Code development for eigenvalue total sensitivity analysis and total uncertainty analysis

被引：27

作者：

Wan, Chenghui ^{[1
]}

Cao, Liangzhi ^{[1
]}

Wu, Hongchun ^{[1
]}

Zu, Tiejun ^{[1
]}

Shen, Wei ^{[1
,2
]}

机构：

[1] Xi An Jiao Tong Univ, Xian 710049, Shaanxi, Peoples R China

[2] Canadian Nucl Safety Commiss, Ottawa, ON, Canada

来源：

ANNALS OF NUCLEAR ENERGY | 2015年 / 85卷

基金：

中国国家自然科学基金;

关键词：

Sensitivity analysis; Uncertainty analysis; Implicit effects; Cross sections;

D O I：

10.1016/j.anucene.2015.06.036

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：

The uncertainties of multigroup cross sections notably impact eigenvalue of neutron-transport equation. We report on a total sensitivity analysis and total uncertainty analysis code named UNICORN that has been developed by applying the direct numerical perturbation method and statistical sampling method. In order to consider the contributions of various basic cross sections and the implicit effects which are indirect results of multigroup cross sections through resonance self-shielding calculation, an improved multigroup cross-section perturbation model is developed. The DRAGON 4.0 code, with application of WIMSD-4 format library, is used by UNICORN to carry out the resonance self-shielding and neutron-transport calculations. In addition, the bootstrap technique has been applied to the statistical sampling method in UNICORN to obtain much steadier and more reliable uncertainty results. The UNICORN code has been verified against TSUNAMI-1D by analyzing the case of TMI-1 pin-cell. The numerical results show that the total uncertainty of eigenvalue caused by cross sections can reach up to be about 0.72%. Therefore the contributions of the basic cross sections and their implicit effects are not negligible. (C) 2015 Elsevier Ltd. All rights reserved.

引用

页码：788 / 797

页数：10

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