Development of test technique for thermal properties of nuclear fuels

A sound understanding of the thermal conductivity of nuclear materials is essential both successful prediction of fuel performance such as centerline temperature, temperature gradient of fuels and behaviors of fission gas release and to evaluation of heat transfer of fuel cladding and steam generator tube to heat exchanger media. Thus, in this study apparatuses and techniques for measuring thermal conductivity are surveved and set up, and thermal conductivity of nuclear materials is produced. The results will be applied to measuring thermal conductivity for developing nuclear materials of system components as well as fuels for advanced reactors. The data-base of thermal conductivity will be a basis for improving the domestic design code of fuels and for utilizing domestic nuclear materials. (Author)