The co-precipitation method in the production of thorium oxide and uranium–thorium mixed oxide fuels − A review

[Display omitted] Thorium oxide is referred to as the world’s nuclear fuel of the future for fourth-generation reactors, according to its numerous advantages. So, it is essential to provide practical solutions to improve thoria production technology.Recently, the oxalates co-precipitation method has...

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Veröffentlicht in:Nuclear engineering and design 2024-09, Vol.426, p.113366, Article 113366
Hauptverfasser: Bagheri, Narges, Nosratinia, Ferial, Zahakifar, Fazel, Yousefi, Taher
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Sprache:eng
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Zusammenfassung:[Display omitted] Thorium oxide is referred to as the world’s nuclear fuel of the future for fourth-generation reactors, according to its numerous advantages. So, it is essential to provide practical solutions to improve thoria production technology.Recently, the oxalates co-precipitation method has received much attention as a wet method with many benefits, including reducing the production of radioactive dust and producing a homogeneous product. One of the significant advantages of this method is the possibility of precise control of the final oxide characteristics through the optimization of precipitation and heat treatment conditions. This study attempts to provide a complete report on the effect of multiple parameters of the oxalate precipitation and decomposition method, such as temperature, stirrer, and calcination, on the various properties of the final ThO2powder, including size, morphology, and surface area. In addition, the synthesis of (U-Th)O2fuels via oxalate co-precipitation and hydrothermal methods is investigated.
ISSN:0029-5493
1872-759X
DOI:10.1016/j.nucengdes.2024.113366