期刊
JOURNAL OF NUCLEAR MATERIALS
卷 442, 期 1-3, 页码 227-234出版社
ELSEVIER
DOI: 10.1016/j.jnucmat.2013.08.023
关键词
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The standard powder metallurgy preparation of SFR (Sodium Fast Reactor) oxide fuel involves UO2 and PuO2 co-milling. An alternative route, using a solid-solution of mixed oxide obtained by oxalic co-conversion as the starting material, is presented. It was used to manufacture nuclear fuels for the COPIX irradiation conducted in the Phenix SFR. Two processes using co-converted powders were tested to elaborate fuel pellets: (1) the Direct Process that consists in pressing and sintering the mixed oxide with the final Pu content and (2) the Dilution Process, which involves the dilution of a high Pu content mixed oxide with UO2. After studying the structural and microstructural evolution with temperature of these innovative raw materials, the elaboration parameters were adjusted to obtain final pellets in accordance with the Phenix fuel specifications. This study demonstrates the feasibility of such new fabrication route at laboratory scale and, from a more fundamental prospect, allows a better understanding of the underlying phenomena involved during sintering. (C) 2013 Elsevier B.V. All rights reserved.
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