Oxidation of U-10 at% Zr alloy in air at 432–1028 K
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference15 articles.
1. The oxidation behaviour of uranium in air at 50–300°C
2. The kinetics of oxidation of uranium between 300 and 625° C
3. The oxidation behaviour of highly irradiated uranium in dry carbon dioxide at 375–500°C and in dry air at 200–300°C
4. The Kinetics of Oxidation of Uranium between 125° and 250°C
5. The effect of the aluminium content of uranium upon its oxidation behaviour in carbon dioxide and air
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2. Performance of U3Si2 in an LWR following a cladding breach during normal operation;Journal of Nuclear Materials;2020-10
3. Anisotropic lattice thermal expansion of uranium-based metallic fuels: A high-temperature X-ray diffraction study;Journal of Nuclear Materials;2019-12
4. Oxidation behavior of U-6 mass% Zr alloy;Journal of Thermal Analysis and Calorimetry;2018-10-11
5. Crystallographic characterization of irradiated U-10Zr and U-10Zr-5Ce metallic fuels;J RADIOANAL NUCL CH;2017
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