A UO2-based salt target for rapid isolation of fission products

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...

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Bibliographic Details
Published in:Journal of radioanalytical and nuclear chemistry 2019-03, Vol.319 (3), p.1291-1300
Main Authors: Dorhout, Jacquelyn M., Wilkerson, Marianne P., Czerwinski, Kenneth R.
Format: Article
Language:English
Subjects:
Acid extraction
Catcher
Chemistry
Chemistry and Materials Science
Diagnostic Radiology
Fission path lengths
Fission products
Hadrons
Heavy Ions
Inorganic Chemistry
Microparticles
Nuclear Chemistry
Nuclear Physics
Physical Chemistry
RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
Recoil energy
UO2 irradiation
Uranium
Uranium dioxide
Uranium microparticles
Uranium oxides
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Summary: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 HNO 3 are compared.
ISSN:0236-5731
1588-2780
DOI:10.1007/s10967-019-06433-9