Fast and Intermediate Energy Neutron Albedos for Fusion Materials

Neutron albedo methods can be used to simplify transport calculations in a wide variety of applications. Their utilization requires a collection of albedo data and a model which makes these results convenient for hand or machine computation. Results are presented here from neutron albedo calculations for incident intermediate-energy neutrons. These results can be explained using our knowledge of neutron interaction physics. Total albedos are directly related to the cross sections for elastic scatter and absorption. Angular distributions of reflected neutrons are approximately cos^θ_r for all incident neutron conditions. The total albedo results are well modeled by an extension of a previously developed fast-neutron albedo model when ∑_abs/∑_t (the ratio of absorption to total cross section) is small.