Calculation of the moderator temperature coefficient of reactivity for miniature neutron source reactors

Abstract

This paper presents results of the evaluated group constants for fuel and other important materials of the Miniature Neutron Source Reactor (MNSR) and the moderator temperature coefficient of reactivity through global reactor calculation. In this study, the group constants were calculated with the WIMSD code and the global reactor calculation is accomplished by the CITATION code. This work also presents a method for evaluation of the moderator temperature coefficient of reactivity at different temperatures and it’s average value in a range of temperatures directly through the values of moderator temperature ​​for MNSRs. This method provides simple analytical representation convenient for reactor kinetics calculation and reactor safety assessment.