Oxidation behavior of U–10 wt% Mo alloy in air at 473–773 K
- 31 August 2002
- journal article
- Published by Elsevier BV in Journal of Nuclear Materials
- Vol. 304 (2-3), 242-245
- https://doi.org/10.1016/s0022-3115(02)00905-4
Abstract
No abstract availableKeywords
This publication has 14 references indexed in Scilit:
- Characterization of U-2 wt% Mo and U-10 wt% Mo alloy powders prepared by centrifugal atomizationJournal of Nuclear Materials, 1997
- Oxidation behavior of U3Si (3.9 wt% Si) in air at 250–400°CJournal of Nuclear Materials, 1996
- Oxidation of U-10 at% Zr alloy in air at 432–1028 KJournal of Nuclear Materials, 1994
- Oxidation studies on UZr alloysJournal of Nuclear Materials, 1994
- Oxidation of U-20 at% Zr alloy in air at 423–1063 KJournal of Nuclear Materials, 1993
- The oxidation of uranium-0.75 wt% titanium in environments containing oxygen and/or water vapor at 140°CJournal of Nuclear Materials, 1987
- A review of the rates of reaction of uranium with oxygen and water vapour at temperatures up to 300° cJournal of Nuclear Materials, 1981
- The effect of the aluminium content of uranium upon its oxidation behaviour in carbon dioxide and airJournal of Nuclear Materials, 1977
- The oxidation behaviour of highly irradiated uranium in dry carbon dioxide at 375–500°C and in dry air at 200–300°CJournal of Nuclear Materials, 1974
- The kinetics of oxidation of uranium between 300 and 625° CJournal of Nuclear Materials, 1966