Solvent extraction systems for mutual separation of Am(III) and Cm(III) from nitric acid solutions. A review of recent state-of-the-art
Системы экстракции растворителями для взаимного разделения Am(III) и Cm(III) из азотнокислых растворов: обзор современного состояния
2020-12-21
SCID: 54.1/eh5964ma
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Am(III)/Cm(III) mutual separationhigh-level liquid wasteminor actinidesnitric acid solutionssolvent extraction
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Abstract (AI)
Americium and curium, present in spent nuclear fuel, are carried forward to the high-level wastes (HLW) upon its reprocessing within the closed nuclear fuel cycle strategy. These minor actinides are required to be extracted efficiently to mitigate the long-term radiotoxicity of the HLW, which in some countries is the proposed strategy for the safe management of radioactive wastes emanating from the reprocessing of spent nuclear fuel. While both Am and Cm are co-extracted by most of extractants used for actinide partitioning and lanthanide-actinide separations, their mutual separation makes Am transmutation less complicated. In their most stable (trivalent) oxidation state, these elements are very difficult to separate. In this review, solvent extraction systems for the mutual separation of Am(III) and Cm(III) from nitric acid solutions are discussed. The extraction systems for the separation of americium directly from high-level liquid waste and from isolated mixtures of americium and curium are considered.Abbreviations: D:distribution ratio, D=CorgCaq, where Corg – total concentration of a metal in the organic phase, Caq – total concentration of a metal in the aqueous phase; DF: decontamination factor, DF=Cx,feed⋅QfeedCx,product⋅Qproduct, where Cx,feed, Cx,product – concentrations of an impurity in the initial feed solution and the product solution (raffinate or back-extract), Qfeed, Qproduct – flow rates of the initial feed solution and the product solution; GW×day/tHM: burn-up of nuclear fuel, where tHM – tons of heavy metal; HAC: high active concentrate; HLW: high level waste; HSAB: Hard and Soft Lewis Acids and Bases; Kex: constant of extraction, for the reaction M3+(aq) + 3NO3−(aq) +nL(org) = M(NO3)3Ln (org), Kex: [M3+][NO3−]3[L]n/[M(NO3)3Ln]; PUREX: Plutonium Uranium Reduction EXtraction; GANEX: Grouped ActiNide EXtraction; REE: rare earth element; SF: separation factor, SF = D1/D2, D1>D2; SNF: spent nuclear fuel; TRLIFS: time-resolved laser induced fluorescence spectrometry; β: constant of complex formation;List of ligands: ADAAM(EH): tetra-(2-ethylhexyldiamide-(2-ethylhexyl)-amine; BTPhen: bis-triazinylphenanthroline; (Cl-Ph)2PS2H: bis-(chlorophenyl)-dithiophosphinic acid; CMPO: Carbamoylmethylphosphine oxide DMDOHEMA: N,N’-dimethyl-N,N’-dioctyl-2-(hexyloxy)ethylmalonamide; DOODa: N,N,N’,N’-tetraalkyl-3,6-dioxaoctanediamide; H2BP18C6: N,N’-bis[(6-carboxy-2-pyridyl)methyl]-1,10-diaza-18-crown-6; H4TPAEN: N,N,N’,N’-tetrakis-[(6-carboxypyridin-2-yl)-ethylenediamine; HDEHP: di-(2-ethylhexyl)phosphoric acid; HEDTA: hydroxyethylethylenediaminetriacetic acid; HEH[EHP]: 2-ethylhexylphosphonic acid; NTAamide: N,N,N,N’,N’,N’-hexaalkylnitrilotriacetamide; PhPyPO: phenyl-pyridine phosphine oxide; TBP: tri-(n-butyl)phosphate; TEDGA: tetraethyldiglycolamide; TEHP: tri-(2-ethylhexyl) phosphate; TODGA: tetraoctyldiglicolamide; TPH: hydrogenated tetrapropyleneList of terms: CHON-principle: An idea that the extractant molecule should consist only of carbon, hydrogen, oxygen and nitrogen atoms, so that the spent ligand can be easily incinerated without the formation of any solid waste. Salting out-agent: An inorganic salt with the same counter-ion as an extracted complex has.Counter-current process: A process in which the solvent and the aqueous feed streams, in contact with each other, flow in opposite directions.
Key Findings
1
Americium and curium are transferred to high-level waste during spent-fuel reprocessing, motivating their efficient extraction to reduce long-term radiotoxicity.
2
Most actinide-partitioning and lanthanide–actinide separation extractants co-extract Am and Cm, making their mutual separation a critical challenge.
3
Selective separation of americium from curium would simplify americium transmutation strategies within closed nuclear fuel-cycle waste management.
4
Separating trivalent Am(III) and Cm(III) is particularly difficult because both elements share their most stable oxidation state and exhibit closely similar chemistry.
5
The review surveys state-of-the-art solvent-extraction systems for separating Am(III) and Cm(III) from nitric acid, covering direct high-level-waste treatment and isolated Am–Cm mixtures.
Research Object
Solvent extraction systems for mutual separation of trivalent americium and curium from nitric acid solutions, including high-level liquid waste and isolated Am–Cm mixtures
Research Subject
Extraction selectivity, separation efficiency, and operating conditions governing the mutual separation of Am(III) and Cm(III)
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2020-12-21
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