A mechanism for in-reactor oxidation of zirconium alloys from oxide electrical characteristics: (III). Zr-2.5 wt % Nb
- 31 August 1974
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 52 (1) , 13-23
- https://doi.org/10.1016/0022-3115(74)90021-x
Abstract
No abstract availableKeywords
This publication has 12 references indexed in Scilit:
- 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
- A mechanism for in-reactor oxidation of zirconium alloys from oxide electrical characteristics: (I). Zircaloy-2Journal of Nuclear Materials, 1974
- The effects of radiation and oxygen on the aqueous oxidation of zirconium and its alloys at 290 °cJournal of Nuclear Materials, 1973
- The effects of radiation on the corrosion of some Zr alloysCorrosion Science, 1970
- Effects of Alloying and Irradlation on the Oxidation Behaviour of Zirconium AlloysBritish Corrosion Journal, 1970
- Effects of irradiation on the oxidation of zirconium alloys in high temperature aqueous environments: A reviewJournal of Nuclear Materials, 1968
- The influence of niobium in irradiation strengthening of dilute Zr-Nb alloysPhilosophical Magazine, 1968
- The Properties of Oxide Films Formed on a Zirconium-2.7 w/o Niobium Alloy in the Temperature Range 300°–500°CJournal of the Electrochemical Society, 1968
- Use of Ammonia to Supress Oxygen Production and Corrosion in Boiling-Water ReactorsCorrosion, 1967
- The Oxidation Properties of a Zirconium-2.7 w/o Niobium Alloy in the Temperature Range 300°–500°CJournal of the Electrochemical Society, 1967