Microstructurally Explicit Simulation of Intergranular Mass Transport in Oxide Nuclear Fuels
Author:
Affiliation:
1. Arizona State University, School for Engineering of Matter, Transport and Energy Tempe, Arizona 85287-6106
2. Los Alamos National Laboratory, Materials Science and Technology Division Los Alamos, New Mexico 87545
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT13-A16427
Reference24 articles.
1. Fundamental aspects of nuclear reactor fuel elements
2. On the role of grain boundary diffusion in fission gas release
3. Grain Boundaries in Uranium Dioxide: Scanning Electron Microscopy Experiments and Atomistic Simulations
4. Diffusion on grain boundary networks: Percolation theory and effective medium approximations
5. Percolation on grain boundary networks: Application to fission gas release in nuclear fuels
Cited by 3 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. Spectral graph theory for characterization and homogenization of grain boundary networks;Acta Materialia;2018-03
2. Effects of microstructural constraints on the transport of fission products in uranium dioxide at low burnups;Journal of Nuclear Materials;2016-08
3. Microstructurally Explicit Study of Transport Phenomena in Uranium Oxide;TMS 2014 Supplemental Proceedings;2014-01-24
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