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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
MW/m2 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.
IAEA 2001
