Development of a hybrid neutron transport method in 2 energy groups

Abstract

A new hybrid neutron transport method was developed and implemented using the response matrix formulation. The method combines the advantages of deterministic and probabilistic modelling, namely the flexibility in modelling any geometry with high accuracy and the low computing cost of the hybrid scheme. The probabilities associated with the response matrix formulation were determined using the Monte-Carlo based code Serpent2. Further a deterministic code was written to solve for the neutron flux using the response matrix method. With some modifications to Serpent2 the needed probabilities could be determined and a converged neutron flux solution was achieved, for a simplified BWR fuel assembly, using the written deterministic code.