Uncertainty analysis of large break LOCA for pressurized heavy water reactor

被引：5

作者：

Trivedi, A. K. ^{[1
]}

Srivastava, A. ^{[2
]}

Lele, H. G. ^{[2
]}

Kalra, M. S. ^{[1
]}

Munshi, P. ^{[1
]}

机构：

[1] Indian Inst Technol, Nucl Engn & Technol Programme, Kanpur 208016, Uttar Pradesh, India

[2] Bhabha Atom Res Ctr, Reactor Safety Div, Bombay 400085, Maharashtra, India

来源：

NUCLEAR ENGINEERING AND DESIGN | 2012年 / 245卷

关键词：

SAFETY MARGINS;

D O I：

10.1016/j.nucengdes.2012.01.009

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：

Present study involves uncertainty analysis for a large break LOCA of pressurized heavy water reactor (PHWR). It is carried out for the primary safety criteria, peak clad temperature (PCT). Aim of this analysis is to determine the 95th percentile value for PCT during LOCA. Uncertainty quantification for PCT is done based on three different methods: Wilk's method, response surface method (RSM) followed by Monte Carlo simulation and direct Monte Carlo simulation using Latin Hypercube Sampling (LHS). Results obtained by these three methods are compared with acceptance criteria. A best estimate code, RELAP5 MOD3.2, is selected for simulating large break LOCA in 220 MWe PHWR. Statistical analysis is carried out in MATLAB environment. (C) 2012 Elsevier B.V. All rights reserved.

引用

页码：180 / 188

页数：9

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