Open AccessCALCULATION OF THE MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY FOR MINIATURE NEUTRON SOURCE REACTORS
Author(s) -
Quang Binh,
Huy Hung Nguyen
Publication year - 2012
Publication title -
khoa học công nghệ
Language(s) - English
Resource type - Journals
ISSN - 1859-0128
DOI - 10.32508/stdj.v15i2.1796
Subject(s) - temperature coefficient , nuclear engineering , research reactor , neutron moderator , neutron source , reactivity (psychology) , neutron temperature , work (physics) , materials science , moderation , atmospheric temperature range , neutron , delayed neutron , thermodynamics , chemistry , neutron cross section , nuclear physics , physics , mathematics , statistics , composite material , engineering , medicine , alternative medicine , pathology
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.