MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION

Miroslav Cech, Martin Sevecek

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.

Refbacks

  • There are currently no refbacks.


Creative Commons License
This work is licensed under a Creative Commons Attribution 4.0 International License.

ISSN 2336-5382 (Online)
Published by the Czech Technical University in Prague