UMOO6 PREPARATION FOR THE STUDY OF NUCLEAR FUEL OXIDATION
13th International Conference on CANDU Fuel - 2016 Aug. 15-18


Presented at:
13th International Conference on CANDU Fuel
2016 Aug. 15-18
Location:
Kingston, ON Canada
Session Title:
Session 12:Modelling & Computer Code Development - Advanced Methodology

Authors:
E. Corcoran (RMCC)
J. Scott (RMCC)
R.A. Barry (RMCC)
  

Abstract

The fission of uranium oxide or mixed oxides of uranium plutonium nuclear fuels results in the production of a large number of fission and activation products. The common fission product Mo accumulates and is known to form oxides, such as UMoO6. As an excellent scavenger of oxygen species within the fuel, an understanding of the thermodynamic properties of UMoO6 is imperative in order to properly model nuclear fuel behaviour under various conditions. This presentation reviews published procedures and full characterization of pure UMoO6 produced by an aqueous method through an intermediate Na-Mo-U-oxide. A unique single crystal structure was obtained for the intermediate Na2(UO2)6(MoO4)7(H2O)2 displaying a network of connected pentagonal bipyramidal U polyhedra and Mo tetrahedra, with Na ions and water molecules interspersed throughout the structure. By refluxing a sample of Na2(UO2)6(MoO4)7 in an excess of UO2(NO3)2, pure UMoO6 was isolated and fully characterized, establishing a facile route to obtain a pure sample. These samples where then utilized in a number of thermodynamic properties studies (e.g., measurement of heat capacity, decomposition temperature, and transition enthalpy).

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