The unique combination of physical properties inherent to graphite makes it an attractive material for use as a moderator in high-temperature nuclear reactors (HTR’s). High-temperature physical properties of three nuclear grade graphites manufactured by GrafTech International Holdings Inc. (GrafTech) (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.
High-Temperature Properties of Nuclear Graphite
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Albers, TL, Batty, L, & Kaschak, DM. "High-Temperature Properties of Nuclear Graphite." Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology. Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2. Washington, DC, USA. September 28–October 1, 2008. pp. 107-108. ASME. https://doi.org/10.1115/HTR2008-58284
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