Optimization of p-type HPGe detector model using Monte Carlo simulation

Trang, Le Thi Ngoc; Chương, Huỳnh Đình; Thanh, Tran Thien

doi:10.1007/s10967-020-07473-2

Cited by 16 publications

(7 citation statements)

References 28 publications

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“…The outer contact of the IGC50195 p-type detector is made of germanium doped with lithium and its internal contact is composed of germanium doped with boron. Although the lateral dead layer is caused by a lithium n+ contact, the dead layer is not actually consisting of lithium but rather of impure germanium [13,16,34,35]. This also means that the active part of the crystal is smaller than its physical dimensions.…”

Section: Monte Carlo Simulationsmentioning

confidence: 99%

“…High resolution semiconductor detectors like High Purity Germanium (HPGe) are commonly used for recording the prompt gamma-ray spectra to minimize the overlap of gamma peaks [10,11]. Modeling the HPGe detector response using a Monte Carlo simulation and approximating its efficiency for full-energy peaks by an analytical function fitted to the experimental efficiency is a common practice in gamma-ray spectrometry [11][12][13][14]. It is difficult to calibrate HPGe detectors over a broad energy ranges because only a limited number of calibration sources are available for gamma-rays up to 3 MeV energy.…”

Section: Introductionmentioning

confidence: 99%

“…Higher energy gamma-rays are usually produced using particle induced prompt gamma-ray reactions [15]. Although some works have been performed to calibrate the HPGe detectors, most of them are related to standard calibration sources and neutron induced prompt gamma-rays with relatively small energy ranges [12][13][14][16][17][18][19][20].…”

Section: Introductionmentioning

confidence: 99%

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Evaluation the nonlinear response function of a HPGe detector for 59 keV to 10.7 MeV gamma-rays using a Monte Carlo simulation and comparison with experimental data

Saheli¹,

Riazi²,

Jokar³

et al. 2021

J. Inst.

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A: Modeling of High Purity Germanium (HPGe) detector on a wide energy range is important in gamma-ray spectroscopy. The precisely modeled detector can be used for protoninduced prompt gamma-ray spectroscopy. In this work, we used both the gamma-rays of calibration sources and prompt gamma-rays emitted in proton capture reactions to model a coaxial p-type HPGe detector using Geant4 Monte Carlo simulation for the gamma-ray energy range of 59-10764 keV. The calibration sources were 137 Cs, 241 Am, 60 Co, 152 Eu, and 133 Ba, while the prompt gamma-rays were due to the gamma-ray cascades following the 27 Al(p,𝛾) 28 Si reaction capture at the resonant energies of 992, 1317 and 2483 keV, as well as the 23 Na(p,𝛾) 24 Mg reaction capture at the resonant energies of 1417 and 1395 keV. According to the results obtained, the presented simulated and experimental spectra show a good agreement. In addition, the mean and maximum relative deviations between experimental and simulated efficiencies corresponding to 27 major peaks are smaller than 5% and 15%, respectively. K: Gamma detectors (scintillators, CZT, HPGe, HgI etc); Simulation methods and programs; Detector modelling and simulations I (interaction of radiation with matter, interaction of photons with matter, interaction of hadrons with matter, etc); Accelerator Applications

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Section: Monte Carlo Simulationsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Evaluation the nonlinear response function of a HPGe detector for 59 keV to 10.7 MeV gamma-rays using a Monte Carlo simulation and comparison with experimental data

Saheli¹,

Riazi²,

Jokar³

et al. 2021

J. Inst.

View full text Add to dashboard Cite

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“…The efficiency value, which shows the performance of HPGe detectors, must be determined accurately and precisely, no matter what the detector is used for (Modarresi et al, 2017). It has been shown by many studies in the literature that the Monte Carlo simulation method can be successfully applied in gamma-ray spectrometry, especially in the efficiency calculation (Abd El Gawad et al, 2020;Trang et al, 2021;Stríbrnský et al, 2022). Two types of Monte Carlo simulation software are used in gamma-ray spectroscopy: these are either general-purpose codes such as GEANT, PENELOPE, EGS4, FLUKA, PHITS, or GESPECOR, DETEFF, ETNA, EFFTRAN, etc.…”

Section: Introductionmentioning

confidence: 99%

Attenuation Effect of Sample Container in Radioactivity Measurement by Gamma-ray Spectroscopy

Uyar

2022

Gazi University Journal of Science Part A: Engineering and Innovation

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The measurement of radioactivity in environmental samples containing natural radionuclides such as 238U, 232Th, and 40K in gamma-ray spectrometry is the most common application. One of the most widely used sample containers for environmental radioactivity measurements is volumetric sample containers of certain sizes in cylindrical geometry. These cylindrical containers can be made of materials with different densities and thicknesses. In this intention, in this study, the effect of the sample container, which is one of the many parameters affecting the detector efficiency, was investigated. For this purpose, acrylic and polypropylene materials with of different densities were examined. IAEA RGU-1, IAEA-RGTh-1 and IAEA-RGK-1 standards containing uranium, thorium and potassium environmental radionuclides analyzed in gamma-ray spectrometric measurements were used as samples for these sample containers with different densities. Additionally, since the spectra in cylindrical geometry are taken by placing them on the detector endcap, the effect of the bottom thickness was investigated by changing the bottom thickness of these materials. Different material and bottom thickness evaluations were made using PHITS and GESPECOR Monte Carlo simulation programs. Compatible results were obtained with a difference of <5% between the PHITS and GESPECOR programs. From the outcome of this study, it can be concluded that when choosing the container material, the density should be as low as possible and especially the bottom thickness should be thin.

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“…High-purity germanium (HPGe) detectors have superior energy resolution. Therefore, they are widely used in gamma-ray spectroscopy to identify gamma-emitting nuclides and determine their radioactivity in environmental samples or radioactive waste [5,6]. To measure the radioactivity of radionuclides accurately, the full-energypeak (FEP) efficiency of the detector must be calibrated, considering various geometric characteristics such as the size, shape, and composition of each sample [7].…”

Section: Introductionmentioning

confidence: 99%

Dead Layer Thickness and Geometry Optimization of HPGe Detector Based on Monte Carlo Simulation

Kwon

Jang

et al. 2022

Progress in Medical Physics

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A full-energy-peak (FEP) efficiency correction is required through a Monte Carlo simulation for accurate radioactivity measurement, considering the geometrical characteristics of the detector and the sample. However, a relative deviation (RD) occurs between the measurement and calculation efficiencies when modeling using the data provided by the manufacturers due to the randomly generated dead layer. This study aims to optimize the structure of the detector by determining the dead layer thickness based on Monte Carlo simulation. Methods:The high-purity germanium (HPGe) detector used in this study was a coaxial p-type GC2518 model, and a certified reference material (CRM) was used to measure the FEP efficiency. Using the MC N-Particle Transport Code (MCNP) code, the FEP efficiency was calculated by increasing the thickness of the outer and inner dead layer in proportion to the thickness of the electrode.Results: As the thickness of the outer and inner dead layer increased by 0.1 mm and 0.1 μm, the efficiency difference decreased by 2.43% on average up to 1.0 mm and 1.0 μm and increased by 1.86% thereafter. Therefore, the structure of the detector was optimized by determining 1.0 mm and 1.0 μm as thickness of the dead layer. Conclusions:The effect of the dead layer on the FEP efficiency was evaluated, and an excellent agreement between the measured and calculated efficiencies was confirmed with RDs of less than 4%. It suggests that the optimized HPGe detector can be used to measure the accurate radioactivity using in dismantling and disposing medical linear accelerators.

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Optimization of p-type HPGe detector model using Monte Carlo simulation

Cited by 16 publications

References 28 publications

Evaluation the nonlinear response function of a HPGe detector for 59 keV to 10.7 MeV gamma-rays using a Monte Carlo simulation and comparison with experimental data

Evaluation the nonlinear response function of a HPGe detector for 59 keV to 10.7 MeV gamma-rays using a Monte Carlo simulation and comparison with experimental data

Attenuation Effect of Sample Container in Radioactivity Measurement by Gamma-ray Spectroscopy

Dead Layer Thickness and Geometry Optimization of HPGe Detector Based on Monte Carlo Simulation

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