Microstructural evolution of intermetallic phase precipitates in Cr-coated Zirconium alloy cladding in high-temperature steam oxidation up to 1400 °C

Accident tolerant fuel cladding development: Promise, status, and challenges

Kurt A. Terrani · Journal of Nuclear Materials · 2018 · 927 citations · Full text

Engineering, Materials Engineering, Materials Science +12

Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors

Jean-Christophe Brachet, Isabel Idarraga-Trujillo, Marion Le Flem et al. · Journal of Nuclear Materials · 2019 · 381 citations

Engineering, Materials Science, Nuclear Engineering +14

High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process

Jean-Christophe Brachet, Elodie Rouesne, J. Ribis et al. · Corrosion Science · 2020 · 374 citations · Full text

Natural Sciences, Materials Engineering, Materials Science +13

Review on chromium coated zirconium alloy accident tolerant fuel cladding

Jianqiao Yang, M. Steinbrück, Chongchong Tang et al. · Journal of Alloys and Compounds · 2021 · 290 citations · Full text

Natural Sciences, Materials Engineering, Materials Science +12

High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments

Hwasung Yeom, Benjamin Maier, Greg Johnson et al. · Journal of Nuclear Materials · 2019 · 244 citations · Full text

Natural Sciences, Materials Engineering, Materials Science +13