Book Description

A knowledge of the effect of reactor irradiation on the properties of UO2 is relevant to the design and evaluation of UO2 fuel elements for the PRTR. Of particular interest is the effect of reactor irradiation on the thermal conductivity of sintered UO2 and the type, mechanism, and extent of radiation damage in sintered UO2. In the latter case the study of fractured surfaces of irradiated UO2 specimens is a method of determining the extent of radiation damage. It is the purpose of this report to propose an irradiation test of a number of capsules containing UO2 thermal conductivity and fractography specimens.