Low temperature neutron irradiation stability of Zirconium hydride and Yttrium hydride
David Sprouster, M. Ouyang, Nesrin Cetiner, Poonam Negi, AK Sharma, Devanshi Bhardwaj, Y. Huang, Xunxiang Hu, Koroush Shirvan, L.L. Snead
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.