Progress in Nuclear Energy
 2014
DOI: 10.1016/j.pnucene.2013.10.015
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Thermal hydraulic analyses of JRR-3: Code-to-code comparison of COOLOD-N2 and TMAP

Mohammad A. Albati
1
,
Omar S. Al-Yahia
2
,
Jonghark Park
3
et al.
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Cited by 13 publications
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References 7 publications
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RETRACTED: A new strategy to select axial power distribution for thermal hydraulic analysis

Kim
1
,
Park
2
,
Jo
3
2016
Annals of Nuclear Energy
1
0
0
0
1
1
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RETRACTED: A new strategy to select axial power distribution for thermal hydraulic analysis

Kim
1
,
Park
2
,
Jo
3
2016
Annals of Nuclear Energy
1
0
0
0
1
1
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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
16
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9
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SACOS-PLATE: A new thermal-hydraulic subchannel analysis code for plate type fuel assemblies

Sun,
Gui,
Wang
et al. 2024
Annals of Nuclear Energy
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