2012
DOI: 10.1016/j.jhazmat.2012.09.072
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Uranium extraction from TRISO-coated fuel particles using supercritical CO2 containing tri-n-butyl phosphate

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Cited by 16 publications
(9 citation statements)
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“…Once the fuel kernels are exposed, methods of extracting the fissile materials include traditional aqueous digestion, supercritical CO 2 solvent extraction (as the carrier for an appropriate extractant), and molten salt dissolution. [628][629][630][631][632][633][634][635][636][637][638]…”
Section: Processes Applied To Triso-type Fuelsmentioning
confidence: 99%
“…Once the fuel kernels are exposed, methods of extracting the fissile materials include traditional aqueous digestion, supercritical CO 2 solvent extraction (as the carrier for an appropriate extractant), and molten salt dissolution. [628][629][630][631][632][633][634][635][636][637][638]…”
Section: Processes Applied To Triso-type Fuelsmentioning
confidence: 99%
“…In recent years, a more and more attention has been paid to the separation and purification of metal ions through supercritical fluid extraction (SFE) [1,2]. The potential of CO 2 as a solvent for SFE is interesting as it is nontoxic, nonflammable, abundantly available, and recyclable, minimizing the problems associated with waste liquid [3,4].…”
Section: Introductionmentioning
confidence: 99%
“…Moreover, small amounts of a co-solvent are known to increase the polarity of fluids as well as enhance the recovery of specific metal species. The introduction of co-solvents with Sc-CO 2 can not only simplify the subsepuent metal recovery process (when compared to conventional processes), but also cause a reduction in reagent consumption [13]. Therefore, Sc-CO 2 extraction has become a promising technology for the recovery of metal ions from environmental samples.…”
Section: Introductionmentioning
confidence: 99%
“…Several studies have been reported on SFE of actinides and lanthanides with TBP·HNO 3 adduct from various matrices viz. assorted radioactive waste matrices and spent nuclear fuels from different nuclear reactors (Shadrin et al, 2008;Zhu et al, 2012;Shamsipur et al, 2001;Shimada et al, 2006). Uranium present in spent nuclear fuel has been selectively recovered with good separation factors from fission products by SFE followed by counter current chromatographic separation (Myasoedov et al, 2009).…”
Section: Introductionmentioning
confidence: 99%