Bond characterization of plasma sprayed zirconium on uranium alloy by microcantilever testing

K. J. Hollis; N. A. Mara; R. D. Field; T. A. Wynn; J. M. Crapps; P. O. Dickerson

doi:10.1007/s11666-012-9858-7

Bond characterization of plasma sprayed zirconium on uranium alloy by microcantilever testing

K. J. Hollis, N. A. Mara, R. D. Field, T. A. Wynn, J. M. Crapps, P. O. Dickerson

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7 Scopus citations

Abstract

The future production of low enriched uranium nuclear fuel for test reactors requires a well-adhered diffusion barrier coating of zirconium (Zr) on the uranium/molybdenum (U-Mo) alloy fuel. In this study, the interfacial bond between plasma sprayed Zr coatings and U-Mo fuel was characterized by microcantilever beam testing. Test results revealed the effect of specific flaws such as cracks and pores on the bonding of interfaces with a sampling area of approximately 20 μm². TEM examination showed the Zr/U-Mo interface to contain rows of very fine grains (5-30 nm) with the Zr in contact with UO₂. Bond characteristics of plasma sprayed samples were measured that are similar to those of roll bonded samples showing the potential for plasma sprayed Zr coatings to have high bond strength.

Original language	English (US)
Pages (from-to)	233-241
Number of pages	9
Journal	Journal of Thermal Spray Technology
Volume	22
Issue number	2-3
DOIs	https://doi.org/10.1007/s11666-012-9858-7
State	Published - Mar 2013
Externally published	Yes

Keywords

Zr-based alloy
adhesion testing
adhesive strength
cantilever beam method
finite element modeling
low pressure plasma spray (LPPS)
transmission electron microscopy (TEM)

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title = "Bond characterization of plasma sprayed zirconium on uranium alloy by microcantilever testing",

abstract = "The future production of low enriched uranium nuclear fuel for test reactors requires a well-adhered diffusion barrier coating of zirconium (Zr) on the uranium/molybdenum (U-Mo) alloy fuel. In this study, the interfacial bond between plasma sprayed Zr coatings and U-Mo fuel was characterized by microcantilever beam testing. Test results revealed the effect of specific flaws such as cracks and pores on the bonding of interfaces with a sampling area of approximately 20 μm2. TEM examination showed the Zr/U-Mo interface to contain rows of very fine grains (5-30 nm) with the Zr in contact with UO2. Bond characteristics of plasma sprayed samples were measured that are similar to those of roll bonded samples showing the potential for plasma sprayed Zr coatings to have high bond strength.",

keywords = "Zr-based alloy, adhesion testing, adhesive strength, cantilever beam method, finite element modeling, low pressure plasma spray (LPPS), transmission electron microscopy (TEM)",

author = "Hollis, {K. J.} and Mara, {N. A.} and Field, {R. D.} and Wynn, {T. A.} and Crapps, {J. M.} and Dickerson, {P. O.}",

year = "2013",

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doi = "10.1007/s11666-012-9858-7",

language = "English (US)",

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T1 - Bond characterization of plasma sprayed zirconium on uranium alloy by microcantilever testing

AU - Hollis, K. J.

AU - Mara, N. A.

AU - Field, R. D.

AU - Wynn, T. A.

AU - Crapps, J. M.

AU - Dickerson, P. O.

PY - 2013/3

Y1 - 2013/3

N2 - The future production of low enriched uranium nuclear fuel for test reactors requires a well-adhered diffusion barrier coating of zirconium (Zr) on the uranium/molybdenum (U-Mo) alloy fuel. In this study, the interfacial bond between plasma sprayed Zr coatings and U-Mo fuel was characterized by microcantilever beam testing. Test results revealed the effect of specific flaws such as cracks and pores on the bonding of interfaces with a sampling area of approximately 20 μm2. TEM examination showed the Zr/U-Mo interface to contain rows of very fine grains (5-30 nm) with the Zr in contact with UO2. Bond characteristics of plasma sprayed samples were measured that are similar to those of roll bonded samples showing the potential for plasma sprayed Zr coatings to have high bond strength.

AB - The future production of low enriched uranium nuclear fuel for test reactors requires a well-adhered diffusion barrier coating of zirconium (Zr) on the uranium/molybdenum (U-Mo) alloy fuel. In this study, the interfacial bond between plasma sprayed Zr coatings and U-Mo fuel was characterized by microcantilever beam testing. Test results revealed the effect of specific flaws such as cracks and pores on the bonding of interfaces with a sampling area of approximately 20 μm2. TEM examination showed the Zr/U-Mo interface to contain rows of very fine grains (5-30 nm) with the Zr in contact with UO2. Bond characteristics of plasma sprayed samples were measured that are similar to those of roll bonded samples showing the potential for plasma sprayed Zr coatings to have high bond strength.

KW - Zr-based alloy

KW - adhesion testing

KW - adhesive strength

KW - cantilever beam method

KW - finite element modeling

KW - low pressure plasma spray (LPPS)

KW - transmission electron microscopy (TEM)

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ER -

Bond characterization of plasma sprayed zirconium on uranium alloy by microcantilever testing

Abstract

Keywords

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