Annals of Nuclear Energy
 2018
DOI: 10.1016/j.anucene.2018.04.014
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Thermal hydraulic analysis of loss of flow accident in the JRR-3M research reactor under the flow blockage transient

Yuchuan Guo
1
,
Guanbo Wang
2
,
Dazhi Qian
3
et al.
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Cited by 7 publications
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A Support Vector Machine Model for Detection of Transients in Nuclear Reactor

Arunprasath,
Santhosh,
Vinod
et al. 2024
Lecture Notes in Mechanical Engineering
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A Support Vector Machine Model for Detection of Transients in Nuclear Reactor

Arunprasath,
Santhosh,
Vinod
et al. 2024
Lecture Notes in Mechanical Engineering
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Accident safety analysis of flow blockage in an assembly in the JRR-3M research reactor using system code RELAP5 and CFD code FLUENT

Guo
1
,
Wang
2
,
Qian
3
et al. 2018
Annals of Nuclear Energy
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Study on the effect of flow blockage due to rod deformation in QUENCH experiment

Gao
1
,
Zhang
2
,
Shan
3
2022
Nuclear Engineering and Technology
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