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Tensile Test Techniques for a Nuclear Fuel Cladding in a Hot Cell

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Abstract:

Modified transverse and longitudinal tensile test techniques are proposed to evaluate the mechanical properties of nuclear fuel cladding materials under a hoop and axial loading condition in a hot cell. The ring specimen with a gage length of 3 mm and a width of 2 mm is designed to limit a deformation within the gage section and to maximize the uniformity of a strain distribution at the gage section. The loading grip is designed such that a constant curvature of a specimen is maintained during a deformation. The contact surface is lubricated with a graphite lubricant (Model P-37, Molykote Co.). A dogbone specimen with a gage length of 25 mm and a gage width of 2.5 mm has been designed for the longitudinal tensile test. The grip is designed such that any slippage at the gripping section does not occur during a test. Through the tensile test of an unirradiated Zircaloy-4 cladding tube and an SUS 316 steel seamless tube, it is found that the proposed techniques are appropriate for an estimation of the tensile properties of an irradiated nuclear fuel cladding in a hot cell.

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Periodical:

Key Engineering Materials (Volumes 345-346)

Pages:

1561-1564

DOI:

https://doi.org/10.4028/www.scientific.net/KEM.345-346.1561

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Online since:

August 2007

Authors:

Do Sik Kim, Sang Bok Ahn, Wan Ho Oh, Byung Ok Yoo, Yong Sun Choo, Kwon Pyo Hong, Sun Kee Kim

Keywords:

Hot Cell, Irradiated Fuel Cladding, Tensile Test, Transverse Tensile Test

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© 2007 Trans Tech Publications Ltd. All Rights Reserved

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