Abstract
In the last years the V Ti Cr alloys were considered as candidate materials for different structures of Fusion Reactors (blanket, first wall, divertor and so on) due to their advantages over other structure materials. Mobility and trapping parameters of hydrogen are essential characteristics for an assessment of using the V Ti Cr alloys in FR. In this paper: hydrogen problems for V Ti Cr alloys are formulated; V H system data base is analyzed; study results of the hydrogen mobility and trapping in V 4Ti 4Cr and V 10Ti 5Cr alloys are given; the classification of V-alloys as radioactive waste according to the Russian Federation waste management rules is developed taking into account the residual amount of tritium (‘inventory’).
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