Performance revaluation of a N-type coaxial HPGe detector with front edges crystal using MCNPX

Azli, Tarek; Chaoui, Zine-El-Abidine

doi:10.1016/j.apradiso.2014.12.027

Cited by 26 publications

(6 citation statements)

References 24 publications

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“…Discrepancies in the low energy region have also been reported for both Marinelli geometries and point sources in the literature (Ródenas et al, 2003;Huy, 2011;Britton et al, 2013). The photon energy of 59.54 keV is insufficient to reach the crystal just through the detector's outer top dead layer, but the photon energy of 662 keV is sufficient to reach both the outer lateral and inner dead layers of the crystal (Azli & Chaoui, 2015). At energies above 122.06 keV, the results of both GESPECOR (Table 3) and PHITS MC (Table 4) codes are in good agreement with experimental efficiencies with a maximum deviation of 2 % and 2.8 % respectively, at 1.5 mm dead layer.…”

Section: Resultsmentioning

confidence: 81%

“…The FEPE curve is affected the sample geometry, the sample matrix, and the density of the matrix as well as the detection system (Harb et al, 2008). The FEPE curve can be obtained either by using a known radioactive standard source homogeneously distributed in a Marinelli beaker of the same size and composition (Vasconcelos et al, 2011), or by accurately modeling the source geometry, matrix, the position of the source, and the detection system using MC-based simulations (Azli & Chaoui, 2015;Lépy et al, 2019). Using the Monte Carlo method, the detection process can be simulated and applied to obtain efficiency values for each geometry (Ródenas et al, 2003).…”

Section: Introductionmentioning

confidence: 99%

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Comparison of Experimental and Monte Carlo Efficiencies of 0.5g/cc Epoxy Matrix Marinelli Source with Multiple Radioactive Nuclides

Aksoy¹,

Ünlü²,

ORHAN>³

et al. 2022

Gazi University Journal of Science Part A: Engineering and Innovation

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Using the gamma spectroscopy system, it can be determined whether environmental samples or standard radioactive sources are radioactive, and from which elements their radioactivity originates. The purpose of Monte Carlo (MC) simulation is to model a real-life system with its inputs and evaluate the outputs with real results. This study calculates the experimental efficiency of a p-type HPGe detector using a 0.5 g/cc Epoxy Matrix Marinelli beaker and compares these results with GESPECOR and PHITS MC Simulation programs. Thus, the thickness of the dead layer, which thickens over time and affects the detector efficiency, was determined from the most compatible result of the MC calculations made repeatedly at various alternative thicknesses to the experimental results. For 1.5 mm dead layer thickness, less than 2 % error was found between the test and MC results, especially at energies above 165 keV. As a result, it was determined that the dead layer thickness of the detector reached 1.5 mm with an increase of 114 % after its production. The current value of the dead layer thickness of each detector should be checked, as the efficiency affects the determination of the activity.

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Section: Resultsmentioning

confidence: 81%

Section: Introductionmentioning

confidence: 99%

Comparison of Experimental and Monte Carlo Efficiencies of 0.5g/cc Epoxy Matrix Marinelli Source with Multiple Radioactive Nuclides

Aksoy¹,

Ünlü²,

ORHAN>³

et al. 2022

Gazi University Journal of Science Part A: Engineering and Innovation

View full text Add to dashboard Cite

show abstract

“…Because detector simulation is mainly based on information provided by the manufacturer [4]. If the manufacturer gives the detector parameters missing, the accuracy of the simulations is directly affected [5][6][7]. The accuracy of the simulation results depends on adequate input data and the accuracy of the various approaches applied in the physical model [8].…”

Section: Introductionmentioning

confidence: 99%

Evaluation of the Central Copper Contact Pin Effect in High-Energy Region in Gamma-ray Spectrometry

Uyar

2024

Cumhuriyet Science Journal

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The detector must be modeled in the most accurate way when Monte Carlo simulation method is used for efficiency calculation in gamma-ray spectrometric studies. This study aims to investigate the effect of the copper contact pin inside the detector on the efficiency of the HPGe detector for high gamma-ray energies. Simulated efficiencies were determined for 6 different energies in the energy range of 1460.8 keV up to 2614.5 keV in point and cylindrical source geometry. According to the modeling using PHITS Monte Carlo simulation code, the presence of copper contact pin at high gamma-ray energies caused a decrease of up to 6% in detector efficiency. It was emphasized that this ignored parameter should be included in the modeling like all other geometric parameters used in detector modeling, by showing the effect on the efficiency.

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“…For example, Ordonez et al in order to obtain a statistical error of less than 1.5%, they set the number of histories in each simulation at 20 million (Ordóñez et al, 2019). Azli & Chaoui (2015) used 100 million particles to achieve a relative error of less than 1% in the calculated efficiency. Subercaze et al (2022) used 3 million and Miroslav et al used 1 million particles in their study (Ješkovský et al, 2019).…”

Section: Introductionmentioning

confidence: 99%

Comparison of the Number of Particle History for Monte Carlo Codes in Gamma-Ray Spectroscopy

Uyar

GÜNEKBAY

2023

Gazi University Journal of Science Part A: Engineering and Innovation

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Monte Carlo is a numerical computation algorithm that is widely used in many fields of science and is used to obtain numerical results with a large number of repeated random samplings. Radiation transport with Monte Carlo simulation continues to increase its popularity in the fields of radiation measurement. The high accuracy and precision measurement of radionuclide activity amounts in gamma-ray spectrometry depends on the efficiency calibration of the detector. Efficiency calibration is carried out in two ways, using certified reference materials, by experimental method or Monte Carlo simulation method. The experimental method is expensive, procedurally complex and time-consuming due to the supply of reference material. The use of the Monte Carlo technique in a reliable way without the need for a standard radioactive source in determining the detector efficiency is becoming common. The most critical step for accurate and precise results in getting the response of a detector with the Monte Carlo method is modeling the detector with its realistic dimensions. Another parameter as important as detector modeling is the number of histories in the simulation code examined in this study. The effect of the number of histories on efficiency was examined in detail using PHITS, GESPECOR and DETEFF Monte Carlo simulation codes. Since there is no definite number about this effect, which is important for obtaining meaningful and realistic results, the change in the efficiency value was examined by increasing the number of stories from 105 to 108. The results obtained in this work showed that at least 107 particle numbers should be used in all three programs where the uncertainty is below 1%. If the existing facilities are sufficient, it can be increased to 108s in case of having a more equipped and fast computer. However, going higher than this value does not make any sense as seen from the study.

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Performance revaluation of a N-type coaxial HPGe detector with front edges crystal using MCNPX

Cited by 26 publications

References 24 publications

Comparison of Experimental and Monte Carlo Efficiencies of 0.5g/cc Epoxy Matrix Marinelli Source with Multiple Radioactive Nuclides

Comparison of Experimental and Monte Carlo Efficiencies of 0.5g/cc Epoxy Matrix Marinelli Source with Multiple Radioactive Nuclides

Evaluation of the Central Copper Contact Pin Effect in High-Energy Region in Gamma-ray Spectrometry

Comparison of the Number of Particle History for Monte Carlo Codes in Gamma-Ray Spectroscopy

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