Stochastic neutron transport equations for rod and plane geometries

In the derivation of the neutron transport equation, it is assumed that neutron populations are large enough so thatfluctuations in the neutron population due to random neutron interactions can be ignored. This assumption is removed in this investigation. The result is a system of stochastic di€erential equations that models the random behavior of neutron transport. Rod and plane geometries are considered in the present investigation. Isotropic scattering is assumed. Numerical procedures are developed and tested for solving these sys- tems. The results are compared with Monte-Carlo calculations which confirm the accuracy of these stochastic neutron transport equations