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