Estimation of neutronics parameter sensitivity to nuclear data in random sampling-based uncertainty quantification calculations

被引:6
|
作者
Chiba, Go [1 ]
Kawamoto, Yosuke [1 ]
Tsuji, Masashi [1 ]
Narabayashi, Tadashi [1 ]
机构
[1] Hokkaido Univ, Kita Ku, Sapporo, Hokkaido 0608628, Japan
关键词
Sensitivity profile; Random sampling; Uncertainty quantification; PROPAGATION;
D O I
10.1016/j.anucene.2014.08.049
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
We propose a method to estimate sensitivity profiles of neutronics parameters with respect to nuclear data in random sampling-based uncertainty quantification calculations. The proposed method is tested to estimate sensitivity profiles of fast neutron systems criticalities. A high order effect in sensitivity profile estimation is found to be quite important, so a reverse sampling method is developed to mitigate the high order effect. With this reverse sampling method, detail energy group-wise sensitivity profiles can be estimated even though some fluctuations are observed in specific sensitivity profiles. Energy-integrated sensitivity profiles can be accurately calculated with the proposed method. With the estimated sensitivity profiles, partial uncertainties, that are neutronics parameters uncertainties induced by specific nuclear data uncertainties, are also calculated. Numerical tests reveal that the proposed method reproduces quite well the reference partial uncertainties. A simple and practical partial uncertainty estimation method, which only requires a covariance matrix between neutronics parameter and nuclear data, is also tested and assessed. (C) 2014 Elsevier Ltd. All rights reserved.
引用
收藏
页码:395 / 403
页数:9
相关论文
共 50 条
  • [1] NUSS-RF: stochastic sampling-based tool for nuclear data sensitivity and uncertainty quantification
    Zhu, Ting
    Vasiliev, Alexander
    Ferroukhi, Hakim
    Pautz, Andreas
    Tarantola, Stefano
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2015, 52 (7-8) : 1000 - 1007
  • [2] Combination of sensitivity-based and random sampling-based methodologies for efficient uncertainty quantification calculations with control variates method
    Nihira, Shunsuke
    Chiba, Go
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2019, 56 (11) : 971 - 980
  • [3] Testing the Sampling-Based NUSS-RF Tool for the Nuclear Data-Related Global Sensitivity Analysis with Monte Carlo Neutronics Calculations
    Zhu, Ting
    Vasiliev, Alexander
    Ferroukhi, Hakim
    Rochman, Dimitri
    Pautz, Andreas
    [J]. NUCLEAR SCIENCE AND ENGINEERING, 2016, 184 (01) : 69 - 83
  • [4] Sampling-based estimation method for parameter estimation in big data business era
    Alim, Abdul
    Shukla, Diwakar
    [J]. JOURNAL OF ADVANCES IN MANAGEMENT RESEARCH, 2021, 18 (02) : 297 - 322
  • [5] Exact nuclear data uncertainty propagation for fusion neutronics calculations
    Rochman, D.
    Koning, A. J.
    van der Marck, S. C.
    [J]. FUSION ENGINEERING AND DESIGN, 2010, 85 (05) : 669 - 682
  • [6] Illustration of sampling-based methods for uncertainty and sensitivity analysis
    Helton, JC
    Davis, FJ
    [J]. RISK ANALYSIS, 2002, 22 (03) : 591 - 622
  • [7] Survey of sampling-based methods for uncertainty and sensitivity analysis
    Helton, J. C.
    Johnson, J. D.
    Sallaberry, C. J.
    Storlie, C. B.
    [J]. RELIABILITY ENGINEERING & SYSTEM SAFETY, 2006, 91 (10-11) : 1175 - 1209
  • [8] Optimal sampling-based neural networks for uncertainty quantification and stochastic optimization
    Gupta, Subham
    Paudel, Achyut
    Thapa, Mishal
    Mulani, Sameer B.
    Walters, Robert W.
    [J]. AEROSPACE SCIENCE AND TECHNOLOGY, 2023, 133
  • [9] Evaluation of sampling methods for nuclear data uncertainty quantification
    Zou, Xiaoyang
    Wan, Chenghui
    Cao, Liangzhi
    [J]. ANNALS OF NUCLEAR ENERGY, 2024, 200
  • [10] Status of XSUSA for Sampling Based Nuclear Data Uncertainty and Sensitivity Analysis
    Zwermann, W.
    Gallner, L.
    Klein, M.
    Krzykacz-Hausmann, B.
    Pasichnyk, I.
    Pautz, A.
    Velkov, K.
    [J]. WONDER-2012 - 3RD INTERNATIONAL WORKSHOP ON NUCLEAR DATA EVALUATION FOR REACTOR APPLICATIONS, 2013, 42