Accident safety analysis of flow blockage in an assembly in the JRR-3M research reactor using system code RELAP5 and CFD code FLUENT
Author:
Funder
National Natural Science Foundation of China
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference24 articles.
1. Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core;Adorni;Ann. Nucl. Energy,2005
2. Thermal hydraulic analysis of JRR-3: code-to code comparison;Albati;Prog. Nucl. Energy,2014
3. Transient thermal-hydraulic analysis of single flow channel blockage in the JRR-3M 20MW research reactor;Guo;Nucl. Technol.,2018
4. Thermal hydraulic analysis of loss of flow accident in the JRR-3M research reactor under the flow blockage transient;Guo;Ann. Nucl. Energy,2018
5. Analytical study on thermal-hydraulic behavior of transient from forced circulation to natural circulation in JRR-3;Hirano;J. Nucl. Sci. Technol.,1986
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