Acta Polytechnica CTU Proceedings (Dec 2016)

MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION

  • Miroslav Cech,
  • Martin Sevecek

DOI
https://doi.org/10.14311/AP.2016.4.0013
Journal volume & issue
Vol. 4, no. 0
pp. 13 – 18

Abstract

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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.