Enhanced high-temperature oxidation resistance of a zirconium alloy cladding by high-temperature preformed oxide on the cladding

Accident tolerant fuels for LWRs: A perspective

S.J. Zinkle, Kurt A. Terrani, Jess C Gehin et al. · Journal of Nuclear Materials · 2013 · 1.1K citations

Engineering, Nuclear Engineering, Combustion +11

Transmission electron microscopy examination of oxide layers formed on Zr alloys

Aylin Yilmazbayhan, E. Breval, Arthur T. Motta et al. · Journal of Nuclear Materials · 2006 · 273 citations

Natural Sciences, Materials Engineering, Materials Science +16

Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea

Hyung‐Il Kim, Jae‐Ho Yang, Weon-Ju Kim et al. · Nuclear Engineering and Technology · 2015 · 250 citations · Full text

Engineering, Materials Engineering, Nuclear Engineering +17

High-temperature oxidation of zircaloy-2 and zircaloy-4 in steam

V.F. Urbanic, T. R. Heidrick · Journal of Nuclear Materials · 1978 · 243 citations

Natural Sciences, Materials Engineering, Materials Science +12

The influence of grain-boundary segregation of Y in Cr2O3 on the oxidation of Cr metal

C. M. Cotell, G. J. Yurek, R. J. Hussey et al. · Oxidation of Metals · 1990 · 179 citations

Natural Sciences, Materials Engineering, Materials Science +9