A method has been developed for generating damage functions for the correlation and prediction of neutron-induced property changes. The method affords a procedure for studying and determining the neutron spectral dependence of irradiation-effects data obtained in test reactors withh subsequent application of results to the establishment of more exact engineering design fluence limits for reactor components. The method has been applied to ductile-brittle transition temperature increase data obtained in different test-reactor spectra. Results show that neutrons of all energies must be included for best overall interpretation of the experimental irradiation effects data.