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Journal Articles Nuclear Engineering and Design Year : 2015

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

Abstract

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.

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Electric power
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Dates and versions

hal-01265884 , version 2 (16-07-2015)
hal-01265884 , version 1 (01-02-2016)

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Francesco Di Maio, Giancarlo Nicola, Enrico Zio, Yu Yu. Finite mixture models for sensitivity analysis of thermal hydraulic codes for passive safety systems analysis. Nuclear Engineering and Design, 2015, 289, pp.144-154. ⟨10.1016/j.nucengdes.2015.04.035⟩. ⟨hal-01265884v2⟩
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