A model to describe the interaction between UO2 and zircaloy in the temperature range 1000–1700°C
- 31 May 1983
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 116 (1) , 44-54
- https://doi.org/10.1016/0022-3115(83)90290-8
Abstract
No abstract availableKeywords
This publication has 9 references indexed in Scilit:
- Model to simulate oxidation kinetics of zircaloy-4 during temperature transients between 600 and 800°CJournal of Nuclear Materials, 1983
- Model to simulate high temperature oxidation kinetics of zircaloy-4: Parabolic and linear behaviourJournal of Nuclear Materials, 1982
- Diffusion in a semi-infinite system with a moving interphase considering solvent density change: application to the oxidation of zirconiumJournal of Nuclear Materials, 1981
- Diffusion in a semi-infinite system with a moving interface at constant temperature for application to α-zirconium oxidation at high temperatureJournal of Nuclear Materials, 1980
- The kinetics of the uranium dioxide—Zircaloy reactions at high temperaturesJournal of Nuclear Materials, 1979
- Oxygen Diffusion in the Oxide and Alpha Phases during Reaction of Zircaloy‐4 with Steam from 1000° to 1500°CJournal of the Electrochemical Society, 1979
- The diffusion of oxygen in alpha-zirconiumJournal of Nuclear Materials, 1977
- A Study of the Diffusion of Oxygen in Alpha‐Zirconium by Means of Nuclear MicroanalysisJournal of the Electrochemical Society, 1975
- The solubility of uranium in uraniaJournal of Nuclear Materials, 1968