About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
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| Symposium
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Special Topics in Nuclear Materials: Reproducibility and Uncertainty; Hydrogen Effects; Space and Microreactor Systems
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| Presentation Title |
Insights From Post-Irradiation Examination of Yttrium Hydride at ORNL and INL |
| Author(s) |
Mahmut Nedim Cinbiz |
| On-Site Speaker (Planned) |
Mahmut Nedim Cinbiz |
| Abstract Scope |
Yttrium hydride is gaining attention as a solid-state moderator for microreactor and fission surface power systems due to its excellent hydrogen retention and structural integrity. Although considered in legacy nuclear programs, limited data exist on its irradiation performance. To address this gap, the U.S. Department of Energy has recently initiated neutron irradiation campaigns targeting yttrium hydride. These initiatives support a broad post-irradiation examination (PIE) effort that spans from visual inspections to advanced characterization techniques, including x-ray diffraction, electron microscopy, and thermal property evaluation.
This presentation will summarize the neutron irradiation experiments and PIE activities carried out at ORNL and INL. Key findings will be discussed with respect to hydrogen retention, dimensional and structural stability, and irradiation-induced degradation. The talk will also identify critical data gaps and present a forward-looking strategy to advance the qualification and deployment of yttrium hydride moderators in next-generation nuclear technologies.
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| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, High-Temperature Materials, Characterization |