On a Monte Carlo method for neutron transport criticality computations

^** Email: maire{at}univ-tln.fr^*** Email: denis.talay{at}sophia.inria.fr We give a stochastic representation of the principal eigenvalueof some homogeneous neutron transport operators. Our constructionis based upon the Feynman–Kac formula for integral transportequations, and uses probabilistic techniques only. We developa Monte Carlo method for criticality computations. We numericallytest this method on various homogeneous and inhomogeneous problems,and compare our results with those obtained by standard methods.