A Fuzzy Probability Algorithm for Evaluating the AP1000 Long Term Cooling System to Mitigate Large Break LOCA

被引:2
作者
Purba, J. H. [1 ]
机构
[1] Natl Nucl Energy Agcy, Ctr Nucl Reactor Technol & Safety, Puspiptek Area, Serpong 15310, Tangerang, Indonesia
关键词
Uncertainty analysis; Fuzzy probability algorithm; Fuzzy multiplication rule; Fuzzy complementation rule; AP1000 long term cooling system;
D O I
10.17146/aij.2015.417
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Components of nuclear power plants do not always have historical failure data to probabilistically evaluate their reliability characteristics. To overcome this drawback, an alternative approach has been proposed by involving experts to qualitatively justify basic event likelihood occurences. However, expert judgments always involve epistemic uncertainty and this uncertainty needs to be quantified. Existing fault tree analysis quantifies uncertainty using Monte Carlo simulation, which is based on probability distributions. Since expert judgments are not described in probability distributions, Monte Carlo simulation is not appropriate for evaluating epistemic uncertainty. Therefore, a new approach needs to be developed to overcome this limitation. This study proposes a fuzzy probability algorithm to evaluate epistemic uncertainties in fault tree analysis. In the proposed algorithm, fuzzy probabilities are used to represent epistemic uncertainties of basic events, intermediate events, and the top event. To propagate and quantify epistemic uncertainty in fault tree analysis, a fuzzy multiplication rule and a fuzzy complementation rule are applied to substitute the AND Boolean and OR Boolean gates, respectively. To see the feasibility and applicability of the proposed algorithm, a case-based experiment on uncertainty evaluation of the AP1000 long term cooling system to mitigate the large break loss of coolant accident is discussed. The result shows that the best estimate probability to describe the failure of AP1000 long term cooling system generated by the proposed algorithmis 3.15x10(-11), which is very closed to the reference value of 1.11x10(-11). This result confirms that the proposed algorithm offers a good alternative approach to quantify uncertainties in probabilistic safety assessment by fault tree analysis. (c) 2015 Atom Indonesia. All rights reserved
引用
收藏
页码:113 / 121
页数:9
相关论文
共 26 条
[1]   Assessment the safety performance of nuclear power plants using Global Safety Index (GSI) [J].
Abouelnaga, Ayah E. ;
Metwally, Abdelmohsen ;
Aly, Naguib ;
Nagy, Mohammad ;
Agamy, Saeed .
NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (10) :2820-2830
[2]   A risk concept applicable for both probabilistic and non-probabilistic perspectives [J].
Aven, Terje .
SAFETY SCIENCE, 2011, 49 (8-9) :1080-1086
[3]   Design of integrated passive safety system (IPSS) for ultimate passive safety of nuclear power plants [J].
Chang, Soon Heung ;
Kim, Sang Ho ;
Choi, Jae Young .
NUCLEAR ENGINEERING AND DESIGN, 2013, 260 :104-120
[4]   TU Delft expert judgment data base [J].
Cooke, Roger M. ;
Goossens, Louis L. H. J. .
RELIABILITY ENGINEERING & SYSTEM SAFETY, 2008, 93 (05) :657-674
[5]   On the performance of social network and likelihood-based expert weighting schemes [J].
Cooke, Roger M. ;
ElSaadany, Susie ;
Huang, Xinzheng .
RELIABILITY ENGINEERING & SYSTEM SAFETY, 2008, 93 (05) :745-756
[6]   Fault and Event Tree Analyses for Process Systems Risk Analysis: Uncertainty Handling Formulations [J].
Ferdous, Refaul ;
Khan, Faisal ;
Sadiq, Rehan ;
Amyotte, Paul ;
Veitch, Brian .
RISK ANALYSIS, 2011, 31 (01) :86-107
[7]   Fuzzy uncertainty modeling applied to AP1000 nuclear power plant LOCA [J].
Ferreira Guimaraes, Antonio Cesar ;
Franklin Lapa, Celso Marcelo ;
Lamego Simoes Filho, Francisco Fernando ;
Cabral, Denise Cunha .
ANNALS OF NUCLEAR ENERGY, 2011, 38 (08) :1775-1786
[8]   Combining Experts' Judgments: Comparison of Algorithmic Methods Using Synthetic Data [J].
Hammitt, James K. ;
Zhang, Yifan .
RISK ANALYSIS, 2013, 33 (01) :109-120
[9]   A fuzzy-based approach to comprehensive modeling and analysis of systems with epistemic uncertainties [J].
Hanss, M. ;
Turrin, S. .
STRUCTURAL SAFETY, 2010, 32 (06) :433-441
[10]  
Kamyab S, 2010, LECT NOTES ENG COMP, P1668