1 |
K. Oh, S.H. Han, J.H. Park, H.G. Lim, J.E. Yang, G. Heo, Study on quantification method based on Monte Carlo sampling for multiunit probabilistic safety assessment models, Nucl. Eng. Technol. 49 (2017) 710-720.
DOI
|
2 |
S. Samaddar, K. Hibino, O. Coman, Technical approach for safety assessment of MU NPP sites subject to external events, in: Proceedings of Probabilistic Safety Assessment and Management (PSAM 12), Honolulu, Hawaii, 2014.
|
3 |
K.N. Fleming, On the risk significance of seismically induced MU accidents, in: Proceedings of the ANS International Topical Meeting on Probabilistic Safety Assessment and Analysis, ID, USA, 2015.
|
4 |
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
|
5 |
IAEA, Nuclear Power Reactors in the World, Reference Data Series No. 2, International Atomic Energy Agency, 2017, 2017.
|
6 |
D.-S. Kim, S.H. Han, J.H. Park, H.-G. Lim, J.H. Kim, Multi-unit Level 1 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site, Nucl. Eng. Technol. 50 (2018) 1217-1233.
DOI
|
7 |
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.
DOI
|
8 |
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
|
9 |
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
|
10 |
S.H. Han, H.G. Lim, Top event probability evaluation of a fault tree having circular logics by using Monte Carlo method, Nucl. Eng. Des. 243 (2012) 336-340.
DOI
|
11 |
IAEA, The Fukushima Daiichi Accident: Report by the Director General, International Atomic Energy Agency, 2015.
|
12 |
Pickard Lowe, 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.
|
13 |
M. Modarres, T. Zhou, M. Massoud, Advances in MU nuclear power plant probabilistic risk assessment, Reliab. Eng. Syst. Saf. 157 (2017) 87-100.
DOI
|
14 |
U.S. Nuclear Regulatory Commission, Guidelines on Modeling Common-cause Failures in Probabilistic Safety Assessment (NUREG/CR-5485), Washington, D.C, 1998.
|
15 |
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.
|
16 |
W. Vesely, J. Dugan, J. Fragola, J. Minarick, J. Railsback, Fault Tree Handbook with Aerospace Applications, National Aeronautics and Space Administration, 2002.
|
17 |
E. Ruijters, M. Stoelinga, Fault tree analysis: a survey of the state-of-the-art in modeling, analysis and tools, Comp. Sci. Rev. 15-16 (2015) 29-62.
DOI
|
18 |
J. Kahn, N. Linial, A. Samorodnitsky, Inclusion-exclusion: exact and approximate, Combinatorica 16 (4) (1996) 465-477.
DOI
|
19 |
KHNP, LPSD Internal Events Level 1 PSA Report for Hanul Units 3&4, Korea Hydro & Nuclear Power, Co. Ltd., 2015.
|
20 |
W.S. Jung, J.E. Yang, J.J. Ha, A new method to evaluate alternate AC power source effects in multi unit nuclear power plants, Reliab. Eng. Syst. Saf. 82 (2003) 165-172.
DOI
|
21 |
S. Epstein, A. Rauzy, Can we trust PSA? Reliab. Eng. Syst. Saf. 88 (2005) 195-205.
DOI
|
22 |
S. Schroer, M. Modarres, An event classification schema for evaluating site risk in a multi-unit nuclear power plant probabilistic risk assessment, Reliab. Eng. Syst. Saf. 117 (2013) 45-51.
|
23 |
C.S. Kumar, V. Hassija, K. Velusamy, V. Balasubramaniyan, Integrated risk assessment for MU NPP sites - a comparison, Nucl. Eng. Des. 293 (2015) 53-62.
DOI
|
24 |
S. Zhang, J. Tong, J. Zhao, An integrated modeling approach for event sequence development in MU probabilistic risk assessment, Reliab. Eng. Syst. Saf. 155 (2016) 147-159.
DOI
|
25 |
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
|