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(ITER/2) ITER In-Vessel System Design and Performance

   
R. R. Parker  (For the ITER Joint Central Team  and ITER Home Teams )
 
ITER Garching Joint Work Site, Max-Planck Institut für Plasmaphysik, Boltzmannstrasse 2, 85748 Garching, Germany

Abstract
This paper reviews the design and performance of the in-vessel components of ITER  as developed for the EDA Final Design Report (FDR). The double-wall vessel is the first confinement boundary and is designed to maintain its integrity under all normal and off-normal conditions, e.g., the most intense VDE's and seismic events. The shielding blanket  consists of modules connected to a toroidal backplate by flexible connectors which allow differential displacements due to temperature differences. Breeding blanket modules replace the shield modules for the Enhanced Performance Phase. The divertor is based on a cassette structure which is convenient for remote installation and removal. High heat flux (HHF) components are mechanically attached and can be removed and replaced in the hot cell. Operation of the divertor is based on achieving partially detached plasma conditions along and near the separatrix. Nominal heat loads of 5-10 $\rm MW/m^2$ are expected and these are accommodated by HHF technology developed during the EDA. Disruptions and VDE's can lead to melting of the first wall  armour but no damage to the underlying structure. Stresses in the main structural components remain within allowables for all postulated disruption and seismic events.

             

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