Abstract
The ITER Divertor is aimed at exhausting the major part of the plasma thermal power including alpha power and at minimizing the helium and impurity content in the plasma. It consists of assembly of 54 divertor cassettes. Each divertor cassette has three plasma-facing components (PFCs) and one cassette body that accommodates these PFCs. The PFCs consist of the Inner and Outer Vertical targets and the Dome. The Vertical Targets directly intercept the magnetic field lines and are designed to withstand heat fluxes as high as 20 MW/m2. After the successful completion of the qualification phase, three Parties (Japan, Europe and Russia) are qualified and they are in charge of procurement of the first Divertor set. In the paper, the detail component design and the manufacturing as well as the integration of the system are reported.
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