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On a Monte Carlo method for neutron transport criticality computations

Sylvain Maire, Denis Talay
2006 IMA Journal of Numerical Analysis  
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.
doi:10.1093/imanum/drl008 fatcat:4bfylnbcdfg2vkidnacn5h3tyy