Progresses in the structural assessment of the central region of a HELIAS 5-B breeding blanket half sector

Assessment of potential heat flux overload of target and first wall components in Wendelstein 7-X finite-beta magnetic configurations and choice of locations for temperature monitoring

“…The remaining surface of the plasma vessel is covered partly by wall protection tiles of the same design as the baffles [16], partly by steel panels [17]. In the future stellarator FPPs, almost all the plasma vessel internal wall will be covered by breeding blanket modules [18][19] [20] [21] aimed at removing the thermal power generated by the fusion plasma, shielding the magnets from neutron and gamma radiation and ensuring the tritium breeding of the plant.…”