High-Temperature Corrosion Testing of Uranium Silicide Surrogates

Authors

B. J. Jaques, Boise State UniversityFollow
G. Alanko, Boise State UniversityFollow
D. P. Butt, Boise State UniversityFollow

Document Type

Article

Publication Date

10-2016

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 CeSi_1.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 Ce_4.67 (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.

Comments

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Copyright Statement

Copyright 2016 by the American Nuclear Society, La Grange Park, Illinois.

Publication Information

Jaques, B. J.; Alanko, G.; and Butt, D. P.. (2016). "High-Temperature Corrosion Testing of Uranium Silicide Surrogates". Nuclear Technology, 196(1), 100-110. https://doi.org/10.13182/NT15-155