2018
DOI: 10.1007/s10967-018-5853-x
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Am, Cm recovery from genuine HLLW by extraction chromatography

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Cited by 16 publications
(11 citation statements)
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“…The value of C/C0 above 1 must be elution of elements from CMPO/SiO2-P as a result of competitive adsorption of cations. Ba(II), Sr(II) and Ru(III) were not adsorbed by CMPO/SiO2-P, and these results reasonably agree with the previous report 2 . RE(III)-Y(III), La(III), Ce(III), Nd(III), Sm(III) and Eu(III)were adsorbed by the column, and they showed breakthrough at V = 2 BV, where breakthrough of this paper means 5 % breakthrough.…”
Section: Resultssupporting
confidence: 93%
See 1 more Smart Citation
“…The value of C/C0 above 1 must be elution of elements from CMPO/SiO2-P as a result of competitive adsorption of cations. Ba(II), Sr(II) and Ru(III) were not adsorbed by CMPO/SiO2-P, and these results reasonably agree with the previous report 2 . RE(III)-Y(III), La(III), Ce(III), Nd(III), Sm(III) and Eu(III)were adsorbed by the column, and they showed breakthrough at V = 2 BV, where breakthrough of this paper means 5 % breakthrough.…”
Section: Resultssupporting
confidence: 93%
“…Minor actinides (MA(III): Am(III) and Cm(III)) contained in the HLLW are known to be long-lived and/or heat-generating nuclides, and those are desirable to be removed in order to reduce potential hazard of the vitrified radioactive waste. Japan Atomic Energy Agency (JAEA) has been conducting research and development of the extraction chromatography technology for establishing MA(III) recovery process 1,2 . In this technology, MA(III) is recovered from the HLLW through adsorption/elution reactions between the cations with adsorbent packed in a column.…”
Section: Introductionmentioning
confidence: 99%
“…Those processes require diluent for organic extractants, and large amount of secondary waste is suspected to be generated. As an alternative to the solvent extraction, the extraction chromatography technology is promising 6) and Japan Atomic Energy Agency has been con-ducting fundamental studies for the implementation [7][8][9][10][11] .…”
Section: Introductionmentioning
confidence: 99%
“…Some reprocessing plants have already been commercialized for recovering U and Pu from spent nuclear fuel, and numerous studies on partitioning and transmutation of long-lived radioactive nuclides have been conducted globally [1]. In these studies, several researchers have reported the recovery process of long-lived radioactive nuclides by silica-based adsorbents [2][3][4][5][6][7][8][9][10][11][12][13]. Wei et al developed silica-based adsorbents by impregnating an organic extractant into a styrenedivinylbenzene (SDB) copolymer, which is immobilized in porous silica particles [2].…”
Section: Introductionmentioning
confidence: 99%
“…Koma et al assessed the adsorption/elution ability, durability, and after-treatment of several SiO 2 -P adsorbents with different extractants, and the combination of TODGA/SiO 2 -P and R-BTP/SiO 2 -P adsorbents was evaluated as the primary candidate for MA(III) recovery from HLLW [11]. Based on this assessment, MA(III) recovery trials from genuine HLLW were conducted using columns packed with TODGA/SiO 2 -P and R-BTP/SiO 2 -P adsorbents, and the recovery yields of MA(III) and decontamination factors (DF) of other FPs were obtained [12,13]. These previous studies showed that long-lived radioactive nuclides in HLLW could be separated and recovered quantitatively by SiO 2 -P adsorbents impregnated with suitable extractants; however, improvements and optimizations of adsorbents are required for higher recovery yields and DF with less eluent.…”
Section: Introductionmentioning
confidence: 99%