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Hydroxide coprecipitation effectively synthesizes Uranium-Plutonium mixed oxide (MOX) nuclear fuel with excellent cationic homogeneity. Different precipitation methods yield varying microstructures but consistently uniform element distribution.

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Area of Science:

  • Nuclear Materials Science
  • Solid-State Chemistry
  • Ceramic Engineering

Background:

  • Mixed oxide (MOX) fuels containing uranium (U) and plutonium (Pu) are crucial for advanced nuclear reactors.
  • Achieving high cationic homogeneity in MOX fuels is essential for predictable performance and safety.
  • Hydroxide coprecipitation is a key synthesis route for MOX fuel fabrication.

Purpose of the Study:

  • To synthesize U0.86Pu0.14O2±x solid solutions using hydroxide coprecipitation.
  • To evaluate the impact of different precipitation methods on cationic homogeneity and microstructure.
  • To assess the influence of plutonium content on the physicochemical and sintering behavior of MOX powders.

Main Methods:

  • Hydroxide coprecipitation of U(IV) and Pu(IV) or Pu(III) from nitric acid solutions.
  • Calcination and sintering of oxide precipitates at 1700 °C under Ar-4.3 vol% H2.
  • Comparison of three precipitation routes: simultaneous U(IV)-Pu(IV), simultaneous U(IV)-Pu(III), and premixed U(IV)-Pu(III).

Main Results:

  • All precipitation methods resulted in highly uniform U and Pu distribution, exceeding homogeneity from other routes.
  • Distinct microstructures and sintering capabilities were observed despite macroscopic similarity.
  • Plutonium content significantly influenced the physicochemical and sintering properties of the synthesized MOX powders.

Conclusions:

  • Hydroxide coprecipitation is a robust method for achieving excellent cationic homogeneity in MOX fuels.
  • Microstructure and sintering behavior are sensitive to the precipitation method and Pu content.
  • The findings provide valuable insights for optimizing MOX fuel fabrication processes.