The HCLL TBM: present reference design, system integration in ITER and R and D needs

The Helium Cooled Lithium Lead (HCLL) blanket is one of the two European breeding blanket concepts under development for a DEMO power plant and for which mock-ups testing are planned in ITER in one of the 3 equatorial ports dedicated to Test Blanket Modules (TBM). This paper gives an overview of the most recent developments in terms of TBM design, related analyses, fabrication developments, safety features, detailed testing objectives and priorities and corresponding planned test campaign. Required instrumentation, feasibility of its integration in the HCLL-TBM design, and needs of R and D on specific diagnostics will be discussed. Moreover, this paper addresses the issues concerning the interfaces of the HCLLTBM system with ITER and the corresponding proposals of its integration in the ITER machine and buildings. The addressed integration issues in ITER concern several aspects, such as TBM location and attachments in the Port Plug, PbLi ancillary circuit and part of the Helium Cooling System (HCS) components in the Port Cell, access allowance in the Port Cell region, HCS main components in the Torus Cooling Water System vault, piping in the shaft and galleries, required systems for Tritium extraction from He and from the PbLi purge gas in the Tritium building, space needs and specific Remote Handling facilities required for maintenance operations (repairing, Remote Handling disconnecting/connecting components, transport, storage, hot cell operations,..), and diagnostics Data Acquisition System in the control room. For each of these integration aspects, general considerations will be given with a particular emphasis on the unsolved issues. Finally, the envisaged qualification campaign and developments needs for the installation of the HCLL TBM system for day-one of ITER operation, including the main identified milestones, are summarized. (orig.)