Coexistence of He and H in ceramic insulators for the DCLL Breeding Blanket: Evaluation of potential synergistic effects by TEM and nanoindentation

IF 2.7 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY
M. Roldán , J.M. García , M. González , V. Bonache , J. Rams
{"title":"Coexistence of He and H in ceramic insulators for the DCLL Breeding Blanket: Evaluation of potential synergistic effects by TEM and nanoindentation","authors":"M. Roldán ,&nbsp;J.M. García ,&nbsp;M. González ,&nbsp;V. Bonache ,&nbsp;J. Rams","doi":"10.1016/j.nme.2025.101963","DOIUrl":null,"url":null,"abstract":"<div><div>The development of ceramic insulators for fusion applications requires a detailed understanding of their microstructural and mechanical responses under radiation conditions representative of transmutation gas generation. In this work, polycrystalline alumina (Al<sub>2</sub>O<sub>3</sub>) and silicon-infiltrated silicon carbide (SiC-Si) ceramics were subjected to sequential helium (He) and hydrogen (H) ion implantation at MeV energies to evaluate potential synergistic effects on damage accumulation. Ion stopping profiles were designed to produce overlapping damage regions, and the resulting microstructures were examined by focused ion beam lamellae and transmission electron microscopy (FIB+TEM), while mechanical properties were assessed by nanoindentation. In Al<sub>2</sub>O<sub>3</sub>, irradiation induced a high density of nanocavities of nanocavities and dislocation loops, with cavity alignment possibly influenced by hydrogen-induced local strain fields. Conversely, SiC-Si showed a minimal presence of visible defects, suggesting effective recombination mechanisms at SiC/Si interfaces. Hardness increased modestly in both materials—by ∼ 8% in Al<sub>2</sub>O<sub>3</sub> and ∼ 20% in SiC-Si—consistent with the presence of dispersed radiation defects. No evidence of enhanced damage due to He–H synergy was observed, as the microstructural and mechanical changes were consistent with the additive effects of each ion species. These results support the suitability of Al<sub>2</sub>O<sub>3</sub> and, particularly, SiC-Si for use as insulating components in the Dual Coolant Lithium Lead (DCLL) breeding blanket of the future DEMO fusion reactor.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"44 ","pages":"Article 101963"},"PeriodicalIF":2.7000,"publicationDate":"2025-06-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Materials and Energy","FirstCategoryId":"101","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S235217912500105X","RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

The development of ceramic insulators for fusion applications requires a detailed understanding of their microstructural and mechanical responses under radiation conditions representative of transmutation gas generation. In this work, polycrystalline alumina (Al2O3) and silicon-infiltrated silicon carbide (SiC-Si) ceramics were subjected to sequential helium (He) and hydrogen (H) ion implantation at MeV energies to evaluate potential synergistic effects on damage accumulation. Ion stopping profiles were designed to produce overlapping damage regions, and the resulting microstructures were examined by focused ion beam lamellae and transmission electron microscopy (FIB+TEM), while mechanical properties were assessed by nanoindentation. In Al2O3, irradiation induced a high density of nanocavities of nanocavities and dislocation loops, with cavity alignment possibly influenced by hydrogen-induced local strain fields. Conversely, SiC-Si showed a minimal presence of visible defects, suggesting effective recombination mechanisms at SiC/Si interfaces. Hardness increased modestly in both materials—by ∼ 8% in Al2O3 and ∼ 20% in SiC-Si—consistent with the presence of dispersed radiation defects. No evidence of enhanced damage due to He–H synergy was observed, as the microstructural and mechanical changes were consistent with the additive effects of each ion species. These results support the suitability of Al2O3 and, particularly, SiC-Si for use as insulating components in the Dual Coolant Lithium Lead (DCLL) breeding blanket of the future DEMO fusion reactor.
DCLL育种毯中He和H在陶瓷绝缘子中的共存:用透射电镜和纳米压痕评价潜在的协同效应
用于聚变应用的陶瓷绝缘体的开发需要详细了解其微结构和在代表嬗变气体产生的辐射条件下的机械响应。在这项工作中,对多晶氧化铝(Al2O3)和硅渗透碳化硅(SiC-Si)陶瓷进行了MeV能量的氦(He)和氢(H)离子注入,以评估潜在的协同效应对损伤积累的影响。设计离子停止轮廓线,产生重叠的损伤区域,并通过聚焦离子束片和透射电子显微镜(FIB+TEM)检查所产生的微观结构,同时通过纳米压痕评估力学性能。在Al2O3中,辐照诱导了高密度的纳米空腔和位错环,空腔的排列可能受到氢诱导的局部应变场的影响。相反,SiC-Si显示出最小的可见缺陷,表明在SiC/Si界面上存在有效的复合机制。两种材料的硬度都略有增加,Al2O3增加了8%,sic - si增加了20%,这与分散辐射缺陷的存在一致。没有证据表明He-H协同作用增强了损伤,因为微观结构和力学变化与每种离子的加性作用一致。这些结果支持了Al2O3,特别是SiC-Si作为绝缘元件在未来DEMO聚变反应堆的双冷却剂锂铅(DCLL)繁殖层中的适用性。
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
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
×
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:604180095
Book学术官方微信