On a Monte Carlo method for neutron transport criticality computations

被引：0
|
作者：
Maire, Sylvain
Talay, Denis
机构：
[1] Univ Toulon & Var, ISITV, F-83162 La Valette Du Var, France
[2] INRIA, F-06902 Sophia Antipolis, France
来源：
IMA JOURNAL OF NUMERICAL ANALYSIS | 2006年 / 26卷 / 04期
关键词：
neutron transport equations; principal eigenvalue; criticality; Monte Carlo method; Feynman-Kac formula; variance reduction;
D O I：
10.1093/imanum/drl008
中图分类号：
O29 [应用数学];
学科分类号：
070104 ;
摘要：
We give a stochastic representation of the principal eigenvalue of some homogeneous neutron transport operators. Our construction is based upon the Feynman-Kac formula for integral transport equations, and uses probabilistic techniques only. We develop a Monte Carlo method for criticality computations. We numerically test this method on various homogeneous and inhomogeneous problems, and compare our results with those obtained by standard methods.
引用
收藏
页码：657 / 685
页数：29
相关论文
共 50 条
  • [1] Uncertainty analysis in Monte Carlo criticality computations
    Ao, Qi
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (12) : 4697 - 4703
  • [2] A MONTE CARLO METHOD FOR SIMULATING STOCHASTIC NEUTRON FIELDS IN CRITICALITY TRANSIENTS
    Xu, Qi
    Wang, Zhe
    Xiao, Gang
    [J]. PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 3, 2018,
  • [3] Multi-Regional Delta-Tracking Method for Neutron Transport Tracking in Monte Carlo Criticality Calculation
    Guo, Qian
    Chen, Zhenping
    [J]. SUSTAINABILITY, 2018, 10 (07)
  • [4] MONTE-CARLO COMPUTATIONS OF NEOCLASSICAL TRANSPORT
    LOTZ, W
    NUHRENBERG, J
    [J]. PHYSICS OF FLUIDS, 1988, 31 (10) : 2984 - 2991
  • [5] COUPLED SAMPLING WITH MONTE CARLO METHOD IN NEUTRON TRANSPORT CALCULATIONS
    CARTER, LL
    MCCORMICK, NJ
    [J]. NUCLEAR SCIENCE AND ENGINEERING, 1970, 39 (03) : 296 - +
  • [6] A MONTE-CARLO METHOD FOR CRITICALITY PROBLEMS
    GOAD, W
    JOHNSTON, R
    [J]. NUCLEAR SCIENCE AND ENGINEERING, 1959, 5 (06) : 371 - 375
  • [7] MONTE CARLO NEUTRON TRANSPORT ON GPUS
    Bergmann, Ryan M.
    Vujic, Jasmina L.
    [J]. PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 4, 2014,
  • [8] Monte Carlo criticality calculations accelerated by a growing neutron population
    Dufek, Jan
    Tuttelberg, Kaur
    [J]. ANNALS OF NUCLEAR ENERGY, 2016, 94 : 16 - 21
  • [9] Study on Neutron Transport Tracking Using Improved Multi-regional delta-tracking Method in Monte Carlo Criticality Calculation
    Chen, Zhenping
    Xie, Jinsen
    Guo, Qian
    Zhang, Zhenyu
    Xie, Chao
    Yu, Tao
    [J]. Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2019, 53 (02): : 261 - 270
  • [10] MONTE-CARLO METHOD FOR ARRAY CRITICALITY CALCULATIONS
    DICKINSON, D
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 23 (JUN18): : 230 - 232
12345