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Abstract: Thermophysical properties of a uranium-6 wt. % zirconium alloy were investigated at high temperatures to evaluate the performance of the alloy as a driver fuel for a liquid-metal cooled fast reactor. Of particular interest to the authors were the coefficient of thermal expansion, the specific heat, and the thermal conductivity of the alloy.

Reference: Journal of Nuclear Materials, 427 (2012) 1-11

DOI: 10.1016/j.jnucmat.2012.03.045