High-Temperature Corrosion Testing of Uranium Silicide Surrogates. (1st October 2016)

• Record Type: Journal Article
• Authors: Urso, K.; Sridharan, K.; Jaques, B. J.; Alanko, G.; Butt, D. P.; Meyer, M.; Xu, P.; Tyburska-Päschel, B.
• Is Part Of: Nuclear technology. Volume 196:Number 1(2016)
• Page Start: 100
• Page End: 110
• Publication Date: 2016-10-01
• Subjects: Nuclear engineering -- Periodicals; Nuclear engineering; Nuclear Physics; Periodicals; Periodicals; 621.48
• DOI: 10.13182/NT15-155
• Languages: English
• ISSNs: 1943-7471

Abstract

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 Ce3 Si2, 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 )3 O 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 Ce3 Si2 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.