About this Abstract |
Meeting |
2024 TMS Annual Meeting & Exhibition
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Symposium
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Ceramics and Ceramic-based Composites for Nuclear Fission Applications
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Presentation Title |
Steam Corrosion of Cr- and Zr-containing Uranium Nitride Fuels: Mechanistic Insights from In Situ Neutron Diffraction |
Author(s) |
Jennifer Stansby, Yulia Mishchenko, Sobhan Patnaik, Vanessa Peterson, Chris Baldwin, Patrick Burr, Denise Adorno-Lopes, Edward Obbard |
On-Site Speaker (Planned) |
Jennifer Stansby |
Abstract Scope |
Analysing when and how corrosion occurs in realistic conditions is challenging because corrosion products may present temporarily, and often the final product of corrosion is a fragmented mixture of oxides. Using UN-20%CrN and UN-20%ZrN (vol.%) as case studies, the application of in situ neutron diffraction methods to evaluate the corrosion behaviour under conditions relevant for fuel performance problems is demonstrated.
Previously, it was unclear why UN-20%ZrN was superior in its steam oxidation resistance to UN-20%CrN. Now, by observing the rates of mass loss from corrosion of the U2CrN3 and the UN phases in UN-20%CrN pellets, it is shown that the onset of corrosion in this duplex microstructure is led by the UN, which experiences enhanced corrosion rates in the presence of U2CrN3. The results point towards modified UN solid solutions as a promising pathway for the design of advanced nuclear fuel materials with enhance corrosion resistance in steam. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Characterization, Other |