Open Access 
Downloads
Download data is not yet available.
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.
Author's Affiliation
Article Details
Issue: Vol 15 No 3 (2012)
Page No.: 26-35
Published: Sep 30, 2012
Section: Natural Sciences - Research article
DOI: https://doi.org/10.32508/stdj.v15i3.1844
Copyright Info
Copyright: The Authors. This is an open access article distributed under the terms of the Creative Commons Attribution License CC-BY 4.0., which permits unrestricted use, distribution, and reproduction in any medium, provided the original author and source are credited.
How to Cite
Do, B., & Nguyen, H. (2012). CALCULATION OF THE MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY FOR MINIATURE NEUTRON SOURCE REACTORS. Science and Technology Development Journal, 15(3), 26-35. https://doi.org/https://doi.org/10.32508/stdj.v15i3.1844
Download Citation
Cited by
Article Statistics
HTML = 553 times
Download PDF = 409 times
Total = 409 times
Download PDF = 409 times
Total = 409 times
Most read articles by the same author(s)
- Binh Quang Do, Hai Hoang Nguyen, CALCULATION OF THE MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY FOR MINIATURE NEUTRON SOURCE REACTORS , Science and Technology Development Journal: Vol 15 No 2 (2012)
