Finite mixture models for sensitivity analysis of thermal hydraulic codes for passive safety systems analysis

被引:14
|
作者
Di Maio, Francesco [1 ]
Nicola, Giancarlo [1 ]
Zio, Enrico [1 ,2 ,3 ,4 ]
Yu, Yu [5 ]
机构
[1] Politecn Milan, Dept Energy, I-20156 Milan, Italy
[2] Ecole Cent Paris, Chair Syst Sci, Paris, France
[3] Ecole Cent Paris, Energet Challenge Fdn EDF, Paris, France
[4] Supelec, Paris, France
[5] North China Elect Power Univ, Sch Nucl Sci & Engn, Beijing 102206, Peoples R China
基金
中国国家自然科学基金;
关键词
CONTAINMENT COOLING SYSTEM; UNCERTAINTY; PARAMETERS; MARGINS; PERFORMANCE;
D O I
10.1016/j.nucengdes.2015.04.035
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
For safety analysis of Nuclear Power Plants (NPPs), Best Estimate (BE) Thermal Hydraulic (TH) codes are used to predict system response in normal and accidental conditions. The assessment of the uncertainties of TH codes is a critical issue for system failure probability quantification. In this paper, we consider passive safety systems of advanced NPPs and present a novel approach of Sensitivity Analysis (SA). The approach is based on Finite Mixture Models (FMMs) to approximate the probability density function (i.e., the uncertainty) of the output of the passive safety system TH code with a limited number of simulations. We propose a novel Sensitivity Analysis (SA) method for keeping the computational cost low: an Expectation Maximization (EM) algorithm is used to calculate the saliency of the TH code input variables for identifying those that most affect the system functional failure. The novel approach is compared with a standard variance decomposition method on a case study considering a Passive Containment Cooling System (PCCS) of an Advanced Pressurized reactor AP1000. (C) 2015 Elsevier BAT. All rights reserved.
引用
收藏
页码:144 / 154
页数:11
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