Preliminary Development and Verification of Divertor Module for CFETR System Safety Analysis Code

Abstract

China Fusion Engineering Test Reactor (CFETR), the next-generation fusion device of China, is designed to bridge the gap between International Thermonuclear Experimental Reactor (ITER) and the commercial fusion power plant by solving the essential physical, engineering, and technical problems, including tritium self-sufficiency and high duty cycle of 0.3–0.5. Before the completion of the design and construction of CFETR, the thermal-hydraulic safety assessment is needed in order to ensure the safety of nuclear facilities and to get the national nuclear safety license. Up to now, there is no specialized code for the fusion reactor safety assessment. And the safety assessment work that had been done for the fusion device is completed by the system safety analysis code for pressurized water reactors, such as RELAP5, CHATHARE, and so on. For developing a simulation tool that can meet the safety assessment needs of the fusion reactor, some special models need to be established compared to the fission reactor. In this article, the development of a module for the divertor is presented. The thermal-hydraulic safety of the divertor with design basis accidents, and in-vessel loss of coolant (LOCA), is analyzed based on the developed code. Comparisons are performed to verify the reliability and feasibility of the developed code.