Nondestructive evaluation of nuclear-grade graphite

3Citations
Citations of this article
13Readers
Mendeley users who have this article in their library.
Get full text

Abstract

The material of choice for the core of the high-temperature gas-cooled reactors being developed by the U.S. Department of Energy's Next Generation Nuclear Plant Program is graphite. Graphite is a composite material whose properties are highly dependent on the base material and manufacturing methods. In addition to the material variations intrinsic to the manufacturing process, graphite will also undergo changes in material properties resulting from radiation damage and possible oxidation within the reactor. Idaho National Laboratory is presently evaluating the viability of conventional nondestructive evaluation techniques to characterize the material variations inherent to manufacturing and in-service degradation. Approaches of interest include x-ray radiography, eddy currents, and ultrasonics. © 2012 American Institute of Physics.

Cite

CITATION STYLE

APA

Kunerth, D. C., & McJunkin, T. R. (2012). Nondestructive evaluation of nuclear-grade graphite. In AIP Conference Proceedings (Vol. 1430, pp. 1609–1616). https://doi.org/10.1063/1.4716406

Register to see more suggestions

Mendeley helps you to discover research relevant for your work.

Already have an account?

Save time finding and organizing research with Mendeley

Sign up for free