The potential/pO2− diagrams of uranium and the feasibility of a pyrochemical head-end treatment of nuclear fuels in molten chlorides |
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| Authors: | L Martinot M Ligot |
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| Institution: | (1) Laboratory of Analytical Chemistry and Radiochemistry, B6, University in Liège, Sart-Tilman, B-4000 Liège, Belgium;(2) Present address: Research Associate of the Inter-University Institute for Nuclear Sciences, Brussels |
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| Abstract: | In this paper, the values of the solubility products of UO2 and MgUO4 in the (K–Na–Mg 1/2)Cl eutectic and the solubility products of UO2 and (K,Na)UO3 in the (K–Na)Cl eutectic are reported. The complete potential/pO2– diagram of uranium is set up in these liquid melts and a method of separation UO2/PuO2 is discussed in the molten chlorides media. |
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