Comparative study of simulated zirconia inert matrix fuel stabilized with yttrium, lanthanum or praseodymium: Synthesis and leaching tests

• Published in: Progress in nuclear energy (New series) Vol. 48; no. 1; pp. 70 - 84
• Main Authors: Kamel, N., Aït-Amar, H., Taouinet, M., Benazzouz, C., Kamel, Z., Fodil-Cherif, H., Telmoune, S., Slimani, R., Zahri, A., Sahel, D.
• Format: Journal Article
• Language: English
• Published: Tarrytown, NY Elsevier Ltd 2006; Oxford Elsevier
• Subjects: Applied sciences; Corrosion tests; Energy; Exact sciences and technology; Fuels; LaSZ; Nuclear fuels; Preparation and processing of nuclear fuels; PrSZ; Stabilized zirconia; Synthesis; YSZ; Corrosion tests; LaSZ; YSZ; Stabilized zirconia; Synthesis; PrSZ; Nuclear fuel; Microhardness; Corrosion; Lanthanum; Microstructure; Yttrium; Inert matrix fuel; Comparative study; Praseodymium; Crystalline structure
• ISSN: 0149-1970
• DOI: 10.1016/j.pnucene.2005.05.082

Stabilized zirconia inert matrix fuels were synthesized with different lanthanides: yttrium, lanthanum and praseodymium. The materials were sintered in air at 1723 K. Cerium, an analog element of plutonium and americium, was employed to simulate a minor actinide in the process development, owing to the high activity of minor actinides. For each matrix, several properties, such as crystalline structure, density, microhardness, specific area, microstructure and corrosion behaviour were measured. The best materials were those crystallized in a face centred cubic system, with the compositions: (Zr 0.73Y 0.14Er 0.05Ce 0.08)O 2, (Zr 0.73La 0.14Er 0.05Ce 0.08)O 2 and (Zr 0.73Pr 0.05Er 0.07Ce 0.15)O 2. Lanthanum stabilized zirconia materials were the best. The corrosion tests showed that the whole of materials has a satisfactory chemical stability.