High-Temperature Corrosion Testing of Uranium Silicide Surrogates

K. Urso; K. Sridharan; B. J. Jaques; G. Alanko; D. P. Butt; M. Meyer; P. Xu; B. Tyburska-Püschel

doi:10.13182/NT15-155

High-Temperature Corrosion Testing of Uranium Silicide Surrogates

K. Urso, K. Sridharan, B. J. Jaques, G. Alanko, D. P. Butt, M. Meyer, P. Xu, B. Tyburska-Püschel

Micron School of Materials Science and Engineering

Research output: Contribution to journal › Article › peer-review

5 Scopus citations

Abstract

The corrosion resistance of cerium silicide, a surrogate of uranium silicide, is investigated to gain insight into the reaction of uranium silicide with water. As-received and proton-irradiated Ce₃Si₂, CeSi₂, and CeSi1.x monolithic pellets are subjected to corrosion tests in water at 300°C and 9 MPa for up to 48 h. Results show that an oxide layer composed of Ce₄.₆₇ (SiO₄)₃O forms on the surface of all samples, and it grows thicker with extended exposure times. Irradiated samples corrode to a greater extent than their unirradiated counterparts, which is mainly a result of the existing post-irradiation cerium oxide and the presence of ion-induced defects. Most of the Ce₃Si₂ samples crack (as-received) or fracture (ion-irradiated) during testing, which is due to the brittleness of the samples and oxide erosion/spallation that occur during testing.

Original language	American English
Pages (from-to)	100-110
Number of pages	11
Journal	Nuclear Technology
Volume	196
Issue number	1
DOIs	https://doi.org/10.13182/NT15-155
State	Published - Oct 2016

Keywords

cerium silicide
surrogate
water corrosion

EGS Disciplines

Materials Science and Engineering

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High-Temperature Corrosion Testing of Uranium Silicide SurrogatesFinal published version, 1 MBLicense: Other

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title = "High-Temperature Corrosion Testing of Uranium Silicide Surrogates",

abstract = "The corrosion resistance of cerium silicide, a surrogate of uranium silicide, is investigated to gain insight into the reaction of uranium silicide with water. As-received and proton-irradiated Ce3Si2, CeSi2, and CeSi1.x monolithic pellets are subjected to corrosion tests in water at 300°C and 9 MPa for up to 48 h. Results show that an oxide layer composed of Ce4.67 (SiO4)3O forms on the surface of all samples, and it grows thicker with extended exposure times. Irradiated samples corrode to a greater extent than their unirradiated counterparts, which is mainly a result of the existing post-irradiation cerium oxide and the presence of ion-induced defects. Most of the Ce3Si2 samples crack (as-received) or fracture (ion-irradiated) during testing, which is due to the brittleness of the samples and oxide erosion/spallation that occur during testing.",

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AU - Urso, K.

AU - Sridharan, K.

AU - Jaques, B. J.

AU - Alanko, G.

AU - Butt, D. P.

AU - Meyer, M.

AU - Xu, P.

AU - Tyburska-Püschel, B.

PY - 2016/10

Y1 - 2016/10

N2 - The corrosion resistance of cerium silicide, a surrogate of uranium silicide, is investigated to gain insight into the reaction of uranium silicide with water. As-received and proton-irradiated Ce3Si2, CeSi2, and CeSi1.x monolithic pellets are subjected to corrosion tests in water at 300°C and 9 MPa for up to 48 h. Results show that an oxide layer composed of Ce4.67 (SiO4)3O forms on the surface of all samples, and it grows thicker with extended exposure times. Irradiated samples corrode to a greater extent than their unirradiated counterparts, which is mainly a result of the existing post-irradiation cerium oxide and the presence of ion-induced defects. Most of the Ce3Si2 samples crack (as-received) or fracture (ion-irradiated) during testing, which is due to the brittleness of the samples and oxide erosion/spallation that occur during testing.

AB - The corrosion resistance of cerium silicide, a surrogate of uranium silicide, is investigated to gain insight into the reaction of uranium silicide with water. As-received and proton-irradiated Ce3Si2, CeSi2, and CeSi1.x monolithic pellets are subjected to corrosion tests in water at 300°C and 9 MPa for up to 48 h. Results show that an oxide layer composed of Ce4.67 (SiO4)3O forms on the surface of all samples, and it grows thicker with extended exposure times. Irradiated samples corrode to a greater extent than their unirradiated counterparts, which is mainly a result of the existing post-irradiation cerium oxide and the presence of ion-induced defects. Most of the Ce3Si2 samples crack (as-received) or fracture (ion-irradiated) during testing, which is due to the brittleness of the samples and oxide erosion/spallation that occur during testing.

KW - cerium silicide

KW - surrogate

KW - water corrosion

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UR - https://scholarworks.boisestate.edu/mse_facpubs/285

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DO - 10.13182/NT15-155

M3 - Article

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EP - 110

JO - Nuclear Technology

JF - Nuclear Technology

IS - 1

ER -

High-Temperature Corrosion Testing of Uranium Silicide Surrogates

Abstract

Keywords

EGS Disciplines

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