Using eddy-current structurescopes, we have studied the resistivity of
domestic zirconium alloys used in nuclear reactors as cladding and ot
her structural materials. The resistivity is demonstrated to be relate
d to the chemical composition and other characteristics of the given a
lloy. The temperature coefficient of resistivity is determined for var
ious alloys and a method is proposed for using it to calibrate eddy-cu
rrent structurescopes. The results of inspections of tubes used to cla
d fuel elements of VVER water-moderated water-cooled reactors are repo
rted.