Low temperature neutron irradiation stability of Zirconium hydride and Yttrium hydride

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
D.J. Sprouster , M. Ouyang , N. Cetiner , P. Negi , A. Sharma , D. Bhardwaj , Y. Huang , X. Hu , K. Shirvan , L.L. Snead
{"title":"Low temperature neutron irradiation stability of Zirconium hydride and Yttrium hydride","authors":"D.J. Sprouster ,&nbsp;M. Ouyang ,&nbsp;N. Cetiner ,&nbsp;P. Negi ,&nbsp;A. Sharma ,&nbsp;D. Bhardwaj ,&nbsp;Y. Huang ,&nbsp;X. Hu ,&nbsp;K. Shirvan ,&nbsp;L.L. Snead","doi":"10.1016/j.jnucmat.2025.155770","DOIUrl":null,"url":null,"abstract":"<div><div>Metal hydrides, including ZrH<sub>x</sub> and YH<sub>x</sub>, 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<sub>2-x</sub> and YH<sub>2-x</sub> 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<sub>2-x</sub> specimens. Interestingly, minimal-to-nil change in the metallic Y fraction was quantifiable in the YH<sub>2-x</sub> specimens and modest changes in the thermal diffusivity occur for the temperature and dose studied. The loss of hydrogen in the ZrH<sub>2-x</sub> 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.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"609 ","pages":"Article 155770"},"PeriodicalIF":2.8000,"publicationDate":"2025-03-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311525001655","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
引用次数: 0

Abstract

Metal hydrides, including ZrHx and YHx, 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 ZrH2-x and YH2-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 ZrH2-x specimens. Interestingly, minimal-to-nil change in the metallic Y fraction was quantifiable in the YH2-x specimens and modest changes in the thermal diffusivity occur for the temperature and dose studied. The loss of hydrogen in the ZrH2-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.
氢化锆和氢化钇的低温中子辐照稳定性
金属氢化物,包括ZrHx和YHx,对先进的热裂变反应堆特别感兴趣,因为它们具有高中子慢化能力,可以在相对较高的温度下使用。它们作为核心部件有直接的应用,包括作为核燃料中的减速添加剂,以及作为中子反射器或减速剂。了解其热和辐照引起的性质变化对其工程应用具有重要意义。具体来说,不断变化的金属氢比是至关重要的。本文讨论了中子辐照ZrH2-x和YH2-x样品的辐照后检验。我们采用多种表征技术,包括x射线衍射,扫描电子显微镜和热物理(热扩散率)来确定辐照诱导的宏观和微观结构演变作为辐照温度的函数。我们很容易量化热扩散率的退化,晶格参数的变化,以及表明ZrH2-x样品中氢释放的金属Zr的增加。有趣的是,在YH2-x样品中,金属Y组分的变化可以量化为极小至零,并且在所研究的温度和剂量下,热扩散率也发生了适度的变化。ZrH2-x样品中氢的损失与核内中子辐照产生的高电离辐射组分(γ、超热通量和快中子通量)对氢的明显辐照加速解吸有关。从这两种金属氢化物的微观结构分析中,最明显的特征是由于二维缺陷的数量和组成的变化,x射线衍射峰展宽随温度的变化而减小。这些结果和趋势提高了对中子-固体相互作用的基本理解,以及这类重要核心材料的发展。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 求助全文
来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术官方微信