Sensitivity analysis of VERA-CS and FRAPCON coupling in a multiphysics environment

被引:7
作者
Blakely, Cole [1 ]
Zhang, Hongbin [2 ]
Ban, Heng [1 ]
机构
[1] Utah State Univ, Dept Mech & Aerosp Engn, Old Main Hill, Logan, UT 84322 USA
[2] Idaho Natl Lab, 2525 Fremont Ave, Idaho Falls, ID 83415 USA
关键词
Multiphysics environment; Uncertainty quantification; Sensitivity analysis; VERA-CS; FRAPCON; FUEL PERFORMANCE; UNCERTAINTY; BEHAVIOR;
D O I
10.1016/j.anucene.2017.09.029
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
A demonstration and description of the LOCA Toolkit for US light water reactors (LOTUS) is presented. Through LOTUS, the core simulator VERA-CS developed by CASL is coupled with the fuel performance code FRAPCON. The coupling is performed with consistent uncertainty propagation with all model inconsistencies being well-documented. Monte Carlo sampling is performed on a single 17 x 17 fuel assembly with a three cycle depletion case. Both uncertainty quantification (UQ) and sensitivity analysis (SA) are used at multiple states within the simulation to elucidate the behavior of minimum departure from nucleate boiling ratio (MDNBR), maximum fuel centerline temperature (MFCT), and gap conductance at peak power (GCPP). The SA metrics used are the Pearson correlation coefficient, Sobol sensitivity indices, and the density-based, delta moment independent measures. Results for MDNBR show consistency among all SA measures, as well for all states throughout the fuel lifecycle. MFCT results contain consistent rankings between SA measures, but show differences throughout the lifecycle. GCPP exhibits predominantly linear relations at low and high burnup, but highly nonlinear relations at intermediate burnup due to abrupt shifts between models. Such behavior is largely undetectable to traditional regression or variance-based methods and demonstrates the utility of density-based methods. (C) 2017 Elsevier Ltd. All rights reserved.
引用
收藏
页码:683 / 701
页数:19
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