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Ion sieving in graphene oxide membrane enables efficient actinides/lanthanides separation. Nat Commun 2023; 14:261. [PMID: 36650148 PMCID: PMC9845371 DOI: 10.1038/s41467-023-35942-1] [Citation(s) in RCA: 13] [Impact Index Per Article: 13.0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 07/29/2022] [Accepted: 01/09/2023] [Indexed: 01/19/2023] Open
Abstract
Separation of actinides from lanthanides is of great importance for the safe management of nuclear waste and sustainable development of nuclear energy, but it represents a huge challenge due to the chemical complexity of these f-elements. Herein, we report an efficient separation strategy based on ion sieving in graphene oxide membrane. In the presence of a strong oxidizing reagent, the actinides (U, Np, Pu, Am) in a nitric acid solution exist in the high valent and linear dioxo form of actinyl ions while the lanthanides (Ce, Nd, Eu, Gd, etc.) remain as trivalent/tetravalent spheric ions. A task-specific graphene oxide membrane with an interlayer nanochannel spacing between the sizes of hydrated actinyl ions and lanthanides ions is tailored and used as an ionic cut-off filter, which blocks the larger and linear actinyl ions but allows the smaller and spheric lanthanides ions to penetrate through, affording lanthanides/actinides separation factors up to ~400. This work realizes the group separation of actinides from lanthanides under highly acidic conditions by a simple ion sieving strategy and highlights the great potential of utilizing graphene oxide membrane for nuclear waste treatment.
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Study on the α-ray radiolysis product of hydroxysemicarbazide. J Radioanal Nucl Chem 2022. [DOI: 10.1007/s10967-021-08148-2] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Hu Y, Lu C, Chen Q, Liu Y, Zhou Y, Jiao C, Zhang M, Hou H, Gao Y, Tian G. Pertraction of Nd(III) and U(VI) Through Flat Sheet Supported Liquid Membrane Containing N, N’-Dimethyl-N, N’-Dioctyl-3-Oxadiglcolamide as Carrier. SOLVENT EXTRACTION AND ION EXCHANGE 2021. [DOI: 10.1080/07366299.2021.1914910] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
Affiliation(s)
- Yifu Hu
- Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University, Harbin, China
| | - Chuan Lu
- Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, China
| | - Qi Chen
- Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University, Harbin, China
| | - Yaoyang Liu
- Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University, Harbin, China
| | - Yu Zhou
- Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University, Harbin, China
| | - Caishan Jiao
- Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University, Harbin, China
| | - Meng Zhang
- Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University, Harbin, China
| | - Hongguo Hou
- Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University, Harbin, China
| | - Yang Gao
- Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University, Harbin, China
| | - Guoxin Tian
- Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University, Harbin, China
- Department of Radiochemistry, China Institute of Atomic Energy, Beijing, China
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High efficiency biosorption of Uranium (VI) ions from solution by using hemp fibers functionalized with imidazole-4,5-dicarboxylic. J Mol Liq 2020. [DOI: 10.1016/j.molliq.2019.111739] [Citation(s) in RCA: 16] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 01/17/2023]
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Yadav KK, Singh D, Kain V. Separation of terbium from aqueous phase employing hollow fibre supported liquid membrane with EHEHPA as carrier. SEP SCI TECHNOL 2019. [DOI: 10.1080/01496395.2018.1541471] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Submit a Manuscript] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
Affiliation(s)
- Kartikey K. Yadav
- Rare Earths Development Section, Material’s Processing & Corrosion Engineering Division, Bhabha Atomic Research Centre, Mumbai, India
| | - D.K. Singh
- Rare Earths Development Section, Material’s Processing & Corrosion Engineering Division, Bhabha Atomic Research Centre, Mumbai, India
| | - V. Kain
- Rare Earths Development Section, Material’s Processing & Corrosion Engineering Division, Bhabha Atomic Research Centre, Mumbai, India
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Vats BG, Pius IC, Noronha DM, Kannan S. A novel approach for extraction of plutonium and americium from aqueous complexing media. J Radioanal Nucl Chem 2018. [DOI: 10.1007/s10967-018-5857-6] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
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Preparation of halloysite@graphene oxide composite and its application for high-efficient decontamination of U(VI) from aqueous solution. J Mol Liq 2016. [DOI: 10.1016/j.molliq.2016.04.057] [Citation(s) in RCA: 25] [Impact Index Per Article: 3.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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The synergistic extraction of uranium ions from monazite leach solution via HFSLM and its mass transfer. J IND ENG CHEM 2016. [DOI: 10.1016/j.jiec.2015.10.006] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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9
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Mass transfer and selective separation of neodymium ions via a hollow fiber supported liquid membrane using PC88A as extractant. J IND ENG CHEM 2015. [DOI: 10.1016/j.jiec.2014.03.016] [Citation(s) in RCA: 21] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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10
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Vernekar PV, Jagdale YD, Sharma AD, Patwardhan AW, Patwardhan AV, Ansari SA, Mohapatra PK. Simultaneous Extraction of Neodymium and Uranium using Hollow Fiber Supported Liquid Membrane. SEP SCI TECHNOL 2014. [DOI: 10.1080/01496395.2014.890628] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Submit a Manuscript] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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11
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Sunsandee N, Ramakul P, Hronec M, Pancharoen U, Leepipatpiboon N. Mathematical model and experimental validation of the synergistic effect of selective enantioseparation of (S)-amlodipine from pharmaceutical wastewater using a HFSLM. J IND ENG CHEM 2014. [DOI: 10.1016/j.jiec.2013.08.008] [Citation(s) in RCA: 14] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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12
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Mahanty BN, Raut DR, Mohapatra PK, Das DK, Behere PG, Afzal M. Comparative evaluation of actinide ion uptake by polymer inclusion membranes containing TODGA as the carrier extractant. JOURNAL OF HAZARDOUS MATERIALS 2014; 275:146-153. [PMID: 24857898 DOI: 10.1016/j.jhazmat.2014.04.059] [Citation(s) in RCA: 16] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Received: 12/04/2013] [Revised: 04/25/2014] [Accepted: 04/27/2014] [Indexed: 06/03/2023]
Abstract
Polymer inclusion membranes (PIM) containing TODGA (N,N,N',N'-tetra-n-octyl diglycolamide) were evaluated for the separation of actinide ions such as Am(3+), Pu(4+), UO2(2+) and Th(4+) from acidic feeds. The PIMs were prepared using cellulose triacetate (CTA) as the polymer matrix and 2-nitrophenyloctyl ether (NPOE) as the plasticizer along with the diglycolamide carrier extractants and were characterized by conventional techniques such as XRD, thermal analysis and AFM. The PIM composition was optimized by a series of studies which involved variation in the CTA, NPOE and carrier concentration which suggested 58% TODGA, 30% NPOE and 12% CTA to be optimum. The uptake studies were carried out using feed solutions containing varying concentrations of nitric acid and showed the trend: Am(3+)>Pu(4+)>Th(4+)>UO2(2+). Transport studies were carried out in a two-compartment cell where nitric acid concentration the feed was varied (1-3M) while the receiver compartment contained alpha-hydroxy-iso-butyric acid (AHIBA). The actinide ion transport efficiencies with TODGA containing PIMs followed the same trend as seen in the uptake studies. The AFM patterns of the PIMs changed when loaded with Eu(3+) carrier (used as a surrogate for Am(3+)) while the regenerated membranes have displayed comparable morphologies. Diffusion coefficient values were experimentally obtained from the transport studies and were found to be 8.89×10(-8) cm(2)/s for Am(3+) transport.
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Affiliation(s)
- B N Mahanty
- Advanced Fuel Fabrication Facility, Bhabha Atomic Research Centre, Tarapur, Maharashtra, 401502, India
| | - D R Raut
- Radiochemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai, 400085, India
| | - P K Mohapatra
- Radiochemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai, 400085, India.
| | - D K Das
- Advanced Fuel Fabrication Facility, Bhabha Atomic Research Centre, Tarapur, Maharashtra, 401502, India
| | - P G Behere
- Advanced Fuel Fabrication Facility, Bhabha Atomic Research Centre, Tarapur, Maharashtra, 401502, India
| | - Md Afzal
- Advanced Fuel Fabrication Facility, Bhabha Atomic Research Centre, Tarapur, Maharashtra, 401502, India
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Patil AB, Kandwal P, Shinde V, Pathak P, Mohapatra P. Evaluation of DMDOHEMA based supported liquid membrane system for high level waste remediation under simulated conditions. J Memb Sci 2013. [DOI: 10.1016/j.memsci.2013.04.019] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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