Concepedia
Nuclear Engineering and Technology · 2010 · 13 citations · 12 references
Open access
Natural SciencesMaterials EngineeringMaterials ScienceCeramicsMechanical Behavior Of MaterialsMetallurgyAlloysCladding MaterialsCladding SystemsHigh-temperature OxidationMetalsSurface OxidationOxidation Of Zirconium Cladding
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Oxidation kinetics of Zircaloy-4 and Zr–1Nb–1Sn–0.1Fe at temperatures of 700–1200°C
Jong Hyuk Baek, Ki Bum Park, Yong Hwan Jeong · Journal of Nuclear Materials · 2004 · 93 citations
Engineering, Materials Engineering, Materials Science +14
Breakaway phenomenon of Zr-based alloys during a high-temperature oxidation
Jong Hyuk Baek, Yong Hwan Jeong · Journal of Nuclear Materials · 2007 · 86 citations
Natural Sciences, Materials Engineering, Materials Science +15
High-temperature steam-oxidation behavior of Zr-1Nb cladding alloy E110
Yong Yan, Tatyana Burtseva, M.C. Billone · Journal of Nuclear Materials · 2009 · 83 citations
Natural Sciences, Materials Engineering, Materials Science +13
Oxidation Kinetics of Low-Sn Zircaloy-4 at the Temperature Range from 773 to 1,573K
Fumihisa Nagase, Takashi Otomo, Hiroshi Uetsuka · Journal of Nuclear Science and Technology · 2003 · 74 citations · Full text
Ductile-to-brittle transition of oxidised Zircaloy-4 and E110 claddings
Zoltán Hózer, C. Győri, L. Matus et al. · Journal of Nuclear Materials · 2007 · 64 citations
Natural Sciences, Materials Engineering, Materials Science +14