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- W103146715 abstract "Previous work in Germany and Japan has indicated that crystallization of uranyl nitrate at low temperatures from nitric acid solution could be a useful process for removing most of the uranium from spent LWR fuel after the fuel is dissolved in nitric acid. The crystallization process potentially could reduce the cost of LWR fuel partitioning because it provides a selective and compact process for removing most of the uranium which is about 96% of the LWR spent fuel mass. Subsequent separation processes would only need to handle the smaller volume of remaining actinides and the fission products. We are evaluating an approach to separating uranyl nitrate that uses a continuous adiabatic reduced-pressure crystallizer to concentrate and cool a nitric acid solution from dissolution of spent fuel. Initial work to define the process flowsheet and obtain data on optimum crystallization conditions and the purity of the uranium product will be presented." @default.
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- W103146715 date "2004-01-01" @default.
- W103146715 modified "2023-09-27" @default.
- W103146715 title "Evaluation of uranyl nitrate crystallization for spent nuclear fuel separations" @default.
- W103146715 hasPublicationYear "2004" @default.
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