Uncertainty quantification and sensitivity analysis with CASL Core Simulator VERA-CS

被引:20
|
作者
Brown, C. S. [1 ]
Zhang, Hongbin [2 ]
机构
[1] North Carolina State Univ, Dept Nucl Engn, 2500 Stinson Dr, Raleigh, NC 27695 USA
[2] Idaho Natl Lab, POB 1625, Idaho Falls, ID 83415 USA
关键词
CASL; VERA-CS; Uncertainty quantification; Sensitivity analysis;
D O I
10.1016/j.anucene.2016.05.016
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
VERA-CS (Virtual Environment for Reactor Applications, Core Simulator) is a coupled neutron transport and thermal-hydraulics code under development by the Conscirtium for Advanced Simulation of Light Water Reactors (CASL). An approach to uncertainty quantification and sensitivity analysis with VERA-CS was developed and a new toolkit was created to perform uncertainty quantification and sensitivity analysis. A 2 x 2 fuel assembly model was developed and Simulated by VERA-CS, and uncertainty quantification and Sensitivity analysis were performed with fourteen uncertain. input parameters. The minimum departure from nucleate boiling ratio (MDNBR), maximum fuel center-line temperature, and maximum outer clad surface temperature were chosen as the selected figures of merit. Pearson, Spearman, and partial correlation coefficients were considered for all of the figures of merit in sensitivity analysis and coolant inlet temperature was consistently the most influential parameter. Parameters used as inputs to the critical heat flux calculation with the W-3 correlation were shown to be the most influential on the MDNBR, maximum fuel center-line temperature, and maximum outer clad surface temperature. (C) 2016 Elsevier Ltd. All rights reserved.
引用
收藏
页码:188 / 201
页数:14
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