Abstract
AbstractThe present work analyzes the effect of different Zr contents on the microstructure and thermal behavior of non-irradiated UO2. A set of Zr-doped UO2 (0, 20, 40, 80, and 100 wt%) pellets was prepared via solid-state synthesis by mimicking the chemical bonding between ZrO2 and UO2. After sintering, the Zr-doped UO2 monoliths were characterized by scanning electron microscopy, Raman spectroscopy, and X-ray diffraction. Oxidation of the Zr-doped UO2 samples has been monitored by thermogravimetric analysis. Results of thermal behavior under air and low oxygen partial pressure show a profound effect of delayed oxidation with the addition of Zr to UO2 and then an increased oxidation resistance of UO2 to U3O8 when compared to pure UO2 pellet.
Graphical abstract
Funder
H2020 Euratom
Ministerio de Ciencia e Innovación
CIEMAT
Publisher
Springer Science and Business Media LLC
Subject
Mechanical Engineering,Mechanics of Materials,Condensed Matter Physics,General Materials Science
Reference20 articles.
1. IAEA, Thermophysical Properties of Materials for Nuclear Engineering: A Tutorial and Collection of Data (International Atomic Energy Agency, Vienna, 2009)
2. C. Ciszak et al., J. Nucl. Mater. 520, 110–120 (2019)
3. D.G. Frost et al., J. Nucl. Mater. 528, 151876 (2020)
4. OCDE/NEA, Pellet-clad Interaction in Water Reactor Fuels : Seminar Proceedings Aix-en-Provence, France, 9–11 March 2004. Nuclear Science, OCDE, Paris, 2005.
5. F. Tanabe, J. Nucl. Sci. Technol. 48(8), 1135–1139 (2011)
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