Progress on design and R&D of ITER FW/blanket

Abstract The electromagnetic (EM) load on the first wall (FW) panel during disruptions is reduced by slots penetrating the copper layer and the SS backing plate. The maximum stress in the central beam is within the allowables under the most significant load induced by halo currents. In the recent ITER R&D, full-scale FW panels have been manufactured successfully by hot isostatic pressing (HIP) as the reference method. The shield block cooling scheme consists of front water headers that distribute the coolant in radial channels. The shield block is composed of four flat forged blocks electron-beam (EB) welded together at the rear side. Recently, full-scale shield blocks were fabricated by drilling/machining and plugging/welding of flat forged blocks, and assembled with a FW panel with a central beam. Detailed design has progressed on the blanket attachments. Buckling tests, fatigue tests and dynamic load tests have been performed on the T-alloy flexible support (550 kN). Mechanical and thermal fatigue tests, and electrical tests in a solenoid coil, have been carried out on the electrical connection (280 kA). Feasibility of the blanket sub-components has been demonstrated through the R&D.