Investigation of High-Temperature Compatibility of Select Oxides with Yttrium Hydride for Micro and Space Reactor Applications

Yttrium hydride is a promising material for a high-temperature neutron moderator in advanced micro and space reactors due to its high hydrogen density and relative thermal stability compared to other metal hydrides. However, yttrium hydride desorbs hydrogen rapidly at temperatures above 800°C, which is below the operational temperature range of some reactor designs. A hydrogen barrier coating of oxide on the hydride surface may inhibit hydrogen loss at 800°C and beyond, but the high-temperature compatibility between yttrium hydride and many oxides is currently unknown. The high-temperature compatibility of Al<sub>2</sub>O<sub>3</sub>, MgO, and Y<sub>2</sub>O<sub>3</sub> with YH<sub>1.92</sub> was examined by subjecting mixed oxide–hydride pellets to a 1200°C heat treatment then using a combination of diffractometry, microscopy, and spectroscopy to determine changes in the pellet composition as a result. Yttrium scavenged oxygen from both Al<sub>2</sub>O<sub>3</sub> and MgO to form Y<sub>2</sub>O<sub>3</sub>, resulting in significant loss of YH<sub>1.92</sub>. Yttrium reacted with reduced aluminum to form YAl<sub>2</sub> and several other compounds. Reduced magnesium volatilized above 1091°C and vacated the pellet. Only Y<sub>2</sub>O<sub>3</sub> did not appreciably react with YH<sub>1.92</sub>. Of the three oxides tested, only Y<sub>2</sub>O<sub>3</sub> was compatible with YH<sub>1.92</sub> at 1200°C based on the experimental criteria.

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Journal
Nuclear Technology
Published
2025-04-09
DOI
https://doi.org/10.1080/00295450.2025.2462468
Primary Topic
Nuclear Materials and Properties
Type
article
Field-Weighted Citation Impact
0.00

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article

Investigation of High-Temperature Compatibility of Select Oxides with Yttrium Hydride for Micro and Space Reactor Applications

Holly Trellue, Stephen S. Raiman, Caitlin Kohnert, Darrell Cheu et al.
Nuclear Technology
Nuclear Materials and Properties
article

Investigation of High-Temperature Compatibility of Select Oxides with Yttrium Hydride for Micro and Space Reactor Applications

Holly Trellue, Stephen S. Raiman, Caitlin Kohnert, Darrell Cheu, Erik Luther, Ryan Wilkerson, Michael A. Torrez, Eric Tegtmeier, Aditya Shivprasad, Mary Katherine O’Brien, R. H. Bohanon
article en

Abstract

Yttrium hydride is a promising material for a high-temperature neutron moderator in advanced micro and space reactors due to its high hydrogen density and relative thermal stability compared to other metal hydrides. However, yttrium hydride desorbs hydrogen rapidly at temperatures above 800°C, which is below the operational temperature range of some reactor designs. A hydrogen barrier coating of oxide on the hydride surface may inhibit hydrogen loss at 800°C and beyond, but the high-temperature compatibility between yttrium hydride and many oxides is currently unknown. The high-temperature compatibility of Al<sub>2</sub>O<sub>3</sub>, MgO, and Y<sub>2</sub>O<sub>3</sub> with YH<sub>1.92</sub> was examined by subjecting mixed oxide–hydride pellets to a 1200°C heat treatment then using a combination of diffractometry, microscopy, and spectroscopy to determine changes in the pellet composition as a result. Yttrium scavenged oxygen from both Al<sub>2</sub>O<sub>3</sub> and MgO to form Y<sub>2</sub>O<sub>3</sub>, resulting in significant loss of YH<sub>1.92</sub>. Yttrium reacted with reduced aluminum to form YAl<sub>2</sub> and several other compounds. Reduced magnesium volatilized above 1091°C and vacated the pellet. Only Y<sub>2</sub>O<sub>3</sub> did not appreciably react with YH<sub>1.92</sub>. Of the three oxides tested, only Y<sub>2</sub>O<sub>3</sub> was compatible with YH<sub>1.92</sub> at 1200°C based on the experimental criteria.

Nuclear TechnologyVol. 211(sup2)
Los Alamos National Laboratory (US), University of Michigan (US), Texas A&M University (US)
Laboratory Directed Research and Development
Openalex Percentile: Top 95%
Nuclear Materials and Properties
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