Effective separation of Am(III) and Cm(III) using a DGA resin via the selective oxidation of Am(III) to Am(V)

Kazi, Zakir H.; Guérin, Nicolas; Christl, Marcus; Totland, Marina; Gagné, Alexandre; Burrell, Sean

doi:10.1007/s10967-019-06571-0

Cited by 14 publications

(11 citation statements)

References 23 publications

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Section: Resultsmentioning

confidence: 99%

“…We consider that the potential limitation of a small presence of 243 Am in the SFP water would not significantly affect the for 243 Cm calculated using this method. However, further work could explore implementing the separation of Am and Cm for their measure in separate fractions, as, for example, seems effective by oxidizing Am(III) to Am(V) using 0.01 M AgNO 3 …”

Section: Resultsmentioning

confidence: 99%

“…However, further work could explore implementing the separation of Am and Cm for their measure in separate fractions, as, for example, seems effective by oxidizing Am(III) to Am(V) using 0.01 M AgNO 3 . 15 Assessment of the Cm Chronometry Technique. The identification of Cm in the samplers and the calculated time of the retirement of a leaking fuel rod(s) from the neutron flux were blindly presented to colleagues at the nuclear facility where we deployed the samplers.…”

Section: G C Smentioning

confidence: 99%

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Passive Sampling Tool for Actinides in Spent Nuclear Fuel Pools

et al. 2022

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Spent nuclear fuel must be carefully managed to prevent pollution of the environment with radionuclides. Within the framework of correct radioactive waste management, spent fuel rods are stored in cooling pools to allow short-lived fission products to decay. If fuel rods leak, they liberate radionuclides into the cooling water; therefore, it is essential to determine radionuclide concentrations in the pool water for monitoring purposes and to plan the decommissioning process. In this work, we present, to our knowledge, the first passive sampling technique for measures of actinides in spent nuclear fuel pools, based on recently developed diffusive gradients in thin-film (DGT) configurations. These samplers eliminate the need to retrieve and handle large samples of fuel pool water for radiochemical processing by immobilizing their targeted radionuclides in situ on the solid phase within the sampler. This is additionally the first application of the DGT technique for Cm measure. Herein, we make the calibrated effective diffusion coefficients of U, Pu, Am, and Cm in borated spent fuel pool water available. We tested these samplers in the fuel pool of a nuclear facility and measured samples using accelerator mass spectrometry to provide high-precision isotopic reports, allowing for the first independent implementation of a recently developed technique for dating nuclear fuel based on its Cm isotope signature.

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Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

Section: G C Smentioning

confidence: 99%

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Passive Sampling Tool for Actinides in Spent Nuclear Fuel Pools

et al. 2022

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“…Therefore, DGA Resin has been applied, first and foremost, for analyte/matrix separation in the nuclear isotopic analysis. Applications include the separation of radioactive isotopes of Sr [4,5], Y [6], Po [7], Ac [8], Pu [9][10][11], Am [12], and Cm [13]. The beneficial features and characteristics of DGA Resin are also applicable for analyte/matrix separation of stable isotopes in the fields of geochemical, archaeological, environmental, and biomedical sciences.…”

Section: Introductionmentioning

confidence: 99%

Assessing the potential of online ICP–MS analysis to optimize Ca/matrix separation using DGA Resin for subsequent isotopic analysis

et al. 2021

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Ca isotopes have gained increasing interest as a diagnostic tool for bone diseases due to the variations in abundances as a consequence of changes in bone-mineral balance. Optimized Ca/matrix separation prior to analysis is a prerequisite for reliable isotope ratio measurements in complex biological matrices such as blood, serum, or urine. The online analysis of analyte/matrix separation by ICP-MS enables direct assessment of elution profiles supporting the optimization process. The integration of transient signals and signal suppression challenge the quantification and interpretation of the elution profiles. Mn and Co remain unretained by the DGA Resin (TrisKem International) from nitric acid. Hence, in the present study, these elements were investigated for their application as standards to monitor signal suppression. Successful analyte quantification was accomplished using a dynamic correction strategy applying a linear gradient of a suppression factor based on Mn and Co intensities. An optimized Ca/matrix separation procedure using DGA Resin is proposed based on the results during online ICP-MS analysis. Graphic abstract

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“…There have been numerous reports on the separation of Am/Cm and other transuranic elements utilizing the oxidation strategy in the past decades. − For example, Holcomb investigated the separation of Am(VI) from Cm(III) by a calcium fluoride column early in the 1960s . Burns et al prepared Am(V) in a nitric acid solution by sulfate radical oxidation and performed its separation from Cm(III) by ion exchange with metal(IV)-pillared phosphate phosphonate inorganic organic hybrid materials, which led to an Am/Cm separation factor of 20 at the highest .…”

mentioning

confidence: 99%

Separation of Americium from Curium through Oxidation State Control with Record Efficiency

et al. 2022

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Separation of americium (Am) from curium (Cm) could greatly facilitate the development of advanced nuclear fuel cycles, help with accurate nuclear forensic analysis, and allow for more efficient recovery and utilization of the two strategic elements. In this work, an Am/Cm separation strategy based on the stabilization of pentavalent Am in a biphasic solvent extraction system using bismuthate as the oxidant and N,N,N′,N′-tetraoctyl diglycolamide (TODGA) as the extractant was developed. The distinctive differences between Am(V) and Cm(III) in terms of both steric configuration and charge density afford record high Cm/Am separation factors (>10 4 ) through only one single contact in solvent extraction. This separation strategy possesses superior features including fast kinetics, long-time stability, no secondary solid radioactive waste generation, and applicability over a wide range of HNO 3 acidities, making it promising for Am/Cm separation and analysis in a variety of applications.

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Effective separation of Am(III) and Cm(III) using a DGA resin via the selective oxidation of Am(III) to Am(V)

Cited by 14 publications

References 23 publications

Passive Sampling Tool for Actinides in Spent Nuclear Fuel Pools

Passive Sampling Tool for Actinides in Spent Nuclear Fuel Pools

Assessing the potential of online ICP–MS analysis to optimize Ca/matrix separation using DGA Resin for subsequent isotopic analysis

Separation of Americium from Curium through Oxidation State Control with Record Efficiency

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