Design and material selection for ITER first wall/blanket, divertor and vacuum vessel

SCC behavior of solid-HIPed and irradiated type 316LN-IG stainless steel in oxygenated or hydrogenated water at 423–603K

“…Because the in-vessel components, such as a shield blanket, would be fabricated by a solid hot-isostatic pressing (solid-HIPing) technique [18,19], specimens were prepared from the solid-HIPed joints of the type 316LN-IG SS plates. The solid-HIPing condition is described elsewhere [20,21].…”

Changes in hardness and elasticity of a Ti6Al4V alloy under helium irradiation

“…The latest design of the next fusion reactor includes the use of titanium alloys in specific parts of the structure. In particular, the (a + b) alloy Ti 6 Al 4 V has been proposed to be used in flexible supports between the ITER blanket modules and the vacuum vessel [6,7]. One of the most important technical issues for the titanium alloys as fusion structural material is the influence of the transmutant helium production on the irradiation-related mechanical property changes.…”

The effect of neutron irradiation on mechanical properties of YAG laser weldments using previously irradiated material

“…In a fusion reactor such as the International Thermonuclear Experimental Reactor (ITER), a blanket surrounds the plasma and protects the vessel material from high levels of nuclear radiation [1,2]. On the maintenance of the blanket, the used blanket is removed after cutting coolant piping of the blanket.…”