Monte-Carlo modeling of a NaI(Tl) scintillator

Ashrafi, Saleh; Anvarian, S.; Sobhanian, S.

doi:10.1007/s10967-006-0236-0

Cited by 17 publications

(8 citation statements)

References 1 publication

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“…The energy spectrum was also acquired with the FLUKA MC programme and the theoretical energy resolution was found to be 6.77% (Figure 11). Ashrafi et al obtained the 137 Cs gamma energy spectrum by means of the GEANT4 MC method [16]. When a comparison was made between their theoretical spectrum and the one in this work, it was seen that the K X-ray peak was available in the presented spectrum via FLUKA MC method.…”

Section: K X-ray Peak Photopeakmentioning

confidence: 58%

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Analogue and digital analysis of the effects of some parameters in determination of the best experimental energy resolution

Ermis¹,

Tektas²,

Pilicer³

et al. 2014

Turk J Phys

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The gamma-ray energy spectrum of 137 Cs was obtained according to different parameters such as preamplifier capacitance, the amplifier's coarse gain level, power supply voltage for the detector, and source-to-detector distance. This investigation was performed with both analogue and digital methods. In order to examine the effects of these parameters on energy resolution, a NaI(Tl) inorganic scintillation detector was used. In addition, the gamma energy spectrum of the radioisotope was obtained by means of FLUKA, which is one of the Monte Carlo simulation programmes. Energy resolution of the detector by these 3 methods was calculated. These resolution values were compared with each other.Effects of the parameters above on the resolutions from analogue and digital methods were discussed.

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Section: K X-ray Peak Photopeakmentioning

confidence: 58%

“…MC simulation was used to determine gamma-ray response functions of a NaI(Tl) detector by Shi et al [15]. The theoretical energy spectrum of 137 Cs was given by Ashrafi et al via the Geant4 MC method [16].…”

Section: Input F Lementioning

confidence: 99%

Analogue and digital analysis of the effects of some parameters in determination of the best experimental energy resolution

Ermis¹,

Tektas²,

Pilicer³

et al. 2014

Turk J Phys

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“…It is also used in the characterization of the detector system which is the most important part of the positron emission tomography (PET), etc. GATE runs with Geant4 simulation toolkit which is the validated physics models, complex geometrical volume description and powerful 3D visualization (such as Qt mode) [8,[19][20][21][22][23].…”

Section: Introductionmentioning

confidence: 99%

The Determination of the Total Efficiency for NaI(Tl) Detector by GATE Simulation

Yavuzkanat¹,

Yalçın²,

Güngör³

2019

Bitlis Eren Üniversitesi Fen Bilimleri Dergisi

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In this study the total efficiency of the NaI(Tl) detector have been calculated by using Geant4 based GATE simulation program. The simulation was performed using point and disc isotropic gamma-ray sources at various distance between source and detector in the photon energy range 50-3000 keV. Results were compared with different analytical and Monte Carlo calculations obtained in the time of the periods 1958-2018. The calculated and simulated data indicated good agreement with finding more sensitive GATE simulation result in the lower energy range from 50 keV to 150 keV.

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“…There are two faces through which photons can hit a typical NaI (Tl) detector: circular side so-called the detector's entrance window and cylindrical side. In gamma spectrometry, in order to gauge the radioactive contamination originated from different directions of the environment, the cylindrical side of sodium iodide detector is modelled [4], whereas, in laboratorial measurement in which the position of a radiation source in relative to detector is well-defined, shielding of the detector in order to minimize the background radiation is welcome [5]. In radiation measurements, the detection efficiency is an important quantity, so that in the absence of a reliable value for detection efficiency, accurate data analysis is impossible [6,7].…”

Section: Introductionmentioning

confidence: 99%

A method to calculate the gamma ray detection efficiency of a cylindrical NaI (Tl) crystal

2018

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Given a wide range application of NaI(Tl) detector in industrial and medical sectors, computation of the related detection efficiency in different distances of a radioactive source, especially for calibration purposes, is the subject of radiation detection studies. In this work, a 2in both in radius and height cylindrical NaI (Tl) scintillator was used, and by changing the radial, axial, and diagonal positions of an isotropic 137 Cs point source relative to the detector, the solid angles and the interaction probabilities of gamma photons with the detector's sensitive area have been calculated. The calculations present the geometric and intrinsic efficiency as the functions of detector's dimensions and the position of the source. The calculation model is in good agreement with experiment, and MCNPX simulation. K: Detector modelling and simulations I (interaction of radiation with matter, interaction of photons with matter, interaction of hadrons with matter, etc); Scintillators, scintillation and light emission processes (solid, gas and liquid scintillators) 1Corresponding author.

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Monte-Carlo modeling of a NaI(Tl) scintillator

Cited by 17 publications

References 1 publication

Analogue and digital analysis of the effects of some parameters in determination of the best experimental energy resolution

Analogue and digital analysis of the effects of some parameters in determination of the best experimental energy resolution

The Determination of the Total Efficiency for NaI(Tl) Detector by GATE Simulation

A method to calculate the gamma ray detection efficiency of a cylindrical NaI (Tl) crystal

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