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Technical Briefs

High-Temperature Properties of Nuclear Graphite

[+] Author and Article Information
Tracy L. Albers

 GrafTech International Holdings Inc., 12900 Snow Road, Parma, OH 44130

Controlled irradiation experiments are currently being performed at NRG Petten as part of the RAPHAEL program.

J. Eng. Gas Turbines Power 131(6), 064501 (Jul 15, 2009) (2 pages) doi:10.1115/1.3093995 History: Received October 21, 2008; Revised October 27, 2008; Published July 15, 2009

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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Copyright © 2009 by American Society of Mechanical Engineers
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References

Figures

Grahic Jump Location
Figure 1

High-temperature thermal conductivity

Grahic Jump Location
Figure 2

High-temperature with-grain CTE. Isotropy ratio is ag/wg value for RT −2000°C.

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