In the last years the V-Ti-Cr alloys were considered as candidate mate
rials for different structures of Fusion Reactors (blanket, first wall
, divertor and so on) due to their advantages over other structure mat
erials. Mobility and trapping parameters of hydrogen are essential cha
racteristics for an assessment of using the V-Ti-Cr alloys in FR. In t
his paper: hydrogen problems for V-Ti-Cr alloys are formulated; V-H sy
stem data base is analyzed; study results of the hydrogen mobility and
trapping in V-4Ti-4Cr and V-10Ti-5Cr alloys are given; the classifica
tion of V-alloys as radioactive waste according to the Russian Federat
ion waste management rules is developed taking into account the residu
al amount of tritium ('inventory').