Assessing sample attenuation parameters for use in low-energy efficiency transfer in gamma-ray spectrometry

Bruggeman, M.; Verheyen, Leen; Vidmar, T.; Liu, B.

doi:10.1016/j.apradiso.2015.11.077

Cited by 4 publications

(3 citation statements)

References 10 publications

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“…Huy and Luyen, 2005;Aguiar et al, 2006;Khater and Ebaid, 2008) is combined with Monte Carlobased model work (e.g. Huy et al, 2013;Bruggeman et al, 2016).…”

Section: Correcting Self-absorptionmentioning

confidence: 99%

Technical note: Quantifying uranium-series disequilibrium in natural samples for dosimetric dating – Part 1: gamma spectrometry

2022

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Abstract. Dosimetric dating techniques rely on accurate and precise determination of environmental radioactivity. Gamma spectrometry is the method of choice for determining the activity of 238U, 232Th, and 40K. With the aim to standardize gamma-spectrometric procedures for the purpose of determining accurate parent nuclide activities in natural samples, we outline the basics of gamma spectrometry and practical laboratory procedures here. This includes gamma radiation and instrumentation, sample preparation, finding the suitable measurement geometry and sample size for a given detector, and using the most suitable energy peaks in a gamma spectrum. The issue of correct efficiency calibration is highlighted. The procedures outlined are required for estimating contemporary parent nuclide activity. For estimating changing activities during burial specific data analyses are required, and these are also highlighted.

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“…Huy and Luyen, 2005;Aguiar et al, 2006;Khater and Ebaid, 2008) is combined with Monte Carlobased model work (e.g. Huy et al, 2013;Bruggeman et al, 2016).…”

Section: Correcting Self-absorptionmentioning

confidence: 99%

Technical note: Quantifying uranium-series disequilibrium in natural samples for dosimetric dating – Part 1: gamma spectrometry

2022

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“…Huy and Luyen, 2005;Aguiar et al, 2006;Khater and 295 Ebaid, 2008;Kaminski et al, 2014;Barrera et al, 2017), each employing a slightly different method depending on available tools in the respective laboratory. Often, experimental work (e.g., Huy and Luyen, 2005;Aguiar et al, 2006;Khater and Ebaid, 2008) is combined with Monte Carlo-based model work (e.g., Huy et al, 2013;Bruggeman et al, 2016).…”

Section: Correcting Self-absorptionmentioning

confidence: 99%

Technical note: Quantifying Uranium-series disequilibrium in natural samples for dosimetric dating – Part 1: gamma spectrometry

Mauz

Nolan

Appleby

2021

Preprint

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Abstract. Dosimetric dating techniques rely on accurate and precise determination of environmental radioactivity. Gamma spectrometry is the method of choice for determining the activity of 238U, 232Th and 40K. With the aim to standardise gamma-spectrometric procedures for the purpose of determining accurate parent nuclide activities in natural samples, we outline here basics of gamma spectrometry and practical laboratory procedures. This includes gamma radiation and instrumentation, sample preparation, finding the suitable measurement geometry and sample size for a given detector and using the most suitable energy peaks in a gamma spectrum. The issue of correct efficiency calibration is highlighted. The procedures outlined are required for estimating contemporary parent nuclide activity. For estimating changing activities during burial specific data analyses are required and these are also highlighted.

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“…In the gamma-ray spectrometry field, except the simulations performed for the calculation of the detection efficiencies, Monte Carlo simulation codes can also be used to evaluate the transfer factors [5]. Based on its relative sensitivity to the uncertainties of the detector parameters and of the calculation model, the method of efficiency transfer [6,7], based on Monte Carlo simulation or on semi-empirical methods [6,8,9], is more and more relevant to evaluate the efficiency whenever direct experimental calibration is not accessible [10].…”

Section: Efficiency Transfer In Gamma-ray Spectrometrymentioning

confidence: 99%

Dedicated Monte Carlo Procedures Applied in Gamma-ray Spectrometry Used in Decommissioning of Nuclear Facilities

Gurau¹

2016

Nuclear Material Performance

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Because the experimental efficiency calibration is limited to several measurement geometries and cannot be applied directly to all measurement configurations, the efficiency transfer method for the efficiency computation was applied using ETNA software. An approach using efficiencies measured with point sources combined with theoretical procedures was applied for obtaining the peak efficiency ε(E) for disk sources measured with a NaI(Tl) detector. The transfer method was applied for the computation of the efficiency of an HPGe detector using as a reference a point source placed at 10 cm height from the face of the detector. The method was applied both for point sources and volume sources with varied compositions and densities. To correct the experimental values of the efficiencies, coincidence summing effects were evaluated using GESPECOR Monte Carlo code. The study of the response function characterization of the ISOCART and Segmented Gamma Scanner WS1100 gamma-ray spectrometry systems was related. GEANT 3.21 Monte Carlo code was used to simulate the spectra expected to be obtained for the photon energy range from 50 to 2000 keV. A big volume represented by a 220l cylindrical source was considered to be measured with the two systems. The full energy peak efficiency and the total efficiency were evaluated.

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Assessing sample attenuation parameters for use in low-energy efficiency transfer in gamma-ray spectrometry

Cited by 4 publications

References 10 publications

Technical note: Quantifying uranium-series disequilibrium in natural samples for dosimetric dating – Part 1: gamma spectrometry

Technical note: Quantifying uranium-series disequilibrium in natural samples for dosimetric dating – Part 1: gamma spectrometry

Technical note: Quantifying Uranium-series disequilibrium in natural samples for dosimetric dating – Part 1: gamma spectrometry

Dedicated Monte Carlo Procedures Applied in Gamma-ray Spectrometry Used in Decommissioning of Nuclear Facilities

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