Abstract
Yttrium hydride is an excellent solid neutron moderator material for high temperature nuclear reactor applications due to its high hydrogen density and exceptional hydride stability at high temperatures. Despite these attractive characteristics, the details of how hydrogen behaves within yttrium hydride while temperature gradients exist are still not well understood. The evolution of the hydrogen composition profile resulting from a temperature gradient requires knowledge of hydrogen's heat of transport, a critical parameter that has not yet been measured for this material. In this work, we perform hydride redistribution, hydrogen dissociation, and hydrogen leakage calculations while varying the Soret heat of transport of hydrogen in yttrium hydride to elucidate the sensitivity of hydride stability under temperature gradients to this parameter. This study analyzes hydride stability of a hypothetical uranium-yttrium hydride nuclear fuel design during operation of a high temperature liquid metal-cooled nuclear reactor. Assuming U-YHx could be fabricated in a physically stabilized manner, this fuel system can likely maintain hydride stability while operating at very high power densities and temperatures. We find that even though the hydrogen dissociation pressure in the gas gap does vary by several percent as the heat of transport temperature parameter is varied, the hydrogen content in the U-YHx fuel meat is relatively insensitive to this parameter over the course of a high burnup fuel cycle; this is due to yttrium hydride's excellent hydrogen retention under the high temperature conditions considered here. This suggests that hydride stability analyses are insensitive to the value of the Soret heat of transport in U-YHx under steady state liquid metal-cooled reactor conditions. However, the susceptibility to internal gas overpressurization-induced stress-rupture of the cladding during a high temperature transient is more sensitive to this parameter due to the non-linear dependence of hydrogen gas dissociation pressure vs. composition and temperature.
| Original language | English |
|---|---|
| Article number | 114030 |
| Journal | Nuclear Engineering and Design |
| Volume | 438 |
| Early online date | Apr 12 2025 |
| DOIs | |
| State | Published - Jul 2025 |
Keywords
- Heat of transport
- Nuclear fuel
- Soret effect
- Yttrium hydride
INL Publication Number
- INL/JOU-24-82208
- 190814
Fingerprint
Dive into the research topics of 'Sensitivity study of hydrogen Soret transport in yttrium Hydride-Based nuclear fuel'. Together they form a unique fingerprint.Cite this
- APA
- Author
- BIBTEX
- Harvard
- Standard
- RIS
- Vancouver