Abstract
Up to six mock-ups of different tritium breeding blanket systems, referred to as Test Blanket Systems (TBS), will be tested in three equatorial ports of ITER. The paper describes the recent studies performed by the IO for the preparation of the most urgent interfaces required for the integration of the TBSs into the ITER device and Tokamak complex. Main addressed items concern the impact of the TBM ferromagnetic structural material on plasma performance, the preliminary design of the TBM frame, the main dimensions and location for the TBM cooling systems and for the Tritium circuits, and preliminary requirement for measurement systems. A large effort has also been devoted to the proposed maintenance/refurbishment procedure and to the space and equipment requirements in the hot cell facility, including provisions for the shipping of TBM sub-components outside the ITER site for post-irradiation examinations.
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