AbstractThe divertor plate represents a critical component in the design of a tokamak fusion reactor. Within the frame of the International Tokamak Experimental Reactor (ITER), many proposals are underway. The thermal behaviour following a complete Loss of Coolant Accident of a pre-designed divertor plate is analyzed in this paper. The aim is to carry out a parametric study on the most critical parameter, i.e. the plasma shutdown time. Several load hypotheses are studied in order to contribute to a better understanding of the design requirements for the components. According with these results, a significative material damage is expected to occur when plasma burning is not efficiently stopped within some seconds after the LOCA detection.
Power plant design study of a high aspect ratio Tokamak using a SiC composite structure