Thermal hydraulic analysis of loss of flow accident in the JRR-3M research reactor under the flow blockage transient

Author:

Guo YuchuanORCID,Wang Guanbo,Qian Dazhi,Yu Heng,Hu Bo,Guo Simao,Mi Xiangmiao

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference11 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. Probabilistic safety analysis of a Greek Research Reactor;Aneziris;Ann. Nucl. Energy,2004

3. Analytical study on thermal-hydraulic behavior of transient from forced circulation to natural circulation in JRR-3;Hirano;J. Nucl. Sci. Technol.,1986

4. The improvement of COBRA IIIC/MIT-2 and its application to Research Reactor;Jincai;J. Nucl. Sci. Eng.,1996

5. Damage propagation of plate type fuel by flow blockage accident of a research reactor;Lee,2015

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