摘要
核数据不确定性是造成反应堆物理计算结果不确定性的重要因素之一。基于所需抽样核数据的协方差矩阵开发了随机抽样模块(Stochastic Sampling,SAMP),在此基础上利用SCALE(Standardized Computer Analyses for Licensing Evaluation)软件包实现了混合法和随机抽样法两种不确定性分析方法,以研究多群核数据不确定性对堆芯物理计算的影响。以3×3假想堆芯为对象,对两种方法进行了验证,然后应用于国际原子能机构(International Atomic Energy Agency,IAEA)燃料管理基准题中的Almaraz核电厂首循环堆芯。分析结果表明,两种方法结果符合良好,Almaraz核电厂堆芯keff不确定性约为0.5%,堆芯径向和轴向功率的最大不确定性分别为1.9%和0.45%。
Background： The uncertainty of nuclear data is one of the key factors resulting in the uncertainty of reactor physics calculation. Purpose： The influence of multigroup nuclear data uncertainties on the reactor core physics calculation was studied in this paper. Methods： The stochastic sampling modular SAMP based on covariance matrix of nuclear data was developed, and the hybrid method and stochastic sampling method were realized using SCALE （Standardized Computer Analyses for Licensing Evaluation） software package. The two methods were validated using 3×3 hypothetical core and then applied to the first cycle of Almaraz pressurized-water reactor （PWR） in the IAEA （International Atomic Energy Agency） fuel management benchmark. Results： Results of the two methods are in good agreement. The uncertainty of core effective multiplication factor is about 0.5%, and the maximum uncertainties of the radial and axial power are about 1.9% and 0.45% respectively in Almaraz PWR. Conclusion： The two-step method and stochastic sampling method can both be used for the uncertainty analysis of reactor core calculation.
出处
《核技术》
CAS
CSCD
北大核心
2016年第1期58-64,共7页
Nuclear Techniques
基金
国家科技重大专项(No.2013ZX06002001)资助~~
关键词
多群核数据
不确定性
SCALE
随机抽样
协方差矩阵
Multigroup nuclear data, Uncertainty, SCALE, Stochastic sampling, Covariance matrix
