This paper summarises and discusses the results of the material damage assessment for the in-vessel components of the International Tokamak Experimental Reactor (ITER), with reference to the baseline design defined in the Interim Design Report 95 (IDR 95) by the ITER Joint Central Team (JCT).

dpa has been calculated for various zones of the First Wall (FW) and of the Shield Blanket (SB), where stainless steel is located. The second damage exposure index that has been considered and estimated is the gas production into the various ITER zones.