Mario Alberto Gonzalez , Cameron Leavitt , Justin M. Holland , Michael F. Simpson
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UO2 solubility and chemical interactions in molten LiCl-Li2O
This study investigated the solubility of UO2 in LiCl-2 wt% Li2O at 650 °C with O2 partial pressures up to 114 torr. Experiments were run in which UO2 powder was contacted with the molten salt for up to 120 h. Salt samples were taken and analyzed for U and corrosion product concentration using inductively coupled plasma mass spectrometry and for Li2O concentration using titration. The highest measured U concentration in the salt was 0.06 wt%, and O2 partial pressure was observed to have little to no effect on the solubility. Increasing O2 partial pressure did increase the concentration of corrosion products in the salt. The concentration of Li2O in the molten salt progressively decreased with time in contact with UO2. This can be explained by the formation of Li2UO4 via reaction of UO2 with Li2O.
期刊介绍:
The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome.
The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example.
Topics covered by JNM
Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior.
Materials aspects of the entire fuel cycle.
Materials aspects of the actinides and their compounds.
Performance of nuclear waste materials; materials aspects of the immobilization of wastes.
Fusion reactor materials, including first walls, blankets, insulators and magnets.
Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties.
Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.