原子能科学技术Issue(11)：1954-1960,7.DOI:10.7538/yzk.2015.49.11.1954
基于抽样方法的特征值不确定度分析
Eigenvalue Uncertainty Analysis Based on Statistical Sampling Method
摘要
Abstract
The nuclear data are the basic data for reactor physics calculation.It is signif-icant to study the contribution of their uncertainty to the uncertainty of reactor physics calculation for improving the safety and economy of reactor.Based on the ENDF/B-Ⅶ.1 library,the covariance library including the variance and covariance for all the basic cross sections and all the groups was generated using the NJOY code.The uncertainty analysis code UNICORN for reactor physics calculation was developed based on the statistical sampling method.Based on the UNICORN and covariance library,the uncer-tainties of k∞ for Three Mile Island (TMI)lattice and RB31 benchmark,due to the uncertainty of basic cross sections,were analyzed.The results indicate that the uncer-tainty of 238 U(n,γ)cross section is the largest uncertainty to the k∞ of TMI lattice and the relative uncertainty to the k∞ is up to about 0.4%,and different sources of covari-ance library effect the uncertainty of analysis result.关键词
不确定度分析/抽样方法/核数据库Key words
uncertainty analysis/statistical sampling method/nuclear library分类
能源科技引用本文复制引用
万承辉,曹良志,吴宏春,祖铁军,沈炜..基于抽样方法的特征值不确定度分析[J].原子能科学技术,2015,(11):1954-1960,7.基金项目
国家自然科学基金资助项目(91226106) （91226106）
863计划资助项目(2013AA051402) （2013AA051402）
上海核工程研究设计院资助项目 （）
