Interaction of self-interstitials with oxygen atoms in electron-irradiated zirconium
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference21 articles.
1. Recovery of electron-irradiated zirconium at low temperatures
2. Damage rate and recovery measurements on zirconium after electron irradiation at low temperatures
3. Frottement interne dans le zirconium irradie aux neutrons A 77 K
4. The application of channeling for locating impurity atoms and investigating impurity-defect interactions in zirconium
5. Backscattering measurements of the trapping of Zr Self-interstitial atoms by Au Atoms in irradiated Zr-Au Crystals
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1. Influence of vacancy diffusional anisotropy: Understanding the growth of zirconium alloys under irradiation and their microstructure evolution;Acta Materialia;2020-08
2. Effect of Hydrogen on Dimensional Changes of Zirconium and the Influence of Alloying Elements: First-Principles and Classical Simulations of Point Defects, Dislocation Loops, and Hydrides;Zirconium in the Nuclear Industry: 17th Volume;2014-06-17
3. Effect of Oversized Alloying Elements on Damage Rates and Recovery in Zirconium;MRS Proceedings;2009
4. Atomistic calculation of point-defect diffusion anisotropy and irradiation growth inα-zirconium;Philosophical Magazine;2007-06
5. Low-dimension self-interstitial diffusion in α-Zr;Applied Physics A: Materials Science & Processing;2003-01-01
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