Comparison between bulk and thin foil ion irradiation of ultra high purity Fe
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference8 articles.
1. On the potentiality of using ferritic/martensitic steels as structural materials for fusion reactors
2. Helium and point defect accumulation: (i) microstructure and mechanical behaviour
3. Dislocation loop structure, energy and mobility of self-interstitial atom clusters in bcc iron
4. A. Prokhodtseva, B. Décamps, A. Ramar, R. Schäublin, Impact of He and Cr on defect accumulation in ion irradiated ultra high purity Fe(Cr) alloys, submitted for publication.
5. Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 1: Damage evolution in thin-foils at lower doses
Cited by 54 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献
1. In-situ TEM investigation of recovery mechanisms in ion-irradiated ITER-grade tungsten;Journal of Nuclear Materials;2024-10
2. In-situ TEM characterization of dislocation loops in tungsten under simultaneous helium and hydrogen irradiation;Journal of Nuclear Materials;2024-09
3. Elastic stress field solution of helical dislocation lines in BCC Iron: A three-dimensional anisotropic linear elasticity study;Computational Materials Science;2024-06
4. An FFT based approach to account for elastic interactions in OkMC: Application to dislocation loops in iron;Journal of Nuclear Materials;2024-06
5. An evaluation of Ar ion milling in TEM sample preparation by energy-filtered TEM technique;Vacuum;2024-04
1.学者识别学者识别
2.学术分析学术分析
3.人才评估人才评估
"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370
www.globalauthorid.com
TOP
Copyright © 2019-2024 北京同舟云网络信息技术有限公司 京公网安备11010802033243号 京ICP备18003416号-3