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Abstract <p>This work investigates the effects of temperature and process time on the thermal reduction of uranium(VI) trioxide (UO<sub>3</sub>) to uranium(IV) dioxide (UO<sub>2</sub>) in a hydrogen atmosphere in the production of powdered precursors of ceramic nuclear fuel. The optimal temperature (500°C) and exposure time (180 min) to achieve the target phase composition and uranium dioxide stoichiometric ratio were determined by X-ray powder diffraction (XRD). Scanning electron microscopy (SEM) and XRD showed that long exposure times do not increase grain or secondary agglomerate sizes (<i>D</i><sub>XRD</sub> = 13.4–16.1 nm). X-ray photoelectron spectroscopy (XPS) confirmed the achievement of the target stoichiometry and showed 82–83% uranium reduction efficiency. The uranium dioxide produced under the optimized conditions is suitable for manufacturing ceramic nuclear fuel with superior mechanical properties via spark plasma sintering technology.</p>

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Reduction of Uranium Trioxide (UO3) to Uranium Dioxide (UO2) for Ceramic Nuclear Fuel

  • 期刊论文

  • 发表日期：

    2025年11月1日

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  • N. P. Ivanov,
  • O. O. Shichalin,
  • D. K. Tsygankov,
  • A. V. Shurygin,
  • K. V. Barkhudarov,
  • A. O. Lembikov,
  • V. L. Rastorguev,
  • S. A. Azon,
  • I. Yu. Buravlev,
  • I. G. Tananaev,
  • E. K. Papynov

摘要

Abstract

This work investigates the effects of temperature and process time on the thermal reduction of uranium(VI) trioxide (UO3) to uranium(IV) dioxide (UO2) in a hydrogen atmosphere in the production of powdered precursors of ceramic nuclear fuel. The optimal temperature (500°C) and exposure time (180 min) to achieve the target phase composition and uranium dioxide stoichiometric ratio were determined by X-ray powder diffraction (XRD). Scanning electron microscopy (SEM) and XRD showed that long exposure times do not increase grain or secondary agglomerate sizes (DXRD = 13.4–16.1 nm). X-ray photoelectron spectroscopy (XPS) confirmed the achievement of the target stoichiometry and showed 82–83% uranium reduction efficiency. The uranium dioxide produced under the optimized conditions is suitable for manufacturing ceramic nuclear fuel with superior mechanical properties via spark plasma sintering technology.