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

• Published in: Fusion engineering and design 2012-08, Vol.87 (7-8), p.1019-1024
• Main Authors: Palermo, I., Gómez-Ros, J.M., Veredas, G., Sanz, J., Sedano, L.
• Format: Article
• Language: English
• Subjects: Blanket; Blanketing; Coils; Design analysis; Design engineering; Neutronic response; Nuclear power generation; Nuclear reactor components; Optimization; Peak nuclear heating; Specifications; TBR; Vacuum vessel
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2012.02.067

► Dual-Coolant He/Pb15.7Li breeding blanket for a DEMO fusion reactor is studied. ► An iterative process optimizes neutronic responses minimizing reactor dimension. ► A 3D toroidally symmetric geometry has been generated from the CAD model. ► Overall TBR values support the feasibility of the conceptual model considered. ► Power density in TF coils is below load limit for quenching. The generation of design specifications for a DEMO reactor, including breeding blanket (BB), vacuum vessel (VV) 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/Pb15.7Li breeding blanket design. The iteration process focuses on the optimization of allowable space between plasma scrapped-off-layer and VV in order to generate a MFC/VV/BB/plasma sustainable configuration with minimum global system volumes. Two VV designs have been considered: (1) a double-walled option with light-weight stiffeners and (2) a thick massive one. The optimization process also involves VV 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.