CALCULATION OF THE MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY FOR MINIATURE NEUTRON SOURCE REACTORS

Neutron moderator Moderation Temperature coefficient Reactivity
DOI: 10.32508/stdj.v15i3.1844 Publication Date: 2020-03-24T14:17:18Z
ABSTRACT
This paper presents results of the evaluated group constants for fuel and other important materials Miniature Neutron Source Reactor (MNSR) moderator temperature coefficient reactivity through global reactor calculation. In this study, were calculated with WIMSD code calculation is accomplished by CITATION code. work also a method evaluation temperatures directly values MNSRs. provides simple analytical representation convenient kinetics safety assessment.
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