Removal of Cs, Sr, U and Pu Species from Simulated Nuclear Waste Effluent using Graphene Oxide

Thomas Carey; Christopher D Williams; Daniel J McArthur; Tammie Malkinson; Olivia Thompson; Aliaksandr Baidak; Laura Murtagh; Gyorgyi Glodan; Sean P Morgan; Anthony Banford

doi:10.1007/s10967-018-5931-0

Removal of Cs, Sr, U and Pu Species from Simulated Nuclear Waste Effluent using Graphene Oxide

Thomas Carey, Christopher D Williams, Daniel J McArthur, Tammie Malkinson, Olivia Thompson, Aliaksandr Baidak, Laura Murtagh, Gyorgyi Glodan, Sean P Morgan, Anthony Banford

Dalton Nuclear Institute

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Abstract

This article reports the findings from a series of radioactive experimental trials which have examined the sorption properties of graphene oxide focused on four key radionuclides commonly linked to effluent challenges in the nuclear industry – Cs, Sr, U and Pu. Unlike previous experimental studies, simulated effluent waste solutions were utilised with compositions typical of those found at the Sellafield nuclear site, UK. Molecular dynamics simulations were performed in parallel to elucidate the functional groups to which radionuclides preferentially adsorb.

Original language	English
Pages (from-to)	93-102
Number of pages	10
Journal	Journal of Radioanalytical and Nuclear Chemistry
Volume	317
Issue number	1
Early online date	11 Jun 2018
DOIs	https://doi.org/10.1007/s10967-018-5931-0
Publication status	Published - Jul 2018

Keywords

Graphene Oxide
Nuclear decommissioning
Effluents
Decontamination
Radionuclide Sorption
Ion Exchange

Research Beacons, Institutes and Platforms

Dalton Nuclear Institute

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1007/s10967-018-5931-0

FINAL_JRNC_GO_Article1-1_re-submittedAccepted author manuscript, 1.41 MB

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title = "Removal of Cs, Sr, U and Pu Species from Simulated Nuclear Waste Effluent using Graphene Oxide",

abstract = "This article reports the findings from a series of radioactive experimental trials which have examined the sorption properties of graphene oxide focused on four key radionuclides commonly linked to effluent challenges in the nuclear industry – Cs, Sr, U and Pu. Unlike previous experimental studies, simulated effluent waste solutions were utilised with compositions typical of those found at the Sellafield nuclear site, UK. Molecular dynamics simulations were performed in parallel to elucidate the functional groups to which radionuclides preferentially adsorb.",

keywords = "Graphene Oxide, Nuclear decommissioning, Effluents, Decontamination, Radionuclide Sorption, Ion Exchange",

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T1 - Removal of Cs, Sr, U and Pu Species from Simulated Nuclear Waste Effluent using Graphene Oxide

AU - Carey, Thomas

AU - Williams, Christopher D

AU - McArthur, Daniel J

AU - Malkinson, Tammie

AU - Thompson, Olivia

AU - Baidak, Aliaksandr

AU - Murtagh, Laura

AU - Glodan, Gyorgyi

AU - Morgan, Sean P

AU - Banford, Anthony

PY - 2018/7

Y1 - 2018/7

N2 - This article reports the findings from a series of radioactive experimental trials which have examined the sorption properties of graphene oxide focused on four key radionuclides commonly linked to effluent challenges in the nuclear industry – Cs, Sr, U and Pu. Unlike previous experimental studies, simulated effluent waste solutions were utilised with compositions typical of those found at the Sellafield nuclear site, UK. Molecular dynamics simulations were performed in parallel to elucidate the functional groups to which radionuclides preferentially adsorb.

AB - This article reports the findings from a series of radioactive experimental trials which have examined the sorption properties of graphene oxide focused on four key radionuclides commonly linked to effluent challenges in the nuclear industry – Cs, Sr, U and Pu. Unlike previous experimental studies, simulated effluent waste solutions were utilised with compositions typical of those found at the Sellafield nuclear site, UK. Molecular dynamics simulations were performed in parallel to elucidate the functional groups to which radionuclides preferentially adsorb.

KW - Graphene Oxide

KW - Nuclear decommissioning

KW - Effluents

KW - Decontamination

KW - Radionuclide Sorption

KW - Ion Exchange

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DO - 10.1007/s10967-018-5931-0

M3 - Article

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JO - Journal of Radioanalytical and Nuclear Chemistry

JF - Journal of Radioanalytical and Nuclear Chemistry

IS - 1

ER -

Removal of Cs, Sr, U and Pu Species from Simulated Nuclear Waste Effluent using Graphene Oxide

Abstract

Keywords

Research Beacons, Institutes and Platforms

UN SDGs

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