Isothermal experiments on steam oxidation of magnetron-sputtered chromium-coated zirconium alloy cladding at 1200 ℃

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

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

Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings

Chongchong Tang, Michael Stueber, Hans J. Seifert et al. · Corrosion Reviews · 2017 · 457 citations · Full text

Engineering, Materials Engineering, Materials Science +17

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