Nondestructive evaluation of nuclear-grade graphite

Journal Article · Thu May 17 00:00:00 EDT 2012 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.4716406· OSTI ID:22004024

Kunerth, D C; McJunkin, T R ^[1]

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1. Idaho National Laboratory, P.O. Box 1625, MS 2209, Idaho Falls, ID 83415-2209 (United States)

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.

• OSTI ID: 22004024
• Journal Information: AIP Conference Proceedings, Vol. 1430, Issue 1; Conference: 38. annual review of progress in quantitative nondestructive evaluation, Burlington, VT (United States), 17-22 Jul 2011; Other Information: (c) 2012 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
22 GENERAL STUDIES OF NUCLEAR REACTORS
COMPOSITE MATERIALS
EDDY CURRENT TESTING
FISSION
GRAPHITE
HTGR TYPE REACTORS
NONDESTRUCTIVE ANALYSIS
OXIDATION
RADIATION EFFECTS
REACTOR CORES
REACTOR MATERIALS
TOMOGRAPHY
ULTRASONIC TESTING
VARIATIONS
X-RAY RADIOGRAPHY