Nondestructive evaluation of the oxidation and strength of the Fort Saint Vrain HTGR support block

Tingey, G.L.; Posakony, Gerald J.; Morgan, W.C.; Prince, J.M.; Hill, Roger W.; Lessor, D.L.

doi:10.2172/5425001

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2012

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“…Although graphite has been used in nuclear reactors for over 60 years, only a limited amount of work has been performed to develop NDE technologies for inspecting graphite [2][3][4]. There are few ASTM/ASME standards or accepted measurement techniques specifically directed towards graphite.…”

Section: Introductionmentioning

confidence: 99%

Nondestructive evaluation of nuclear-grade graphite

Kunerth¹,

McJunkin²

2012

AIP Conference Proceedings

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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.

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Section: Introductionmentioning

confidence: 99%