Nuclear Engineering and Design
 1997
DOI: 10.1016/s0029-5493(97)00177-5
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Simulation and analysis of transient cooldown natural convection experiments

Truc-Nam Dinh
1
,
Bal Raj Sehgal
2
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Cited by 8 publications
(1 citation statement)
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“…However, the cooling process of fluids with low Pr is also of great interest; for example, in the flooding of the reactor cavity of nuclear power plants in case of an accident [13]. Hyun [14] studied the effect of the Prandtl number on the fluid heating-up.…”
Section: Nomenclaturementioning
confidence: 99%

Transient Laminar MHD Natural Convection Cooling in a Vertical Cylinder

Iatridis
1
,
Sarris
2
,
Vlachos
3
2012
Numerical Heat Transfer, Part A: Applications
5
0
2
0
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“…However, the cooling process of fluids with low Pr is also of great interest; for example, in the flooding of the reactor cavity of nuclear power plants in case of an accident [13]. Hyun [14] studied the effect of the Prandtl number on the fluid heating-up.…”
Section: Nomenclaturementioning
confidence: 99%

Transient Laminar MHD Natural Convection Cooling in a Vertical Cylinder

Iatridis
1
,
Sarris
2
,
Vlachos
3
2012
Numerical Heat Transfer, Part A: Applications
5
0
2
0
View full textAdd to dashboardCite

An approach to numerical simulation and analysis of molten corium coolability in a boiling water reactor lower head

Tran
1
,
Kudinov
2
,
Dinh
3
2010
Nuclear Engineering and Design
34
0
8
0
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The effective convectivity model for simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part II: Model assessment and application

Tran
1
,
Dinh
2
2009
Progress in Nuclear Energy
34
0
4
0
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