Preliminary No Core Melt Assessment for Canadian SCWR With Modified SCTRAN

Abstract

With developing a two-dimensional conduct solution and incorporating a radiation model, the safety analysis code SCTRAN for SCWR is modified to own the ability to calculate the radiation heat transfer in this paper. Then it’s used to analysis the LOCA with loss of ECCS accident of Canadian SCWR to verify its “no core melt” concept. The below conclusions are achieved: 1) in the process of LOCA, about 2.5% of the decay power can be totally removed by the radiation heat transferring to the pressure tube even without an intervention of ECCS, which means that the Canadian SCWR has the potential to accomplish the object of “NO-CORE-MELT”; 2) The HP channel experience the most serious condition because it owns the highest power production. The MCST of the fuel rods in the inner and outer rings of the HP channel are separately 1409oC and 1344oC, which is a little bit high for the cladding material. Core optimization and material study should be carried on.