The unique combination of physical properties inherent to graphite makes it an attractive material for use as a moderator in high-temperature nuclear reactors. High-temperature physical properties of three nuclear-grade graphites manufactured by GrafTech International Holdings Inc. (GrafTech, Parma, OH), PCEA™, PCIB-SFG™, and PPEA™, have been determined experimentally and are presented here. Tensile strength, Young’s modulus, thermal conductivity, specific resistance, and coefficient of thermal expansion (CTE) data are collected at temperatures from 25°C to as high as 2000°C, and are found to be consistent with classical graphite behavior.

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