ITER first wall and divertor design and its influence on materials selection (including first wall test results)
The plasma facing components (PFC) for ITER will be exposed to severe and not yet easily predictable operating conditions, that are not experienced in other technologies. Thus, the PFC design will be crucial both for the achievable plasma performance and the machine availability. The integration of the main PFC in ITER with the reference 22 MA double null plasma for ignition studies is illustrated, showing that about 750 m2 of first wall are integrated with the blanket segments and that about 200 m2 of divertor plates are required for the removal of impurities and thermal power from the plasma edge. The ITER conceptual design activity has now led to the definition of likely operating requirements for PFC, basic design concepts including assessment, and R&D plans to support the contemplated engineering design activity.
Bibliographic Reference: Paper presented: 2nd International Symposium on Fusion Nuclear Technology, Karlsruhe (DE), June 2-7, 1991
Availability: Available from (1) as Paper EN 36171 ORA
Record Number: 199110748 / Last updated on: 1994-12-02
Original language: en
Available languages: en