Analyses of unprotected loss of flow accidents for 500MWe U–Pu–6% Zr and U–Pu–10% Zr
metal fueled sodium cooled reactors are presented and compared with that of the 500MWe …

Under a hypothetical core meltdown and relocation scenario in Sodium cooled Fast Reactor
(SFR), there may be a chance for reactor main vessel failure if the core debris are allowed to …

During core disruptive accident (CDA) in a typical medium-sized fast breeder reactor (FBR),
a significant amount of corium (core melt) relocates to the bottom plate of the grid plate after …

Abstract Analysis of unprotected loss of flow accident for 500 MWe U-Pu-6% Zr and U-Pu-
10% Zr metal fueled sodium cooled reactors is presented and compared with that of the 500 …

The main objective of this numerical study is to develop heat transfer correlations for natural
convection in sodium filled cylindrical cavities heated on the top side and cooled at the …