High-temperature structure, elasticity, and thermal expansion of ε-ZrH1.8

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-10-05 DOI:10.1016/j.jnucmat.2024.155437
James R. Torres , Christopher A. Mizzi , Daniel A. Rehn , Tyler Smith , Scarlett Widgeon Paisner , Adrien J. Terricabras , Darren M. Parkison , Sven C. Vogel , Caitlin A. Kohnert , Mathew L. Hayne , Thomas J. Nizolek , M.A. Torrez , Tannor T.J. Munroe , Boris Maiorov , Tarik A. Saleh , Aditya P. Shivprasad
{"title":"High-temperature structure, elasticity, and thermal expansion of ε-ZrH1.8","authors":"James R. Torres ,&nbsp;Christopher A. Mizzi ,&nbsp;Daniel A. Rehn ,&nbsp;Tyler Smith ,&nbsp;Scarlett Widgeon Paisner ,&nbsp;Adrien J. Terricabras ,&nbsp;Darren M. Parkison ,&nbsp;Sven C. Vogel ,&nbsp;Caitlin A. Kohnert ,&nbsp;Mathew L. Hayne ,&nbsp;Thomas J. Nizolek ,&nbsp;M.A. Torrez ,&nbsp;Tannor T.J. Munroe ,&nbsp;Boris Maiorov ,&nbsp;Tarik A. Saleh ,&nbsp;Aditya P. Shivprasad","doi":"10.1016/j.jnucmat.2024.155437","DOIUrl":null,"url":null,"abstract":"<div><div>Zirconium hydride is a promising candidate material for nuclear microreactor applications as a solid-state moderator component, owing to its favorable neutronics properties and good thermal stability over other metal hydrides. In the present work, the crystal structure, thermal expansion, and elastic properties of the hydrogen-rich ε phase hydride were measured at elevated temperatures in the range 300–900 K. Samples were prepared by direct hydriding Zircaloy-4 metal – a nuclear-grade zirconium alloy. Room-temperature lattice parameters agree well with those reported from literature for unalloyed zirconium hydride and fall within an observed quadratic H-content dependence. The coefficients of thermal expansion, determined from lattice expansion and dilatometry, agree well within our work but were about 30 % lower than those reported by others for unalloyed hydrides. Density functional theory-based molecular dynamics simulations were used to compare with thermal expansion and elasticity measurements. Results showed lattice parameter temperature dependence and slope of thermal expansion align with those from measurements. Based on diffraction scans at select temperatures, ε phase remained stable in air up to at least 770 K. Likewise, dilatometry showed smooth thermal expansion up to the thermal decomposition temperature around 950 K. The precise decomposition temperature was not determined via diffraction due to sparse scanning. The complete elastic property measurements were gathered for ε-phase Ziracloy-4 hydride for the first time. Young's modulus was lower compared to the metal and δ hydride phases. High-temperature elasticity measurements were limited to &lt;350 K due to acoustic dissipation effects.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"603 ","pages":"Article 155437"},"PeriodicalIF":2.8000,"publicationDate":"2024-10-05","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/S0022311524005373","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

Zirconium hydride is a promising candidate material for nuclear microreactor applications as a solid-state moderator component, owing to its favorable neutronics properties and good thermal stability over other metal hydrides. In the present work, the crystal structure, thermal expansion, and elastic properties of the hydrogen-rich ε phase hydride were measured at elevated temperatures in the range 300–900 K. Samples were prepared by direct hydriding Zircaloy-4 metal – a nuclear-grade zirconium alloy. Room-temperature lattice parameters agree well with those reported from literature for unalloyed zirconium hydride and fall within an observed quadratic H-content dependence. The coefficients of thermal expansion, determined from lattice expansion and dilatometry, agree well within our work but were about 30 % lower than those reported by others for unalloyed hydrides. Density functional theory-based molecular dynamics simulations were used to compare with thermal expansion and elasticity measurements. Results showed lattice parameter temperature dependence and slope of thermal expansion align with those from measurements. Based on diffraction scans at select temperatures, ε phase remained stable in air up to at least 770 K. Likewise, dilatometry showed smooth thermal expansion up to the thermal decomposition temperature around 950 K. The precise decomposition temperature was not determined via diffraction due to sparse scanning. The complete elastic property measurements were gathered for ε-phase Ziracloy-4 hydride for the first time. Young's modulus was lower compared to the metal and δ hydride phases. High-temperature elasticity measurements were limited to <350 K due to acoustic dissipation effects.
查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
ε-ZrH1.8的高温结构、弹性和热膨胀
与其他金属氢化物相比,氢化锆具有良好的中子特性和热稳定性,是一种很有希望作为固态慢化剂成分应用于核微堆的候选材料。本研究测量了富氢ε相氢化物在 300-900 K 高温范围内的晶体结构、热膨胀和弹性特性。室温下的晶格参数与文献中报道的非合金氢化锆的晶格参数非常吻合,并且属于观察到的二次氢含量依赖关系。根据晶格膨胀和膨胀率测定的热膨胀系数与我们的研究结果十分吻合,但比其他人报告的非合金氢化物的热膨胀系数低约 30%。基于密度泛函理论的分子动力学模拟与热膨胀和弹性测量结果进行了比较。结果表明,晶格参数的温度依赖性和热膨胀斜率与测量结果一致。根据选定温度下的衍射扫描,ε 相在空气中保持稳定,至少到 770 K。同样,扩张仪显示热膨胀平稳,直到 950 K 左右的热分解温度。首次收集到了ε相 Ziracloy-4 hydride 的完整弹性特性测量值。与金属相和δ氢化物相相比,杨氏模量较低。由于声耗散效应,高温弹性测量被限制在 350 K。
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 去求助
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.
期刊最新文献
Editorial Board Additive manufactured ODS-FeCrAl steel achieves high corrosion resistance in lead-bismuth eutectic (LBE) Molecular dynamics simulations on the evolution of irradiation-induced dislocation loops in FeCoNiCrCu high-entropy alloy Effect of grain boundary engineering on corrosion behavior and mechanical properties of GH3535 alloy in LiCl-KCl molten salt Pressure-less joining SiCf/SiC tube and Kovar alloy with AgCuInTi filler: Interfacial reactions and mechanical properties
×
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
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 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 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1