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http://dx.doi.org/10.1016/j.net.2022.03.011

Application of Chernoff bound to passive system reliability evaluation for probabilistic safety assessment of nuclear power plants  

So, Eunseo (Department of Energy Systems Engineering, Chung-Ang University)
Kim, Man Cheol (Department of Energy Systems Engineering, Chung-Ang University)
Publication Information
Nuclear Engineering and Technology / v.54, no.8, 2022 , pp. 2915-2923 More about this Journal
Abstract
There is an increasing interest in passive safety systems to minimize the need for operator intervention or external power sources in nuclear power plants. Because a passive system has a weak driving force, there is greater uncertainty in the performance compared with an active system. In previous studies, several methods have been suggested to evaluate passive system reliability, and many of them estimated the failure probability using thermal-hydraulic analyses and the Monte Carlo method. However, if the functional failure of a passive system is rare, it is difficult to estimate the failure probability using conventional methods owing to their high computational time. In this paper, a procedure for the application of the Chernoff bound to the evaluation of passive system reliability is proposed. A feasibility study of the procedure was conducted on a passive decay heat removal system of a micro modular reactor in its conceptual design phase, and it was demonstrated that the passive system reliability can be evaluated without performing a large number of thermal-hydraulic analyses or Monte Carlo simulations when the system has a small failure probability. Accordingly, the advantages and constraints of applying the Chernoff bound for passive system reliability evaluation are discussed in this paper.
Keywords
Probabilistic safety assessment; Nuclear power plant; Chernoff bound; Passive system; Micro modular reactor;
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Times Cited By KSCI : 2  (Citation Analysis)
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1 Seok-Jung Han, Joon-Eon Yang, A quantitative evaluation of reliability of passive systems within probabilistic safety assessment framework for VHTR, Ann. Nucl. Energy 37 (3) (March 2010) 345-358.   DOI
2 E. So, M.C. Kim, Level 1 probabilistic safety assessment of supercritical-CO2-cooled micro modular reactor in conceptual design phase, Nucl. Eng. Technol. 53 (Issue 2) (February 2021) 498-508.   DOI
3 USNRC, Rates of Initiating Events at U.S. Nuclear Power Plants: 1987-1995," NUREG/CR-5750, United States Nuclear Regulatory Commission, Washington, D.C., 1998.
4 USNRC, Industry-averaged Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants, NUREG/CR-6928, United States Nuclear Regulatory Commission, Washington, D.C., 2007.
5 J.C. Helton, F.J. Davis, Latin hypercube sampling and the propagation of uncertainty in analyses of complex systems, Reliabil. Eng. Syst. Reliabil. 81 (Issue 1) (July 2003) 23-69.   DOI
6 H.S. Lim, GAMMA+1.0, in: Theory Manual," KAERI/TR-5728/2014 vol. 2, Korea Atomic Energy Research institute, Dajeon, Korea, 2014.
7 I. Andre, Khuri and siuli mukhopadhyay, "response surface methodology, Wiley Interdiscipl. Rev.: Comput. Stat. 2 (Issue 2) (2010) 128-149.   DOI
8 Luciano Burgazzi, Reliability evaluation of passive systems through functional reliability assessment, Nucl. Technol. 144 (Issue 2) (2003).
9 Horst Glaeser, GRS method for uncertainty and sensitivity evaluation of code results and applications, Sci. Technol. Nuclr. Install. 2008 (2008).
10 S.S. Wilks, Determination of sample sizes for setting tolerance limits, Ann. Math. Stat. 12 (No. 1) (1941) 91-96.   DOI
11 Ferson Scott, What Monte Carlo methods cannot do," human and ecological risk assessment, Int. J. 2 (Issue 4) (1996).
12 Jalil Jafaria, Francesco D'Auria, Hossein Kazeminejad, Hadi Davilu, Reliability evaluation of a natural circulation system, Nucl. Eng. Des. 224 (Issue 1) (September 2003) 79-104.   DOI
13 E. Zio, N. Pedroni, Estimation of the functional failure probability of a thermalhydraulic passive system by Subset Simulation, Nucl. Eng. Des. 239 (3) (2009) 580-599.   DOI
14 E. Zio, N. Pedroni, An optimized Line Sampling method for the estimation of the failure probability of nuclear passive systems, Reliab. Eng. Syst. Saf. 95 (Issue 12) (2010) 1300-1313.   DOI
15 H. Touchette, The large deviation approach to statistical mechanics, Phys. Rep. 478 (Issues 1-3) (2009) 1-69.   DOI
16 Gerald J. Hahn, Sample sizes for Monte Carlo simulation, IEEE Transact. Syst. Man Cybern. (Issue 5) (November 1972) 678-680. SMC-2.   DOI
17 M. Mitzenmacher, E. Upfal, Probability and Computing: Randomized and Probabilistic Techniques in Algorithms and Data Analysis, Cambridge University Press, July 2017.
18 Rajmund Drenyovszki, Lorant Kovacs, Istvan Pinter, Andras Olah, Kalman Tornai, On the convexity of Chernoff bound in the context of consumption admission in smart grids, in: International Conference on Smart Systems and Technologies (SST), Croatia, 2016. October 12-14.
19 Samprit Chatterjee, Ali S. Hadi, Regression Analysis by Example, John Wiley & Sons, 2012.
20 Arun Kumar Nayak, Chandrakar Amit, Gopika Vinod, A review: passive safety system reliability analysis - accomplishments and unresolved issues, Front. Energy Res. 2 (October 2014) 1-14. Article 40.
21 USNRC, Best-estimate Calculations of Emergency Core Cooling System Performance, Regulatory Guide 1.157, U.S. Nuclear Regulatory Commission, May 1989.
22 Seola Han and Taewan Kim, "Numerical experiments on order statistics method based on Wilks' formula for best-estimate plus uncertainty methodology," J. Environ. Manag., Volume 235, Issue 1, Pages 28-33.
23 Dong Gu Kang, Analysis of LBLOCA using best estimate plus uncertainties for three-loop nuclear power uprate, Ann. Nucl. Energy 90 (2016) 318-330.   DOI
24 Michel Marques, J.F. Pignatel, P. Saignes, F. D'Auria, L. Burgazzi, C. Muller, R. Bolado-Lavin, C. Kirchsteiger, V. La Lumia, I. Ivanov, Methodology for the reliability evaluation of a passive system and its integration into a probabilistic safety assessment, Nucl. Eng. Des. 235 (24) (December 2005) 2612-2631.   DOI
25 Christoper J. Fong, George E. Apostolakis, Dustin R. Langewisch, Pavel Hejzlar, Neil E. Todreas, Michael J. Driscoll, Reliability analysis of a passive cooling system using a response surface with an application to the flexible conversion ratio reactor, Nucl. Eng. Des. 239 (12) (2009) 2660-2671.   DOI
26 IAEA, Progress in Methodologies for the Assessment of Passive Safety System Reliability in Advanced in Advanced Reactors, International Atomic Energy Agency, Vienna, September 2014. IAEA-TECDOC-1752.
27 E. Zio, N. Pedroni, How to effectively compute the reliability of a thermalhydraulic nuclear passive system, Nucl. Eng. Des. 241 (Issue 1) (2011) 310-327.   DOI
28 A.K. Nayak, M.R. Gartia, A. Antony, G. Vinod, R.K. Sinha, Passive system reliability analysis using the APSRA methodology, Nucl. Eng. Des. 238 (6) (June 2008) 1430-1440.   DOI
29 Andrej Prosek, Borut Mavko, Review of best estimate plus uncertainty methods of thermal-hydraulic safety analysis, in: Proceedings of the International Conference Nuclear Energy for New Europe, Slovenia, 2003. September 8-11.
30 B.E. Boyack, Quantifying the reactor safety margins part 1: an overview of the code scaling, applicability, and uncertainty evaluation methodology, Nucl. Eng. Des. 119 (Issue 1) (1990) 1-15.   DOI
31 H. Pishro-Nik, Introduction to Probability, Statistics, and Random Process, Kappa Research LLC, 2014.
32 Rajmund Drenyovszki, Lorant Kovacs, Istvan Pinter, Andras Olah, Kalman Tornai, Janos Levendovszky, Power system reliability assessment based on Large Deviation Theory bounds, in: 2016 IEEE International Energy Conference (ENERGYCON), 2016. Belgium, April 4-8.
33 Enrico Zio, Pedroni Nicola, Literature Review of Methods for Representing Uncertainty, Foundation for an Industrial Safety Culture, March 2013.
34 Bong Seong Oh, Safety Analysis and Development of Control Logic of KAIST Micro Modular Reactor with GAMMA+ Code, MS Thesis, Korea Advanced Institute of Science and Technology, Department of Nuclear and Quantum Engineering, December 2016.
35 Bong Seong Oh, Yoon Han Ahn, Hwanyeal Yu, Jangsik Moon, Seong Gu Kim, Seong Kuk Cho, Yonghee Kim, Yong Hoon Jeong, Jeong Ik Lee, Safety evaluation of supercritical CO2 cooled micro modular reactor, Ann. Nucl. Energy 110 (2017) 1202-1216.   DOI
36 IAEA, Basic Safety Principles for Nuclear Power Plants 75-INSAG-3 Rev.1", INSAG-12, International Atomic Energy Agency, Vienna, October 1999.
37 Ho-Gon Lim, Sang-Hoon Han, Jae Jun Jeong, MOSAIQUE - a network based software for probabilistic uncertainty analysis of computerized simulation models, Nucl. Eng. Des. 241 (Issue 5) (May 2011) 1776-1784.   DOI
38 Seong Gu Kim, Hwanyeal Yu, Jangsik Moon, Seungjoon Baik, Yonghee Kim, Yong Hoon Jeong, Jeong Ik Lee, A concept design of supercritical CO2 cooled SMR operating at isolated microgrid region, Int. J. Energy Res. 41 (4) (2017) 512-525.   DOI
39 Sarah Kang, ChiWoong Choi, Kwi-Seok Ha, Jaeseok Heo, Sensitivity and uncertainty analysis for ULOF of PGSFR using PAPIRUS, Ann. Nucl. Energy 110 (2017) 1232-1241.   DOI
40 Chernoff Herman, A measure of asymptotic efficiency for tests of a hypothesis based on the sum of observations, Ann. Math. Stat. 23 (Issue 4) (1952), 493-207.   DOI
41 Hyeonmin Kim, Jaehyun Cho, Jae Young Yoon, Jinkyun Park, The Generation of Failure Surface for Reliability Assessment of Passive Safety Systems Using Deep Learning Technology, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, 2019. May 23-24.