A facility within WIMS-E for solving multigroup transport problems with external neutron sources

Lattice calculations are routinely solved in the multigroup formulation of neutron transport using the WIMS-E suite of computer programs. By providing a short handling program it is shown here that WIMS-E can be employed to solve neutron transport reflector problems for an input external neutron source containing some or no fissile materials. The method offers the chance to capitalise on the numerous WIMS geometry options and has most relevance to situations where smeared few group nuclear data are required for reflector volumes composed of reflector plus structural materials in quite complicated geometry. The question of source distribution to be used has to be resolved for each problem. (UK)