Solid-phase extraction of 225Ac using ion-imprinted resin and 243Am as a radioactive tracer for internal dosimetry and incorporation measurements

Cusnir, Ruslan; Froidevaux, Pascal; Carbonez, Pierre; Straub, Marietta

doi:10.1016/j.aca.2021.339421

Cited by 4 publications

(2 citation statements)

References 32 publications

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“…The linear temporal uptake of the actinides by the fully assembled KMS-1 and IIP-Y 3+ DGT samplers has previously been demonstrated . Additionally, the adsorbent functionalities of the KMS-1 and IIP-Y 3+ resins used in the DGT resin gels have been shown to be effective at both lower and higher pH than the BASS solution. − This also offers the reassurance that the KMS-1 resin will not break down and potentially liberate ions such as sulphates and chlorides into the SFP water.…”

Section: Resultsmentioning

confidence: 90%

“…Deriving dbl δ from the c DGT calculated from the samplers with different thicknesses as described by Warnken et al 14 can indicate whether stagnant conditions in the SFP water have enlarged the dbl δ in front of the DGT device during deployment, allowing g Δ and therefore c DGT to be further finetuned as a function of the conditions in the specific SFP. We also note that different nuclear facilities may use boron enriched in 11 B in order to reduce the concentration of boric acid required in the SFP. If the H 3 BO 3 concentration is significantly different than that used in this work, further calibration of D in BASS at the relevant concentration using a diffusion cell may increase the accuracy of the calculated c DGT .…”

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: 90%

Section: G C Smentioning

confidence: 99%

Passive Sampling Tool for Actinides in Spent Nuclear Fuel Pools

et al. 2022

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Actinium-225 as an example for monitoring of internal exposure of occupational intakes of radionuclides in face of new nuclear-medical applications for short-lived alpha emitting particles

Hartmann,

Taubner,

Vogt

et al. 2024

Radiat Environ Biophys

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Monitoring of internal exposure to short-lived alpha-emitting radionuclides such as actinium-225 (225Ac), which are becoming increasingly important in nuclear medicine, plays an important role in the radiation protection of occupationally exposed persons. After having tested gamma spectrometry, liquid scintillation counting and alpha spectrometry for monitoring of internal exposure, the focus of the present study was on solid phase extraction of 225Ac from urine in combination with alpha spectrometry. The development of the method was based on recent findings from the literature on this topic. The method was used in a pilot phase to monitor internal exposure of four workers who were directly or indirectly involved in the manufacture and/or use of 225Ac. The monitoring protocol allowed a relatively short 24-hour urine sample analysis with excellent recovery of the internal standard, but it did not allow for a detection limit of less than 1 mBq nor a sufficient yield of 225Ac. Based on these results it is concluded that an in vitro excretion analysis alone is not appropriate for monitoring internal exposure to 225Ac. Instead, different radiation monitoring techniques have to be combined to ensure the radiation protection of employees.

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