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An official journal of Viet Nam National University Ho Chi Minh City, Viet Nam since 1997

ISSN: 1859-0128
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CALCULATION OF THE MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY FOR MINIATURE NEUTRON SOURCE REACTORS

Binh Quang Do 1, *
Hai Hoang Nguyen 2

  1. University of Technical Education-HoChiMinh City
  2. Research and Development Center for Radiation Technology, Ho Chi Minh city
Correspondence to: Binh Quang Do, University of Technical Education-HoChiMinh City. Email: pvphuc@hcmuns.edu.vn.
Volume & Issue: Vol. 15 No. 3 (2012) | Page No.: 26-35 | DOI: 10.32508/stdj.v15i3.1844
Published: 2012-09-30

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Copyright © 2012 by the author(s).

Copyright The Author(s) 2023. This article is published with open access by Vietnam National University, Ho Chi Minh city, Vietnam. This article is distributed under the terms of the Creative Commons Attribution License (CC-BY 4.0) which permits any use, distribution, and reproduction in any medium, provided the original author(s) and the source are credited. 

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 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.

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