Oxidation of Zirconium and its Alloys
- 1 January 1976
- book chapter
- Published by Springer Nature
Abstract
No abstract availableKeywords
This publication has 100 references indexed in Scilit:
- A mechanism for in-reactor oxidation of zirconium alloys from oxide electrical characteristics: (III). Zr-2.5 wt % NbJournal of Nuclear Materials, 1974
- A mechanism for in-reactor oxidation of zirconium alloys from oxide electrical characteristics: (II). Crystal-bar zirconium and Zr-1.2 wt % Cr-0.08 wt % FeJournal of Nuclear Materials, 1974
- Corrosion behaviour of new Zr alloysJournal of Nuclear Materials, 1974
- Tritium diffusion in zircaloy-2 in the temperature range −78 to 204° CJournal of Nuclear Materials, 1974
- Oxygen diffusion in beta zircaloy during steam oxidationJournal of Nuclear Materials, 1974
- A mechanism for in-reactor oxidation of zirconium alloys from oxide electrical characteristics: (I). Zircaloy-2Journal of Nuclear Materials, 1974
- Oxydation du zirconium en phase β sous tres basses pressions. Aspect superficiel presente par les alliages zirconium-oxygeneJournal of Nuclear Materials, 1967
- The embrittlement of oxide films on zirconium by neutron irradiationJournal of Nuclear Materials, 1967
- Further studies on the inhibition by boric acid of the oxidation of zirconium in high pressure steamJournal of Nuclear Materials, 1965
- Contribution a l'etude de la cinetique de l'oxydation du zirconium α et de la diffusion de l'oxygene dans le metal sous-jacent a l'oxydeJournal of Nuclear Materials, 1965