Abstract
One of the features peculiar to the application of 316L(N) steel for International Thermonuclear Experimental Reactor components is that it will be used in such components as the divertor and the first wall, mainly as part of the Cu–stainless steel bimetal composition. The main purpose of this investigation was to estimate the effect of heat treatment on the radiation hardening and embrittlement of 316L(N) steel. The report presents the results from an experimental investigation into the effect of low-temperature neutron irradiation on the radiation hardening and embrittlement in 316L(N) steel after different heat treatments. Specimens of 316L(N) steel were irradiated at T irr=150 and 80 °C in the dose range 0.001–2 dpa in the RBT-6 and SM-2 reactors. It is shown that heat treatment does not cause a significant effect on the radiation hardening and embrittlement of 316L(N) steel.
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