Abstract
The primary circuit of a pulsed type fusion reactor will be subjected to cyclic loads at high temperature. Deformation rates will be in the range from below 10 −6 s −1 (creep) to 1 s −1 (fatigue) leading to creep-fatigue interaction in the neutron irradiated structural materials. The effects of neutron irradiation on fatigue and fatigue-creep interaction are reviewed. The study of austenitic stainless steel is most advanced, but the test conditions are still far from the first wall operating conditions, leaving a lot of uncertainties. It is expected that irradiation reduces the fatigue-creep endurance of austenites to very low levels, because of enhanced intergranular cracking. Two classes of alloys in an early stage of development, low activation steels and vanadium base alloys, hold the promise to be more fatigue-creep resistant due to their more ductile creep behaviour.
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