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Solid Oxide Membrane Process for the Reduction of Uranium Oxide Surrogate in Spent Nuclear Fuel

机译:固体氧化物膜工艺减少乏核燃料中铀氧化物的替代

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Solid oxide membrane (SOM) electrolysis was employed to reduce ytterbium oxide (Yb_2O_3) which was identified as a possible surrogate for uranium oxide in spent nuclear fuel treatment. In this research, an yttria-stabilized zirconia (YSZ) tube was used as the SOM membrane in a LiF-YbF_3-Yb_2O_3 salt to reduce ytterbium (Yb) metal on an inert cathode. The melting point of the supporting electrolyte (LiF-YbF_3) was analyzed as a function of Yb_2O_3 concentration. The stability of YSZ tubes at the electrolysis operating temperature in the chosen flux was characterized. Yb metal deposited on the cathode during the SOM electrolysis process was analyzed.
机译:固体氧化物膜(SOM)电解用于还原氧化oxide(Yb_2O_3),氧化identified被确定为乏核燃料处理中铀氧化物的可能替代物。在这项研究中,使用氧化钇稳定的氧化锆(YSZ)管作为LiF-YbF_3-Yb_2O_3盐中的SOM膜来还原惰性阴极上的y(Yb)金属。分析支持电解质(LiF-YbF_3)的熔点与Yb_2O_3浓度的关系。表征了YSZ管在所选焊剂中在电解操作温度下的稳定性。分析了在SOM电解过程中沉积在阴极上的Yb金属。

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