Design and simulation of a blanket module with high efficiency cooling system of tokamak focused on DEMO reactor

Abstract

In this study, the neutronic calculation to obtain tritium breeding ratio (TBR) in a deuterium-tritium (D-T) fusion power reactor using Monte Carlo MCNPX is done. In addition, by using COMSOL software, an efficient cooling system is designed. In the proposed design, it is adequate to enrich up to 40% 6Li. Total tritium breeding ratio of 1.12 is achieved. The temperature of helium as coolant gas never exceed 687°C. As regards the tolerable temperature of beryllium (650°C), the design of blanket module is done in the way that beryllium temperature never exceed 600°C. The main feature of this design indicates the temperature of helium coolant is higher than other proposed models for blanket module, therefore power of electricity generation will increase. Keywords: Fusion, Breeding blanket, Tritium, Tokamak, Helium-cooled pebble bed (HCPB)