On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material

Within the European Fusion Technology Programme, research activities have been conducted on the Helium-Cooled Lithium Lead (HCLL) breeding blanket concept with the aim of manufacturing a Test Blanket Module (TBM) to be irradiated in ITER. HCLL-TBM is planned to be located in an ITER equatorial port, housed inside an AISI 316 stainless steel-supporting frame. Since that frame has been designed to provide two positions separated by a dividing plate and the HCLL-TBM is expected to fill one of them, its nuclear response could vary depending on the filling status of the other position and on the plate thickness. A parametric study has been carried out to investigate the potential effects on the radiation-induced damage of the HCLL-TBM structural material, due to the dividing plate thickness and to the presence of either a void, a water-cooled steel plug, or a Helium-Cooled Pebble Bed TBM in the adjacent frame position.