Browsing Acta Polytechnica CTU Proceedings. 2016, vol. 4 by Author "Cech, Miroslav"
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MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION
Author: Cech, Miroslav; Sevecek, Martin
(České vysoké učení technické v PrazeCzech Technical University in Prague, 2016)This paper describes materials made of zirconium-based alloys used for nuclear fuel cladding fabrication. It is focused on corrosion problems their theoretical description and modeling in nuclear engineering.