Heat Transfer Processes in Reactor Vessel Lower Plenum During Late Phase of In-Vessel Core Melt Progression

Author(s):  
B.R. Sehgal ◽  
V.A. Bui ◽  
T.N. Dinh ◽  
R.R. Nourgaliev
2001 ◽  
Vol 32 (7-8) ◽  
pp. 7
Author(s):  
M. I. Osipov ◽  
K. A. Gladoshchuk ◽  
A. N. Arbekov

2016 ◽  
Vol 15 (5) ◽  
pp. 1027-1033 ◽  
Author(s):  
Timea Gabor ◽  
Viorel Dan ◽  
Ancuta Elena Tiuc ◽  
Ioana Monica Sur ◽  
Iulian Nicolae Badila

Author(s):  
D. Dupleac

The paper overviews the analytical studies performed at Politehnica University of Bucharest on the analysis of late phase severe accident phenomena in a Canada Deuterium Uranium (CANDU) plant. The calculations start from a dry debris bed at the bottom of calandria vessel. Both SCDAPSIM/RELAP code and ansys-fluent computational fluid dynamics (CFD) code are used. Parametric studies are performed in order to quantify the effect of several identified sources of uncertainty on calandria vessel failure: metallic fraction of zirconium inside the debris, containment pressure, timing of water depletion inside calandria vessel, steam circulation in calandria vessel above debris bed, debris temperature at moment of water depletion inside calandria vessel, calandria vault nodalization, and the gap heat transfer coefficient.


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