Optimizing Nuclear Fuel Fabrication

Several types of nuclear reactors are currently using uranium dioxide (UO2) as well as actinide mixed oxides such as (U,Pu)O2 MOx and these are still considered to be reference components for future concepts. If the sintering of these ceramics was extensively investigated for powder metallurgy methods, the latest emergence of new ways of preparation for actinides dioxides, primarily based on the precipitation of low-temperature precursors, requires caring about the role of chemistry during sintering and its effect over the final microstructure of the pellets.

In this article, the preparation of UO2 powders was undertaken from uranium(IV) oxalate in order to understand the effect of several parameters over the densification process, including the impact of the residual carbon content retained in the oxide following thermal conversion of the initial precursor.

The significant role played by the atmosphere of calcination was revealed by the extensive characterization of the powders obtained from the conversion of oxalate precursor under different heating conditions. The main differences seen arose from the oxidization of U(IV) under air in the particular case of uranium-bearing compounds. Indeed, this later leads to changes at the microscopic scale, specifically concerning diffusion coefficients that strongly influence the development of the powder microstructure. Besides dealing with the crystallite size, which considerably increased during calcination under oxidizing atmosphere, these changes were also concerned with the grains morphology at the macroscopic level through solarization-related processes.

Densification Processes and Final Microstructure

Densification processes and final microstructure of the sintered pellets prepared following sintering at high temperatures also considerably differ regarding to the conditions of preparation of the starting powder. Such modifications mainly occur from the in depth differences presented above, but also arise from differences in the residual carbon content of the oxide powders. Although expected from the data earlier reported in the literature for other actinide-bearing oxides prepared from oxalate precursors, the effect of the atmosphere of conversion on the residual carbon content was proved in this study. As a matter of evidence, the amount of carbon was systematically detected to be 4 to 5 times higher in the samples prepared under only reducing conditions. Additionally, thanks to a Hiden Analytical QGA analyzer, an original coupling between dilatometric measurements and MS analysis (Figure 1) was set.Nuclear Fuel Fabrication, Nuclear Fuel, Fabrication, Nuclear, Fuel Fabrication

 

Hiden QGA Real-time gas analyzer

 

Conclusion

It showed that carbon was eliminated during the first step of the densification as gaseous CO2. However, the residual carbon content was observed to be more likely a second-order parameter to be taken into account in order to evaluate the behavior of the samples during the sintering process. Indeed, the more significant variations stated when studying the microstructure of the sintered samples came from redox or morphological considerations (presence of U3O8 in the starting powder, decrease of reactivity through improved crystallite growth, …). Conversely, despite the vital differences measured in terms of carbon content in the final samples, neither the relative density of the sintered pellets nor the average grain size were found to be considerably modified.

Dilatometry/MS study of the sample obtained after conversion of U(C2O4)2.2H2O under reducing atmosphere at 500 °C.

Figure 1. Dilatometry/MS study of the sample obtained after conversion of U(C2O4)2.2H2O under reducing atmosphere at 500 °C.

Project Summary By:

Nicolas CLAVIER / Julien MARTINEZ
ICSM, UMR 5257 CEA/CNRS/ESNCM/Univ. Montpellier,
Site de Marcoule Bât. 426,
BP 17171, 30207 Bagnols/Cèze cedex
France

Paper Reference

F J. Martinez, N. Clavier, T. Ducasse, A. Mesbah, F. Audubert, B. Corso, N. Vigier, N. Dacheux : "From uranium(IV) oxalate to sintered UO2 : consequences of the powders’ thermal history on the microstructure", J. Europ. Ceram. Soc., 35, 4535-4546, 2015.

This information has been sourced, reviewed and adapted from materials provided by Hiden Analytical.

For more information on this source, please visit Hiden Analytical.

Citations

Please use one of the following formats to cite this article in your essay, paper or report:

  • APA

    Hiden Analytical. (2021, December 17). Optimizing Nuclear Fuel Fabrication. AZoM. Retrieved on November 23, 2024 from https://www.azom.com/article.aspx?ArticleID=14014.

  • MLA

    Hiden Analytical. "Optimizing Nuclear Fuel Fabrication". AZoM. 23 November 2024. <https://www.azom.com/article.aspx?ArticleID=14014>.

  • Chicago

    Hiden Analytical. "Optimizing Nuclear Fuel Fabrication". AZoM. https://www.azom.com/article.aspx?ArticleID=14014. (accessed November 23, 2024).

  • Harvard

    Hiden Analytical. 2021. Optimizing Nuclear Fuel Fabrication. AZoM, viewed 23 November 2024, https://www.azom.com/article.aspx?ArticleID=14014.

Ask A Question

Do you have a question you'd like to ask regarding this article?

Leave your feedback
Your comment type
Submit

While we only use edited and approved content for Azthena answers, it may on occasions provide incorrect responses. Please confirm any data provided with the related suppliers or authors. We do not provide medical advice, if you search for medical information you must always consult a medical professional before acting on any information provided.

Your questions, but not your email details will be shared with OpenAI and retained for 30 days in accordance with their privacy principles.

Please do not ask questions that use sensitive or confidential information.

Read the full Terms & Conditions.