A UO2-Based Salt Target for Rapid Isolation of Fission Products
Journal of Radioanalytical and Nuclear Chemistry
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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.
Fission products; Recoil energy; UO2 irradiation; Acid extraction; Uranium microparticles; Fission path lengths; Catcher
Biochemistry | Chemistry
Dorhout, J. M.,
Wilkerson, M. P.,
Czerwinski, K. R.
A UO2-Based Salt Target for Rapid Isolation of Fission Products.
Journal of Radioanalytical and Nuclear Chemistry, 319(3),