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JOM (1989), ISSN 1543-1851, 2011, Volume 63, Issue 8, pp. 59 - 63
...Research Summary Advanced Fuel Performance: Modeling and Simulation Waterside Corrosion in Zirconium Alloys Arthur T. Motta How would you… …describe... 
Environment, general | Chemistry/Food Science, general | Materials Science, general | Material Science | Earth Sciences, general | Engineering, general | Physics, general | Physiological aspects | Zirconium | Research | Corrosion and anti-corrosives | Studies | Corrosion | Microstructure | Zirconium alloys
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 08/2016, Volume 477, Issue C, pp. 157 - 164
Journal Article
Microscopy and microanalysis, ISSN 1431-9276, 07/2016, Volume 22, Issue S3, pp. 1496 - 1497
...  1496 doi:10.1017/S1431927616008321 Multi-scale Characterization of Oxidized Zirconium Alloys Yan Dong1, Arthur T. Motta2 and Emmanuelle A. Marquis1 1... 
Nuclear and Irradiated Materials | Physical Science Symposia
Journal Article
Journal of nuclear materials, ISSN 0022-3115, 2015, Volume 466, Issue C, pp. 606 - 614
Zirconium carbide (ZrC) is a candidate material for use in one of the layers of TRISO coated fuel particles to be used in the Generation IV high-temperature,... 
Ion irradiation | Zirconium carbide | Nuclear materials | Defects | EVOLUTION | NUCLEAR SCIENCE & TECHNOLOGY | MATERIALS SCIENCE, MULTIDISCIPLINARY | AMORPHIZATION | RADIATION-DAMAGE | MICROSTRUCTURE | Zirconium | Carbides | Radiation | Stoichiometry | Zirconium carbides | Saturation | Clusters | Irradiation | Evolution | Microstructure
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 01/2018, Volume 498, Issue C
Journal Article
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, ISSN 0168-583X, 11/2017, Volume 410, Issue C
Journal Article