Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

AIMS-MUPSA software package for multi-unit PSA

  • Han, Sang Hoon (Risk & Environment Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Oh, Kyemin (KHNP Central Research Institute) ;
  • Lim, Ho-Gon (Risk & Environment Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Yang, Joon-Eon (Risk & Environment Safety Research Division, Korea Atomic Energy Research Institute)
  • Received : 2017.09.21
  • Accepted : 2018.06.11
  • Published : 2018.12.25
Download PDF
⟨ Previous Next ⟩

Abstract

The need for a PSA (Probabilistic Safety Assessment) for a multi-unit at a site is growing after the Fukushima accident. Many countries have been studying issues regarding a multi-unit PSA. One of these issues is the problem of many combinations of accident sequences in a multi-unit PSA. This paper deals with the methodology and software to quantify a PSA scenarios for a multi-unit site. Two approaches are developed to quantify a multi-unit PSA. One is to use a minimal cut set approach, and the other is to use a Monte Carlo approach.

Keywords

References

  1. Pickard, Lowe, Garrick, Inc, Seabrook Station Probabilistic Safety Assessment, 1983. Main Report, PLG-0300.
  2. Ho-Gon Lim, Sang Hoon Han, Joon Eon Yang, Research status of multi-unit PSA methodology in Korea, in: 13th International Conference on Probabilistic Safety Assessment and Management (PSAM 13), Held on Seoul, Korea, Oct. 2-7, 2016.
  3. CNSC, Summary Report of the International Workshop on Multi-unit Probabilistic Safety Assessment, 2014. Held on Ottawa, Canada, Nov. 17-20.
  4. Sang Hoon Han, Ho-Gon Lim, Seung-Cheol Jang, Joon-Eon Yang, AIMS-psa: a software for integrated PSA, in: 13th International Conference on Probabilistic Safety Assessment and Management (PSAM 13), Held on Seoul, Korea, Oct. 2-7, 2016.
  5. Woo Sik Jung, et al., A fast BDD algorithm for large coherent fault trees analysis, Reliab. Eng. Syst. Saf. 83 (2004) 369-374. https://doi.org/10.1016/j.ress.2003.10.009
  6. Sang Hoon Han, Ho-Gon Lim, Top event probability evaluation of a fault tree having circular logics by using Monte Carlo method, Nucl. Eng. Des. 243 (2012) 336-340. https://doi.org/10.1016/j.nucengdes.2011.11.029
  7. Kyemin Oh, Sang Hoon Han, Jin Hee Park, Ho-Gon Lim, Joon-Eon Yang, Gyunyoung Heo, Study on quantification method based on Monte Carlo sampling for multiunit probabilistic safety assessment models, Nuclear Eng. Technol. 49 (4) (2017) 710-720. https://doi.org/10.1016/j.net.2016.12.009
  8. USNRC, Severe Accident Risks: an Assessment for Five U.S, vols. 1 & 2, Nuclear Power Plants, Washington, DC, December, 1990. NUREG-1150.
  9. USNRC, NUREG/CR-4551, Evaluation of Severe Accident Risks: Methodology for Containment, Source Term, Consequence, and Risk Integration Analyses, vol. 1, 1993. Rev.1.
  10. K.I. Ahn, Y.H. Jin, C.K. Park, et al., Development of a computer code, CONPAS, for an integrated level 2 PSA, J. Kor. Nuclear Soc. 30 (1) (1998) 58-74.
  11. Sai Zhang, Jiejuan Tong, Jun Zhao, An integrated modeling approach for event sequence development in multi-unit probabilistic risk assessment, Reliab. Eng. Syst. Saf. 155 (2016) 147-159. https://doi.org/10.1016/j.ress.2016.07.008
  12. Antoine Rauzy, New algorithms for fault trees analysis, Reliab. Eng. Syst. Saf. 40 (1993) 203-211. https://doi.org/10.1016/0951-8320(93)90060-C
  13. FTREX 1.9 Beta User Manual, EPRI and KAERI, 2016, 3002008108.
  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. https://doi.org/10.1016/j.net.2018.10.012
  15. 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. https://doi.org/10.1016/j.net.2018.01.006
  16. 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. https://doi.org/10.1016/j.net.2018.04.005
  17. 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. https://doi.org/10.1016/j.net.2018.09.019
  18. Sang Hoon Han, Jin Hee Park, Dong San Kim, Ho-Gon Lim, Seung Cheol Jang, Comparison of various methods to quantify a fault tree for Seismic PSA, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 7-8, 2015.
  19. CAFTA Fault Tree Analysis System Version 5.4, Software Manual, EPRI, 2009.
  20. SAREX User's Manual Version 1.2, KEPCO-E&C, 2011.
  21. J.U.N.G. Woo Sik, H.A.N. Sang Hoon, H.A. Jaejoo, An overview of the fault tree solver FTREX, in: 13th International Conference on Nuclear Engineering, Beijing, China, May 16-20, 2005.
  22. Y.A.N.G. Joon-Eon, et al., Analytic method to break logical loops automatically in PSA, Reliab. Eng. Safety 56 (1997) 101-105. https://doi.org/10.1016/S0951-8320(96)00142-1
  23. H. Kumamoto, Dagger-sampling Monte Carlo for system unavailability evaluation, IEEE Trans. Reliab. R 29 (2) (1980) 122-125.

Cited by

  1. Multi-unit Level 1 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site vol.50, pp.8, 2018, https://doi.org/10.1016/j.net.2018.01.006
  2. Multi-unit Level 2 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site vol.50, pp.8, 2018, https://doi.org/10.1016/j.net.2018.04.005
  3. Multi-unit risk assessment of nuclear power plants: Current status and issues vol.50, pp.8, 2018, https://doi.org/10.1016/j.net.2018.09.010
  4. Development of logical structure for multi-unit probabilistic safety assessment vol.50, pp.8, 2018, https://doi.org/10.1016/j.net.2018.10.012
  5. A Method to Avoid Underestimated Risks in Seismic SUPSA and MUPSA for Nuclear Power Plants Caused by Partitioning Events vol.14, pp.8, 2021, https://doi.org/10.3390/en14082150
  6. Probability subtraction method for accurate quantification of seismic multi-unit probabilistic safety assessment vol.53, pp.4, 2021, https://doi.org/10.1016/j.net.2020.09.022
  7. Application of Dynamic Fault Tree Analysis to Prioritize Electric Power Systems in Nuclear Power Plants vol.14, pp.14, 2018, https://doi.org/10.3390/en14144119
  8. Development of Dependence Indexes for Multi-Unit Risk Assessment and its Estimation Using Copula vol.213, pp.None, 2021, https://doi.org/10.1016/j.ress.2021.107652
  9. Multi-unit nuclear power plant probabilistic risk assessment: A comprehensive survey vol.213, pp.None, 2021, https://doi.org/10.1016/j.ress.2021.107782