Comparisons organized by Ionizing Radiation Metrology Laboratory of FTMC, Lithuania

Gudelis, A.; Gorina, I.

doi:10.1016/j.apradiso.2015.11.011

Cited by 2 publications

(2 citation statements)

References 9 publications

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“…Quality control procedures for this detector and the results from proficiency test schemes are previously described [ 23 ]. Certified reference radionuclide solutions traceable to the national standard of activity were used for efficiency calibration [ 24 ]. True coincidence-summing corrections were applied to the 60 Co activity measurement.…”

Section: Experimental Equipment and Analysis Methodsmentioning

confidence: 99%

Rapid analysis method for the determination of 14C specific activity in irradiated graphite

et al. 2018

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14C is one of the limiting radionuclides used in the categorization of radioactive graphite waste; this categorization is crucial in selecting the appropriate graphite treatment/disposal method. We propose a rapid analysis method for 14C specific activity determination in small graphite samples in the 1–100 μg range. The method applies an oxidation procedure to the sample, which extracts 14C from the different carbonaceous matrices in a controlled manner. Because this method enables fast online measurement and 14C specific activity evaluation, it can be especially useful for characterizing 14C in irradiated graphite when dismantling graphite moderator and reflector parts, or when sorting radioactive graphite waste from decommissioned nuclear power plants. The proposed rapid method is based on graphite combustion and the subsequent measurement of both CO2 and 14C, using a commercial elemental analyser and the semiconductor detector, respectively. The method was verified using the liquid scintillation counting (LSC) technique. The uncertainty of this rapid method is within the acceptable range for radioactive waste characterization purposes. The 14C specific activity determination procedure proposed in this study takes approximately ten minutes, comparing favorably to the more complicated and time consuming LSC method. This method can be potentially used to radiologically characterize radioactive waste or used in biomedical applications when dealing with the specific activity determination of 14C in the sample.

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Section: Experimental Equipment and Analysis Methodsmentioning

confidence: 99%

Rapid analysis method for the determination of 14C specific activity in irradiated graphite

et al. 2018

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“…These techniques allow for determining the detection efficiency of a particular sample and for converting the count rate (CPM) to the disintegration rate (DPM). In our study, the quench curves were obtained from a set of 10 quenched tritium standards containing constant tritium activity (222,540 Bq) with varying levels of quenching using the TDCR method for Hidex 600SL (Gudelis et al, 2017) and the SCR method (L'Annunziata et al, 2020) in the selected counting windows of 1-175 and 176-350 channels for Quantulus 1220. Figure 2(a) shows the quench curve for tritium, which shows a correlation between the TDCR value and the counting efficiency, which is a second-order polynomial curve given by the equation y=-0.5856x 2 +1.5468x-0.098 (R 2 =0.9993), where x is the TDCR value and y is the counting efficiency.…”

Section: Quench Curve Generationmentioning

confidence: 99%

Low-Level Tritium Measurement in Tap Water in Bangkok Area and Annual Dose Estimation

Sudprasert

Phattanasub²,

Srimork³

et al. 2022

Environ. Nat. Resour. J.

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Monitoring of tritium concentration in tap water is an essential tool to determine the effective dose received from tap water. Liquid scintillation counting (LSC) is a widely used technique for determining tritium in water. Due to the very low activity of tritium in tap water, its detection requires a high-efficiency LSC with the lowest minimum detectable activity (MDA). Low-level tritium analysis in tap water were performed in two LSC models using conventional distillation techniques. The optimal conditions with the lowest MDAs were applied to determine the tritium concentration in the tap water distributed from two main sources located in the Bangkok metropolitan region: Bang Khen and Maha Sawat water treatment plants (WTPs). Twenty-six tap water samples were collected from petrol stations located around both water treatment plants. The results revealed that the amount of tritium in the tap water around the Bangkhen WTP was between 1.88-2.63 Bq/L with an average of 2.28±0.28 Bq/L, whereas those from the Maha Sawat WTP were between 2.01-2.69 Bq/L with an average of 2.44±0.26 Bq/L, which are far below the World Health Organization’s (WHO) guideline limit (10,000 Bq/L) for drinking water. The annual effective dose (AED) for infants, children and adults obtained from tap water samples around the Bangkhen WTP were 0.010, 0.014, and 0.030 µSv/year, respectively, and those from the Maha Sawat WTP were 0.011, 0.015, and 0.032 µSv/year, respectively, which are far below the WHO’s guideline limit (100 µSv/year).

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Comparisons organized by Ionizing Radiation Metrology Laboratory of FTMC, Lithuania

Cited by 2 publications

References 9 publications

Rapid analysis method for the determination of 14C specific activity in irradiated graphite

Rapid analysis method for the determination of 14C specific activity in irradiated graphite

Low-Level Tritium Measurement in Tap Water in Bangkok Area and Annual Dose Estimation

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