MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION

Authors

  • Miroslav Cech Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, V Holesovickach 2, Praha 8, Czech Republic
  • Martin Sevecek ALVEL a.s., Opletalova 37, Praha 1, Czech Republic

DOI:

https://doi.org/10.14311/AP.2016.4.0013

Abstract

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.

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Published

2016-12-16

Issue

Vol. 4 (2016): ŠIMÁNĚ 2016

Section

Articles

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