Transients analysis of the offshore fixed multi-purpose integrated all-natural-cycle small lead-cooled reactor with the FRTAC code

Abstract

The offshore fixed multi-purpose integrated all-natural circulation small lead-cooled reactor is one of the safest and most economical offshore nuclear power plant solution. In order to verify the safety and rationality of the reactor design, this study used the lead-cooled reactor safety analysis code FRTAC to complete the construction of the offshore reactor loop model and simulated unprotected transient overpower accidents (UTOP) and unprotected Loss of Heat Sink accidents (ULOHS). The reactor physics parameters of the offshore reactor and the fission gas yield were calculated by the neutron transport calculation code Serpent. Based on the transient accident calculation results, we can preliminarily confirm that the offshore reactor can withstand the introduction of reactivity of up to 0.42$ under UTOP scenario; and under different degrees of ULOHS scenario, the maximum operating temperature of the offshore reactor core will not exceeds its failure limits.