MODELLING OF NUCLEAR FUEL CLADDING TUBES CORROSION
oleh: Miroslav Cech, Martin Sevecek
| Format: | Article |
|---|---|
| Diterbitkan: | CTU Central Library 2016-12-01 |
Deskripsi
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.