MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION

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.

Bibliographic Details
Main Authors: Miroslav Cech, Martin Sevecek
Format: Article
Language:English
Published: CTU Central Library 2016-12-01
Series:Acta Polytechnica CTU Proceedings
Online Access:https://ojs.cvut.cz/ojs/index.php/APP/article/view/3740