Neutronic design analyses for a dual-coolant blanket concept: Optimization for a fusion reactor DEMO

摘要

The generation of design specifications for a DEMO reactor, including breeding blanket (BB), vacuum vessel (W) and magnetic field coils (MFC), requires a consistent neutronic optimization of structures between plasma and MFC. This work targets iteratively to generate these neutronic specifications for a Dual-Coolant He/Pbl5.7Li breeding blanket design. The iteration process focuses on the optimization of allowable space between plasma scrapped-off-layer and W in order to generate a MFC/W/BB/plasma sustainable configuration with minimum global system volumes. Two W designs have been considered: (1) a double-walled option with light-weight stiffeners and (2) a thick massive one. The optimization process also involves W materials, looking to warrant radiation impact operational limits on the MFC. The resulting nuclear responses: peak nuclear heating in toroidal field (TF) coil, tritium breeding ratio (TBR), power amplification factor and helium production in the structural material are provided.