Low temperature neutron irradiation stability of Zirconium hydride and Yttrium hydride

Metal hydrides, including ZrH x and YH x , are of particular interest for advanced thermal fission reactors as they have high neutron moderating power and can be used at relatively high temperatures. They have direct applications as core components including as a moderating addition in nuclear fuel, and as neutron reflectors or moderators. Understanding their thermal and irradiation-induced property changes are important to their engineering application. Specifically, evolving metal hydrogen ratios are of critical importance. In this work we discuss the post-irradiation examination of neutron irradiated ZrH 2-x and YH 2-x specimens. We employ multiple characterization techniques including X-ray diffraction, scanning electron microscopy and thermophysical (thermal diffusivity) to determine the irradiation-induced macro- and microstructural evolution as a function of irradiation temperature. We readily quantify degradations in the thermal diffusivity, changes in lattice parameters, and an increase in metallic Zr indicative of hydrogen release in ZrH 2-x specimens. Interestingly, minimal-to-nil change in the metallic Y fraction was quantifiable in the YH 2-x specimens and modest changes in the thermal diffusivity occur for the temperature and dose studied. The loss of hydrogen in the ZrH 2-x samples is related to an apparent irradiation-accelerated desorption of hydrogen by the high ionizing radiation components (gamma, epithermal and fast neutron fluxes) from the in-core neutron irradiation. The most apparent feature from the microstructural analysis for both metal hydrides was a temperature-dependent decrease in the X-ray diffraction peak broadening, attributable to changes in the number and makeup of the two-dimensional defects. These results and trends improve both the fundamental understanding of neutron-solid interactions, and the development of such an important class of core materials.

Authors

Institutions

Publication Details

Journal
Journal of Nuclear Materials
Published
2025-03-18
DOI
https://doi.org/10.1016/j.jnucmat.2025.155770
Citations
5
Primary Topic
Nuclear Materials and Properties
Type
article
Field-Weighted Citation Impact
2.59
Controls
|||
ALL TIME
JAN
FEB
MAR
APR
MAY
JUN
JUL
AUG
SEP
OCT
article

Low temperature neutron irradiation stability of Zirconium hydride and Yttrium hydride

Minggao Ouyang, Poonam Negi, David Sprouster, Koroush Shirvan et al.
5 citations
Journal of Nuclear Materials
Nuclear Materials and Properties
2.59
article

Low temperature neutron irradiation stability of Zirconium hydride and Yttrium hydride

Minggao Ouyang, Poonam Negi, David Sprouster, Koroush Shirvan, Devanshi Bhardwaj, Xunxiang Hu, Y. Huang, Nesrin Cetiner, L.L. Snead, AK Sharma
article en
5 citations

Abstract

Metal hydrides, including ZrH x and YH x , are of particular interest for advanced thermal fission reactors as they have high neutron moderating power and can be used at relatively high temperatures. They have direct applications as core components including as a moderating addition in nuclear fuel, and as neutron reflectors or moderators. Understanding their thermal and irradiation-induced property changes are important to their engineering application. Specifically, evolving metal hydrogen ratios are of critical importance. In this work we discuss the post-irradiation examination of neutron irradiated ZrH 2-x and YH 2-x specimens. We employ multiple characterization techniques including X-ray diffraction, scanning electron microscopy and thermophysical (thermal diffusivity) to determine the irradiation-induced macro- and microstructural evolution as a function of irradiation temperature. We readily quantify degradations in the thermal diffusivity, changes in lattice parameters, and an increase in metallic Zr indicative of hydrogen release in ZrH 2-x specimens. Interestingly, minimal-to-nil change in the metallic Y fraction was quantifiable in the YH 2-x specimens and modest changes in the thermal diffusivity occur for the temperature and dose studied. The loss of hydrogen in the ZrH 2-x samples is related to an apparent irradiation-accelerated desorption of hydrogen by the high ionizing radiation components (gamma, epithermal and fast neutron fluxes) from the in-core neutron irradiation. The most apparent feature from the microstructural analysis for both metal hydrides was a temperature-dependent decrease in the X-ray diffraction peak broadening, attributable to changes in the number and makeup of the two-dimensional defects. These results and trends improve both the fundamental understanding of neutron-solid interactions, and the development of such an important class of core materials.

Journal of Nuclear MaterialsVol. 609
Oak Ridge National Laboratory (US), Stony Brook School (US), Stony Brook University (US), Massachusetts Institute of Technology (US)
Openalex Percentile: Top 11%
Nuclear Materials and Properties
2.59
AI Navigator

Ask Laika to Summarize, Analyze, and Connect papers live on the map.

Summarize Papers & Methodologies

Extract key findings, datasets, and comparative methods across publications.

Benchmark Rankings & Visual Analytics

Rank top research institutions, authors, funders, topics, and journals by Field-Weighted Citation Impact (FWCI) and paper volume with instant charts.

Connect Distant Disciplines

Bridge topological clusters on the map to find hidden collaborative intersections.