Low temperature neutron irradiation stability of Zirconium hydride and Yttrium hydride
Source abstract
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.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear materials and radiation effects · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (36)
Show source-provided references
1. Economics and finance of small modular reactors: a systematic review and research agenda10.1016/j.rser.2019.109519 ↗
2. Superheated water-cooled small modular underwater reactor concept10.1016/j.net.2016.06.003 ↗
3. Review of nuclear thermal propulsion systems10.1016/j.paerosci.2015.09.001 ↗
4. Design feasibility and failure mode analysis for a HALEU-based Kilopower-class space power reactor10.1016/j.anucene.2023.109940 ↗
5. Hydrides as neutron moderator and reflector materials10.1016/0029-5493(70)90159-7 ↗
6. Considerations for Hydride Moderator Readiness in Microreactors10.1080/00295450.2022.2121583 ↗
7. Phase stability and microstructure of neutron-irradiated substoichiometric yttrium dihydrides10.1016/j.jnucmat.2024.155374 ↗
8. Challenges in developing materials for microreactors: A case-study of yttrium dihydride in extreme conditions10.1016/j.actamat.2024.120333 ↗
9. Fabrication of yttrium hydride for high-temperature moderator application10.1016/j.jnucmat.2020.152335 ↗
10. Heterogeneous microstructure of yttrium hydride and its relation to mechanical properties10.1016/j.jeurceramsoc.2023.01.015 ↗
11. Development and potential of composite moderators for elevated temperature nuclear applications10.1080/21870764.2021.1993592 ↗
12. Thermomechanical properties and microstructures of yttrium hydride10.1016/j.jallcom.2021.158992 ↗
13. Thermophysical properties of high-density, sintered monoliths of yttrium dihydride in the range 373–773 K10.1016/j.jallcom.2020.156303 ↗
14. Hydrogen desorption kinetics from zirconium hydride and zirconium metal in vacuum10.1016/j.jnucmat.2014.01.028 ↗
15. Comparison of irradiation hardening and microstructure evolution in ion-irradiated delta and epsilon hydrides10.1016/j.jnucmat.2013.03.013 ↗
16. Irradiation hardening and microstructure evolution of ion-irradiated Zr-hydride10.1016/j.jnucmat.2011.06.041 ↗
17. Solov'ev, Nature and thermal stability of radiation-induced defects in zirconium hydride10.1007/BF01134756 ↗
18. Thermophysical properties and reversible phase transitions in yttrium hydride10.1016/j.jnucmat.2020.152569 ↗
19. X. Hu, C. Silva, K. Terrani, Development of yttrium hydride moderator for the transformational challenge reactor (DOI:10.13182/T122-32423), United States, 2020.10.13182/T122-32423 ↗
20. X. Hu, P. Mouche, D. Schappel, D.J. Sprouster, Technology enabling zero-EPZ micro modular reactors: fabrication of zirconium hydride with controlled hydrogen loading (DOI:10.2172/1879976), United States, 2020.10.2172/1879976 ↗
21. X. Hu, H. Wang, K. Linton, A. Le Coq, K.A. Terrani, Handbook on the material properties of yttrium hydride for high temperature moderator applications (DOI:10.2172/1808171), United States, 2021.10.2172/1808171 ↗
22. Thermal and mechanical properties of zirconium hydride10.1016/S0925-8388(99)00389-8 ↗
23. Thermal properties of zirconium hydride10.1016/S0022-3115(01)00457-3 ↗
24. Hydrogen effects on thermal diffusivity and electrical resistivity of zircaloy cladding10.1016/j.jnucmat.2022.154213 ↗
25. Thermal properties of yttrium hydride10.1016/j.jnucmat.2005.04.058 ↗
26. Thermal conductivity degradation of ceramic materials due to low temperature, low dose neutron irradiation10.1016/j.jnucmat.2004.11.009 ↗
27. Handbook of SiC properties for fuel performance modeling10.1016/j.jnucmat.2007.05.016 ↗
28. Reprint of: Microstructural evolution of neutron irradiated 3C-SiC10.1016/j.scriptamat.2017.09.034 ↗
29. Atomic and microstructural origins of stored energy release in neutron-irradiated silicon carbide
30. Advanced synchrotron characterization techniques for fusion materials science10.1016/j.jnucmat.2020.152574 ↗
31. Microstructural parameters from X-ray diffraction peak broadening10.1016/j.scriptamat.2004.05.007 ↗
32. Long-term thermal aging effects in ferritic-martensitic steel HT910.1016/j.matchar.2024.114418 ↗
33. The kinetics of hydrogen desorption from and adsorption on zirconium hydride10.1016/j.jnucmat.2009.12.008 ↗
34. Dimensional isotropy of 6H and 3C SiC under neutron irradiation10.1016/j.jnucmat.2016.01.010 ↗
35. 3.01 - Radiation effects in zirconium alloys☆
36. A review of microstructure evolution in zirconium alloys during irradiation10.1016/0022-3115(88)90093-1 ↗