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

页码：657 / 685

页数：29

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