Certain corrosion and fission products of importance in reactor
waste management cannot be measured by gammaspectrometric
techniques. In this study, a met.hod is suggested by which the
occurrence of such nuclides can be quantitatively related to
suitable gamma-emitters of similar origin. The method is tested
by statistical analysis on the waste data recorded from two
Swedish nuclear power plants. As this method is not applicable
for Carbon-14, this nuclide was measured directly in spent ion
exchange resins from three Finnish and Swedish power plants.