Post-quench ductility evaluation of Zircaloy-4 and select iron alloys under design basis and extended LOCA conditions

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Materials Engineering, Materials Science, Lwr Fuel Cladding +5

High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments

Bruce A. Pint, Kurt A. Terrani, Michael P. Brady et al. · Journal of Nuclear Materials · 2013 · 478 citations

Materials Science, Chemical Engineering, High Temperature Materials +8

Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure

Ting Cheng, James R. Keiser, Michael P. Brady et al. · Journal of Nuclear Materials · 2012 · 177 citations

Materials Science, Chemical Engineering, Steam Distribution +7

High-temperature steam-oxidation behavior of Zr-1Nb cladding alloy E110

Yong Yan, Tatyana Burtseva, M.C. Billone · Journal of Nuclear Materials · 2009 · 80 citations

Materials Science, Materials Engineering, Engineering +6

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 · 72 citations · Full text

Engineering, Oxidation Resistance, Mechanical Engineering +19