Stefan Gicquel

Design and Integration of ITER Divertor Components

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.

Assembly and remote handling of ITER plasma facing components

The assembly and remote maintenance of the plasma-facing components of ITER presents major challenges for the construction, operation and maintenance of ITER. The main plasma-facing components, the divertor and the blankets, are large components, with exceptionally demanding alignment requirements, and require complex support systems to sustain loads under normal and off-normal operational conditions. The plasma-facing components are designed to be maintained using special remote handling (RH) tools. These tools and the associated RH systems and processes are currently undergoing detailed design and certain key processes have been subject to extensive R&D / prototyping activities.