研究论文开放获取
Experimental characterizations by EBSD and TEM of sub-grain boundaries and dislocations in low irradiated UO2 fuels
C. Onofri, I. Zacharie-Aubrun, D. Drouan, T. Blay, C. Sabathier, T. Grenèche, K. Hanifi, Carlos Rodríguez‐Abreu 等 13 位
Commissariat à l'Énergie Atomique et aux Énergies Alternatives CEA Cadarache
来源Journal of Nuclear Materials
年份2025
阅读操作
确认中在文库中上传 PDF 后可生成中文音频讲解。
摘要与影响
摘要 · 节选
暂未获取摘要。可打开原文或 PDF，后续可基于全文生成更完整的速读。
逐年被引趋势
320
25
326
关键指标
4
被引次数 · OpenAlex
1.13
领域内被引倍数
同类平均 = 1
同类平均 = 1
前 25%
引用位次
同领域 · 同年份 · 同类型
同领域 · 同年份 · 同类型
58
参考文献
Google Scholar 与 OpenAlex 的被引统计范围不同，数值存在差异属正常。
AI 辅助阅读
依据：文献信息
论文问答
当前基于文献信息回答
可就本文提问；依据不足时会说明。
学术脉络
学科主题
材料 / 化学Nuclear Materials and Properties
Nuclear reactor physics and engineering · Fusion materials and technologies
参考文献 58
Fundamental Aspects of Inert Gases in Solids
被引 241S. E. Donnelly, John H. Evans · NATO ASI series. Series B : Physics · 1991
Fission Gas Behaviour during Power Transients in High Burn-Up LWR Nuclear Fuels Studied by Electron Microscopy
被引 7I. L. F. Ray, H. Thiele, Hj. Matzke · NATO ASI series. Series B : Physics · 1991
Interpretation of the stress dependence of creep by a mixed climb mechanism in TiAl
被引 34J. Malaplate, D. Caillard, A. Couret · The Philosophical Magazine A Journal of Theoretical Experimental and Applied Physics · 2004
此处列出前 3 条
引用本文 4
Atomistically-informed cross-slip and slip-system transition modeling in uranium dioxide
被引 1Jules-Elémir Suchorski, Adrien Pivano, L. Dupuy · International Journal of Plasticity · 2026
In-situ ion irradiation induced nanograin growth in a spent UO2 fuel
被引 0Sadman Sakib, Yunyuan Lu, Cameron B. Howard · Journal of Nuclear Materials · 2025
UO2-composite fuels with enhanced thermal conductivity for improved safety and performance of LWRs - A review of the technological status and challenges
被引 0Jae Ho Yang, Dong Seok Kim, Heung Soo Lee · Nuclear Engineering and Technology · 2026
按被引量排序，此处列出前 3 条