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Argonne National Laboratory has proposed a new extraction procedure to handle TRISO-coated fuels, the Fluoride Extraction Process (FLEX). The FLEX process is designed to separate the uranium in the fuel from the actinides and most fission products by taking advantage of the unique properties of uranium hexafluoride (UF6). In the FLEX process, the used TRISO fuel is reacted with zirconium fluoride salt, forming UF6 and the fluoride salts of the actinides and fission products. At process temperatures, the UF6 volatizes into a gas, and is released from the molten salt mixture. This leaves behind the actinides and most fission products in a fluoride salt, which is subsequently processed using pyrochemical techniques to recover the actinides and other long lived fission products for transmutation. The UF6 is then cooled, causing it to sublime into solid form, which is then further processed for disposal or reuse.
The research effort was divided along two parallel paths: the Fabrication Path, led by collaborators at the Khlopin Radium Institute (KRI) in St. Petersburg, Russia; and the Characterization Path, led by researchers from UNLV.
The Fabrication Path focused on examining and evaluating various techniques for fabricating synthetic fluorapatite; synthesizing synthetic fluorapatite; and examining the impacts of waste loading and other fabrication process factors on the performance of the synthetic fluorapatite as a potential waste form.
The Characterization Path focused on adapting and refining the Xray spectroscopy techniques currently used to characterize borosilicate glass for use in examining the fluorapatite system. This path also encompassed the examination of the ceramic and synthetic mineral waste forms created at KRI, with subsequent examination of these techniques to develop a molecular-level understanding of natural fluorapatite and other fluorine-bearing natural phases as natural analogs for the waste form. These techniques were also be used to examine the changes in surface chemistry caused by environmental degradation of these materials.
Calcium phosphate; Ceramic materials; Fluorides; Phosphate minerals; Radioactive wastes – Purification; Separation (Technology); Zinc; Zirconium compounds
Radioactive wastes; Separation (Technology); Zirconium compounds
Chemistry | Oil, Gas, and Energy | Physical Chemistry
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Lindle, D. W.,
Perry, D. L.
Evaluation of Fluorapatite as a Waste-Form Material.
Available at: https://digitalscholarship.unlv.edu/hrc_trp_separations/63