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Abstract <p>Thermodynamic modeling of changes in the chemical and phase composition of uranium–zirconium carbonitride nuclear fuel U<sub>0.9</sub>Zr<sub>0.1</sub>(C<sub>0.495</sub>N<sub>0.495</sub>O<sub>0.01</sub>)<sub>0.995</sub> containing an oxygen impurity depending on the temperature (1600–2000 K) and burnup (1–10%) was performed. Under these conditions, accumulation of fission products in the fuel leads to the formation of a heterogeneous system consisting of a solid solution based on uranium–zirconium oxycarbonitride containing lanthanides and of separate condensed carbide, intermetallic, and oxide phases, of cesium and its iodide, of barium and its telluride, of strontium, and of technetium. The concentrations of these phases at the indicated temperatures and burnup levels were calculated.</p>

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Modeling of Changes in the Composition of Uranium–Zirconium Carbonitride with an Oxygen Impurity Depending on Temperature and Burnup

  • 期刊论文

  • 发表日期：

    2025年12月1日

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  • G. S. Bulatov,
  • K. E. German

摘要

Abstract

Thermodynamic modeling of changes in the chemical and phase composition of uranium–zirconium carbonitride nuclear fuel U0.9Zr0.1(C0.495N0.495O0.01)0.995 containing an oxygen impurity depending on the temperature (1600–2000 K) and burnup (1–10%) was performed. Under these conditions, accumulation of fission products in the fuel leads to the formation of a heterogeneous system consisting of a solid solution based on uranium–zirconium oxycarbonitride containing lanthanides and of separate condensed carbide, intermetallic, and oxide phases, of cesium and its iodide, of barium and its telluride, of strontium, and of technetium. The concentrations of these phases at the indicated temperatures and burnup levels were calculated.