Standard recommended practice for reporting dosimetry results on nuclear graphite

A procedure for determination and reporting of the neutron flux density and fluence for the correlation of radiation-induced changes in nuclear graphite are described. The equivalent fission fluence for damage in graphite is defined mathematically, and the proper use of the function with relation to flux spectra, scattering cross section, etc. is specified. Correlations made by this method indicated that an overall precision of +-15 percent is obtainable over a wide range of irradiation facilities between the calculated numbers of displaced atoms and the changes in dimensions or physical properties of irradiated graphite samples