Multi-unit Level 1 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site |
Kim, Dong-San
(Korea Atomic Energy Research Institute)
Han, Sang Hoon (Korea Atomic Energy Research Institute) Park, Jin Hee (Korea Atomic Energy Research Institute) Lim, Ho-Gon (Korea Atomic Energy Research Institute) Kim, Jung Han (Pusan National University) |
1 | U.S. Nuclear Regulatory Commission, Common-Cause Failure Database and Analysis Systems: Event Data Collection, Classification, and Coding (NUREG/CR-6268), Rev. 1, Washington, D.C, 2007. |
2 | K.N. Fleming, On the issues of integrated riskda PRA practitioners perspective, in: Proceedings of the ANS International Topical Meeting on Probabilistic Safety Analysis, San Francisco, CA, USA, 2005. |
3 | K.N. Fleming, On the risk significance of seismically induced multi-unit accidents, in: Proceedings of the ANS International Topical Meeting on Probabilistic Safety Assessment and Analysis, ID, USA, 2015. |
4 | M.A. Stutzke, Scoping estimates of multi-unit accident risk, in: Proceedings of Probabilistic Safety Assessment and Management (PSAM 12), Honolulu, Hawaii, 2014. |
5 | Pickard Lowe and Garrick, Inc, in: Seabrook Station Probabilistic Safety Assessment - Section 13.3 Risk of Two Unit Station, Prepared for Public Service Company of New Hampshire, PLG-0300, 1983. |
6 | S. Samaddar, K. Hibino, O. Coman, Technical approach for safety assessment of multi-unit NPP sites subject to external events, in: Proceedings of Probabilistic Safety Assessment and Management (PSAM 12), Honolulu, Hawaii, 2014. |
7 | K. Ebisawa, T. Teragaki, S. Nomura, H. Abe, M. Shigemori, M. Shimomoto, Concept and methodology for evaluating core damage frequency considering failure correlation at multi units and sites and its application, Nucl. Eng. Des. 288 (2015) 82-97. DOI |
8 | C.S. Kumar, V. Hassija, K. Velusamy, V. Balasubramaniyan, Integrated risk assessment for multi-unit NPP sites - a comparison, Nucl. Eng. Des. 293 (2015) 53-62. DOI |
9 | T.D. Le Duy, D. Vasseur, E. Serdet, Probabilistic safety assessment of twin-unit nuclear sites: methodological elements, Reliab. Eng. Syst. Saf. 145 (2016) 250-261. DOI |
10 | S. Zhang, J. Tong, J. Zhao, An integrated modeling approach for event sequence development in multi-unit probabilistic risk assessment, Reliab. Eng. Syst. Saf. 155 (2016) 147-159. DOI |
11 | S.H. Han, K. Oh, H.-G. Lim, J.-E. Yang, AIMS-MUPSA software package for multi-unit PSA, Nucl. Eng. Technol. 50 (2018) 1255-1265. DOI |
12 | M. Modarres, T. Zhou, M. Massoud, Advances in multi-unit nuclear power plant probabilistic risk assessment, Reliab. Eng. Syst. Saf. 157 (2017) 87-100. DOI |
13 | IAEA. Nuclear Power Reactors in the World, Reference Data Series No. 2, 2017 Edition, International Atomic Energy Agency, 2017. |
14 | H.-G. Lim, D.-S. Kim, S.H. Han, J.-E. Yang, Development of logical structure for multi-unit probabilistic safety assessment, Nucl. Eng. Technol. 50 (2018) 1210-1216. DOI |
15 | J. Cho, S.H. Han, D.-S. Kim, H.-G. Lim, Multi-unit Level 2 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site, Nucl. Eng. Technol. 50 (2018) 1234-1245. |
16 | S.-Y. Kim, Y.H. Jung, S.H. Han, S.-J. Han, H.-G. Lim, Multi-unit Level 3 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site, Nucl. Eng. Technol. 50 (2018) 1246-1254. DOI |
17 | D.S. Kim, J.H. Park, H.G. Lim, Multi-unit initiating event analysis for a singleunit internal events Level 1 PSA, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, 2016. |
18 | S.H. Han, H.G. Lim, S.C. Jang, J.E. Yang, AIMS-PSA: a software for integrated PSA, in: Proceedings of the 13th International Conference on Probabilistic Safety Assessment and Management (PSAM 13), Seoul, Korea, 2016. |
19 | W.S. Jung, S.H. Han, J. Ha, A fast BDD algorithm for large coherent fault trees analysis, Reliab. Eng. Syst. Saf. 83 (2004) 369-374. DOI |
20 | 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, in: ASME/ANS RA-sb-2013, the American Society of Mechanical Engineers & American Nuclear Society, New York, U.S, 2013. |
21 | S.H. Han, H.G. Lim, Fault tree modeling of AAC power source in multi-unit nuclear power plant PSA, in: Transactions of the Korean Nuclear Society Fall Meeting, Gyeongju, Korea, 2015. |
22 | U.S. Nuclear Regulatory Commission, CCF Parameter Estimations (2007 Update), http://nrcoe.inl.gov/results/CCF/ParamEst2007/ccfparamest.htm, September 2008. |
23 | U.S. Nuclear Regulatory Commission, Guidelines on Modeling Common-Cause Failures in Probabilistic Safety Assessment (NUREG/CR-5485), Washington, D.C, 1998. |
24 | U.S. Nuclear Regulatory Commission, Reevaluation of Station Blackout Risk at Nuclear Power Plants - Analysis of Loss of Offsite Power Events: 1986-2004 (NUREG/CR-6890), 1, 2005. Washington, D.C. |
25 | U.S. Nuclear Regulatory Commission, CCF Parameter Estimations (2012 Update), http://nrcoe.inl.gov/results/CCF/ParamEst2012/ccfparamest.htm, November 2013. |
26 | KAERI, Development of Site Risk Assessment and Management Technology Including Extreme External Events, KAERI/RR-4225/2016, Korea Atomic Energy Research Institute, 2017. |
27 | IAEA, Attributes of Full Scope Level 1 Probabilistic Safety Assessment (PSA) for Applications in Nuclear Power Plants, IAEA-TECDOC-1804, International Atomic Energy Agency, Vienna, 2016. |
28 | EPRI, Seismic Probabilistic Risk Assessment Implementation Guide, Electric Power Research Institute, Palo Alto, CA, 2013, 3002000709. |
29 | J.H. Kim, I.K. Choi, Evaluation of failure probability considering seismic correlation for probabilistic safety assessment, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, 2012. |