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Study on the Oxidation Behavior of Uranium Dioxide in Carbonate Molten Salts

  • Zhuang Shen
  • , Guoan Ye
  • , Haofan Fang
  • , Chunhui Li
  • , Luping Wang
  • , Meng Zhang
  • , Mingjian He*
  • , Caishan Jiao*
  • *Corresponding author for this work
  • Harbin Engineering University
  • Heilongjiang Provincial Key Laboratory of Nuclear Chemical Engineering and Radiochemistry
  • China National Nuclear Corporation

Research output: Contribution to journalArticlepeer-review

Abstract

The molten salt oxidation (MSO) process has significant potential for spent fuel reprocessing. In this work, we focused on the initial oxidation stage of the MSO process, investigating the effects of temperature, KNO3, and carbonate molten salt composition on the oxidation behavior of UO2 in molten salt. The results indicate that increasing the molten salt temperature can significantly enhance the oxidation rate of UO2; the oxidation rate of UO2 is fastest in the Li2CO3–K2CO3 eutectic molten salt for different molten salt compositions; the addition of KNO3 has a significant impact on the oxidation process of UO2─when the molar ratio of KNO3 to UO2 exceeds 0.4, complete oxidation of UO2 in carbonate molten salt can be achieved within 1 h. In addition, the oxidation product evolution during UO2 oxidation was investigated. The results show that UO2 is first oxidized to U3O8 and then is further converted to K2U2O7. At temperatures above 650 °C in the presence of carbonates, K2U2O7 is transformed into Li4UO5. In the end, we found that KNO3 functions as an oxidant in the UO2 oxidation process, deduces the UO2 molten salt oxidation equation, and summarizes the reaction mechanism.

Original languageEnglish
Pages (from-to)2162-2172
Number of pages11
JournalInorganic Chemistry
Volume65
Issue number4
DOIs
StatePublished - 2 Feb 2026
Externally publishedYes

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