Calculation Method of Sensitivity Coefficient Based on Statistical Sampling

被引:0
|
作者
Ma X. [1 ]
Tang H. [1 ]
Yang L. [1 ]
Zhu S. [1 ]
Chen Y. [1 ]
机构
[1] School of Nuclear Science and Engineering, North China Electric Power University, Beijing
来源
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2019年 / 53卷 / 12期
关键词
Moto Carlo method; Nuclear engineering; Sampling; Sensitivity coefficient;
D O I
10.7538/yzk.2018.youxian.0873
中图分类号
学科分类号
摘要
Uncertainty and sensitivity analysis of the nuclear system is of great significance for reducing the design margin of nuclear design and improving the economics of the nuclear system. The sampling method for the uncertainty and sensitivity analysis is becoming more and more important because of its simple algorithm, taking into account high-order effects, and no special requirement for response parameters. However, it was previously considered that it was difficult to analyze the sensitivity coefficient based on the statistical sampling method. The main reason was that the change of the response was caused by the simultaneous change of the multivariate, and it was difficult to determine the change of the response caused by the change of a single variable. In this paper, the theoretical formula of sensitivity coefficient analysis using statistical sampling method was deduced firstly. Then the critical formula of bare reactor with two groups approximation and the PWR cell TMI benchmark were verified, and the feasibility of the method was verified. In order to deal with the difficulty of inversion of the covariance matrix of the actual problem, the simplified covariance matrix and the unified perturbation method were proposed in this study, and the two alternative solutions were verified by using the 235U fission cross section. The analysis proves the feasibility of the method. At the same time, the influence of different sensitivity coefficients on the TMI infinite multiplication factor uncertainty was also analyzed. © 2019, Editorial Board of Atomic Energy Science and Technology. All right reserved.
引用
收藏
页码:2413 / 2419
页数:6
相关论文
共 17 条
  • [11] Xu J., Ma X., Shen J., Et al., A new method to evaluate the correlation coefficients between nuclides in uncertainty and sensitivity analysis, Proceedings of the 25th International Conference on Nuclear Engineering, ICONE25, (2017)
  • [12] Xu J., Ma X., Lu F., Nuclear data and fuel/assembly manufacturing uncertainties analysis and preliminary validation of SUACL, Proceedings of the Reactor Physics Asia 2017(RPHA17) Conference, (2017)
  • [13] Ma X., Xu J., Lu F., Et al., Uncertainty analysis by concerning effective resonance integral based on sampling method, Atomic Energy Science and Technology, 51, 12, pp. 2248-2252, (2017)
  • [14] Wan C., Cao L., Wu H., Et al., Eigenvalue uncertainty analysis based on statistical sampling method, Atomic Energy Science and Technology, 49, 11, pp. 1954-1960, (2015)
  • [15] Liu Y., Cao L., Wu H., Et al., Eigenvalue sensitivity and uncertainty analysis based on classical perturbation theory, Atomic Energy Science and Technology, 49, 7, pp. 1247-1253, (2015)
  • [16] Pan X., Lan B., Zhang C., Et al., Influence of multigroup nuclear data uncertainties on the reactor core physics calculation, Nuclear Techniques, 39, 1, (2016)
  • [17] Macfarlanef R.E., Kahler A.C., Methods for processing ENDF/B-Ⅶ with NJOY, Nuclear Data Sheets, 111, 12, pp. 2739-2890, (2010)