Transmutation and Activation Cross Sections Important for Reuse of Fusion Materials

Abstract

Important neutron reactions relevant to the generation of medium and long-lived radionuclides of significance to waste management in a fusion power plant have been identified. Cross sections from EAF-2001 were used to calculate the concentrations of these significant induced radionuclides. The concentrations of these radionuclides, namely A126, Co60, Nb94, and Agl08m, and the corresponding contact dose rates, due to 1 ppm of their parent impurities in the blanket and hot shield components made of vanadium based structural alloy, were calculated. The concentration of induced Ar42 in the V-4Cr-4Ti alloy was also calculated after the respective lifetime of the power plant components. A review was made of the important transmutation and activation cross sections.

Keywords:

• fusion power plant
• long-lived radionuclide
• activation cross section
• contact dose rate
• A126
• Ar42
• Co60
• Nb94
• Agl08m