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- W2912553147 abstract "We report here an initial isolation study based upon the use of small uranium oxide particles dispersed in a soluble salt matrix to evaluate the relative recovery of fission products into acidic media. We further show that the macrostructures of the uranium microparticles are largely preserved, such that the bulk target material could be retained for additional irradiations or characterizations. Through this approach, fission products can be separated from the actinide-based target using low molarities of acid without the need to dissolve the actinide itself, reducing the amount of acidic waste. Extraction yields using two molarities of HCl and HNO3 are compared." @default.
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- W2912553147 date "2019-01-30" @default.
- W2912553147 modified "2023-10-12" @default.
- W2912553147 title "A UO2-based salt target for rapid isolation of fission products" @default.
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- W2912553147 doi "https://doi.org/10.1007/s10967-019-06433-9" @default.
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