The Performance of Low Activation Steel SCRAM on ACPs Source Term in Water-cooled Loop of Fusion Reactor ITER

摘要

In this paper, firstly the corrosion rate of Super-clean Reduced Activation Martensitic (SCRAM) steel under ITER operation conditions was measured using a high-temperature flowing-water corrosion experiment loop. Then the model of ITER LIM-OBB loop was simulated by the ACPs source term analysis code CATE, and the nuclide composition and space distribution of ACPs of SCRAM and SS316 were calculated. These results were introduced to the dose rate analysis code ARShield, and the contact dose rate of Out-Flux region in ITER LIM-OBB loop caused by ACPs was calculated. At last, some comparisons among SCRAM and SS316 were made from the point of view of ORE. The results showed that compared with SS316, SCRAM produced higher dose rate during the operation phase of the reactor because of the bad corrosion resistance, but during the shutdown phase, it presented advantage on ORE decrease due to its good activation resistance.