Neutron irradiation effects on the ITER-EDA and ITER-RC first wall/blanket materials

摘要

Safety relevant effects of the 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 FW/SB are water cooled and the structural material is AISI 316LN with Beryllium as protective layer material.