Neutronic analysis of selected fuel assemblies of the MIT BEAVRS benchmark using HEADE collision probability code

Abstract

Neutronic models for fresh core fuel assemblies of the MIT BEAVRS benchmark are developed using the HEADE collision probability code which is a module of the OSCAR-4 code used for research reactor calculations. This research study is based on the MIT BEAVRS benchmark, which is a specification of a Pressurized Water Reactor (PWR). The neutronics models are performed at 300K, assuming the use of fresh fuel as one state of the BEAVERS benchmark. Parameters such as the kint, power profiles, flux profiles and group constants were evaluated for selected fuel assemblies taken from the MIT BEAVRS benchmark reactor core. In this study, the applicability of the HEADE collision probability code to a PWR calculation is evaluated. The Serpent code was used as a reference code for selected cases, in order to verify HEADE in this study. The results obtained from the HEADE and Serpent codes for various models were investigated and compared and are presented in this dissertation. The behaviour of the results obtained, confirm that the HEADE code can be used for PWR calculations for the cases considered in this study except for those in which spacer grids were included.