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
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