Preliminary Numerical Modelling of No-core-melt in the Generation IV Canadian SCWR

Abstract

Heat transfer through a typical fuel channel in a Generation IV Canadian Supercritical Water Reactor was modelled numerically using Finite Element Method software. With the objective of limiting the fuel cladding to sub-melting temperatures during a Loss of Coolant Accident, it was found that two distinct fuel channel designs both attained maximum cladding surface temperatures of approximately T = 1,393 K; a result that compared favourably with the 1,723 Kmelting point of the stainless steel cladding. The ratios of LOCA to normal operation thermal fluxes were also computed and it was observed that the reference configuration performed best by limiting losses in normal operation while also permitting sufficient heat rejection to the moderator during the LOCA.