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Meeting Materials Science & Technology 2020
Symposium Ceramics in the Nuclear Fuel Cycle
Presentation Title Radiolytic Damage and Hydrogen Generation at Carbide – Water Interfaces
Author(s) Simon M. Pimblott, Jay A LaVerne
On-Site Speaker (Planned) Simon M. Pimblott
Abstract Scope Carbides have great potential for application in the nuclear industry; however, various properties require detailed understanding for the materials to be properly utilized in situations where they will be exposed to extreme temperatures and mixed radiation fields. The behavior of SiC and ZrC as well as water slurries have been systematically studied using gamma and alpha radiation. Damage to the carbides was determined using analytical techniques including TGA, ICP-OES and SEM-EDS. Gamma irradiation of ZrC in air results in a reduction in Zr:C ratio with SEM examination showing oxidation of the surface. SiC is relatively stable under gamma irradiation except for some conversion of beta to the alpha phase: alpha radiolysis leads to the formation of SiO2. Aqueous slurry irradiations yield a large increase in the radiolytic yield of hydrogen compared to water, an effect that could have significant deleterious consequences if the material is deployed in nuclear energy environs.
Proceedings Inclusion? Planned: At-meeting proceedings


A First-principles Database Approach to Predicting Trans-Uranic Waste Forms
Evaluation of the Corrosion of High Purity CVD SiC in Light Water Reactor Environments
First-principles Study on the Trapping and Recombination of Tritium in Lithium Vacancy of the γ-LiAlO2 (100) Surface
Multi-scale Cs Sorbents Easily Transformable into Waste Confinement Matrices
Nb and Ti Alloying Effects on the Phase and Oxidation of U3Si2
Radiolytic Damage and Hydrogen Generation at Carbide – Water Interfaces
Thermophysical Properties of Sintered Yttrium Dihydride

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