Safety relevant effects of neutron irradiation (material activation, decay heat, radiation damage, heat deposition and gas production) on the in-vessel components materials of the ITER-EDA and the preliminary European ITER-RC designs are assessed. The integrated radiation transport and activation methodological approach based on the calculation sequence Vitamin(ENEA)-Scale-ANITA has been used. The first wall and shield blanket are water cooled and the structural material is AISI 316LN with Be as a protective layer material.
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