Structural material requirements and related R and D for ITER plasma-facing components

Solution-annealed 316 type austenitic steels have been selected as structural material for the first wall and blanket of ITER, with cold-worked 316 and MnCr austenitic steels as candidate alloys. The effects of irradiation on their properties: tensile, fracture toughness, low cycle fatigue, creep and rupture, swelling, stress corrosion cracking and hydrogen embrittlement, are discussed in terms of the proposed ITER operating conditions. Arguments for the selection of oxide dispersion strengthened Cu alloy for divertor plates are presented. Finally, the investigations which are being undertaken within the ITER Technology Programme to provide additional data are reviewed.