeongju, Korea; 2015.
   Google Scholar
• Jang S, Jae M. A development of methodology for assessing the inter-unit common cause failure in multi-unit PSA model. Reliability Engineering & System Safety; 2020. In Press, Journal Pre-proof.
   Google Scholar
• Song W, Park S, Seo Y, et al. A source term binning methodology for multi-unit consequence analyses. Reliab Eng Syst Saf. 2019;202:106989.
   Web of Science ®Google Scholar
• Bixler N, Walton F, Eubanks L, et al. MELCOR accident consequence code system (MACCS): user’s guide and reference manual. Washington (DC).
   Google Scholar
• Jae M, Jin Y, Jang S, et al. A study on MACCS input parameters for A level 3 PSA model for regulation verification. Korea: Hanyang University; 2018. Korean.
   Google Scholar
• Park S, Park H, Sohn S, et al. Construction of Preliminary ETE Model Using TSIS-CORSIM. Transactions of the Korean Nuclear Society Autumn Meeting. Yeosu, Korea; 2018.
   Google Scholar
• Park H, Kwon D, Song W, et al. Use of COMIDA2 for evaluating korean ingestion doses during severe accidents. Transactions of the Korean Nuclear Society Autumn Meeting. Yeosu, Korea; 2018.
   Google Scholar
• Seo Y, Lim D, Jae M An evaluation of long-term protective actions using the MACCS code. Transactions of the Korean Nuclear Society Spring Meeting. Jeju, Korea; 2018.
   Google Scholar
• Ahn B, inventor; Hanyang University, assignee. Bisangdaeeung risk jeongbo program (HEPRI) [Hanyang emergency pre-risk information program]. Republic of Korea patent C-2019-029390. 2019.
   Google Scholar
• Seo Y, Park H, Ahn BM, et al. A consideration of the single release location for the multi-unit accidents. Probabilistic Safety Assessment and Management, PSAM 14. Los Angeles (CA); 2018.
   Google Scholar
• Seo Y, Jang S, Lim D, et al. Consideration of risk metrics for site probabilistic safety assessment. Asian Symposium on Risk Assessment and Management; ASRAM 2019. Gyeongju, Korea; 2019.
   Google Scholar