2018
DOI: 10.1016/j.jnucmat.2018.01.022
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A study on recovery of uranium in the anode basket residues delivered from the pyrochemical process of used nuclear fuel

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“…Photos of uranium metal fuels and chlorination product: uranium metal pellet (left) and chlorination product (right) [39]. NH 4 Cl was also investigated, recently, by H.C. Eun at al [40] By sparging a Cl 2 and CO gas mixture into a molten halide media, the uranium oxides could be chlorinated [41]. In this chlorination process, the suspended oxides was dissolved in the halide meda and fission products could also be removed, the rate of which were dependent on the compositopn of used halide media.…”
Section: Chlorinating Agentmentioning
confidence: 99%
“…Photos of uranium metal fuels and chlorination product: uranium metal pellet (left) and chlorination product (right) [39]. NH 4 Cl was also investigated, recently, by H.C. Eun at al [40] By sparging a Cl 2 and CO gas mixture into a molten halide media, the uranium oxides could be chlorinated [41]. In this chlorination process, the suspended oxides was dissolved in the halide meda and fission products could also be removed, the rate of which were dependent on the compositopn of used halide media.…”
Section: Chlorinating Agentmentioning
confidence: 99%