Energy and resolution calibration of NaI(Tl) and LaBr3(Ce) scintillators and validation of an EGS5 Monte Carlo user code for efficiency calculations

Casanovas, R.; Morant, J.J.; Salvadó, M.

doi:10.1016/j.nima.2012.02.006

Cited by 67 publications

(27 citation statements)

References 16 publications

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“…When the results of this study are compared with those belonging to other workers (Casanovas et al, 2012;Hamzawy, 2014;Rehman et al, 2009), the observed differences between the values of this work and others' due to the parameters such as detector and the source dimensions, geometric arrangement of the detector and source, etc., that are effective on detector efficiency as mentioned in Introduction section.…”

Section: Figure 4 Energy Resolution Of the Nai(tl) Detector For Sevementioning

confidence: 61%

Source-to-detector Distance Dependence of Efficiency and Energy Resolution of a 3"x3" NaI(Tl) Detector

Tarim

Gürler

2018

European Journal of Science and Technology

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NaI(Tl) scintillation detectors are widely used in measurements of environmental radioactivity, low level radioactive waste, prompt gamma ray neutron activation analysis, some nuclear physics experiments, geology, etc. This paper reports the results of the energy calibration, resolution and full energy peak efficiency and total efficiency calculations for a 3"x3" NaI(Tl) detector (Canberra Inc.) that are essential to specify the quality of the results of gamma spectrometry measurements. To investigate the effects of the gamma ray energy and the distance from source to detector center on detector efficiency, measurements were performed at different six axial distances for four point sources (Am-241, Cs-137, Co-60 and Na-22). Thus, fundamental data for further works with this detector system were obtained.

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Section: Figure 4 Energy Resolution Of the Nai(tl) Detector For Sevementioning

confidence: 61%

Source-to-detector Distance Dependence of Efficiency and Energy Resolution of a 3"x3" NaI(Tl) Detector

Tarim

Gürler

2018

European Journal of Science and Technology

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“…Somehow, the gamma-rays spectra obtained in the simulations are very different from the spectra obtained with the detectors. Thus, the resolution calibration in the user code must be accounted for obtaining the realistic spectra [17]. As we know, the absolute efficiency of detector is dependent on the source-detector distance.…”

Section: Validation Of Monte Carlo Model: Efficiency Calculations Of mentioning

confidence: 99%

MCNP-X Monte Carlo Code Application for Mass Attenuation Coefficients of Concrete at Different Energies by Modeling 3 × 3 Inch NaI(Tl) Detector and Comparison with XCOM and Monte Carlo Data

Tekın

2016

Science and Technology of Nuclear Installations

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Gamma-ray measurements in various research fields require efficient detectors. One of these research fields is mass attenuation coefficients of different materials. Apart from experimental studies, the Monte Carlo (MC) method has become one of the most popular tools in detector studies. An NaI(Tl) detector has been modeled, and, for a validation study of the modeled NaI(Tl) detector, the absolute efficiency of 3 × 3 inch cylindrical NaI(Tl) detector has been calculated by using the general purpose Monte Carlo code MCNP-X (version 2.4.0) and compared with previous studies in literature in the range of 661–2620 keV. In the present work, the applicability of MCNP-X Monte Carlo code for mass attenuation of concrete sample material as building material at photon energies 59.5 keV, 80 keV, 356 keV, 661.6 keV, 1173.2 keV, and 1332.5 keV has been tested by using validated NaI(Tl) detector. The mass attenuation coefficients of concrete sample have been calculated. The calculated results agreed well with experimental and some other theoretical results. The results specify that this process can be followed to determine the data on the attenuation of gamma-rays with other required energies in other materials or in new complex materials. It can be concluded that data from Monte Carlo is a strong tool not only for efficiency studies but also for mass attenuation coefficients calculations.

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“…It typically depends primarily on the detector material, the energy of the γ-ray, and the physical thickness of the detector in the direction of the incident gamma rays [16][17][18][19][20]. During the calculation of efficiency, the net full-energy peak area is obtained using the total peak area method [21,22].…”

Section: Efficiency Calibrationmentioning

confidence: 99%

Spectrum correction algorithm for detectors in airborne radioactivity monitoring equipment NH-UAV based on a ratio processing method

Cao

Tang

Wang

et al. 2015

Nuclear Instruments and Methods in Physics Research Section A:

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Energy and resolution calibration of NaI(Tl) and LaBr3(Ce) scintillators and validation of an EGS5 Monte Carlo user code for efficiency calculations

Cited by 67 publications

References 16 publications

Source-to-detector Distance Dependence of Efficiency and Energy Resolution of a 3"x3" NaI(Tl) Detector

Source-to-detector Distance Dependence of Efficiency and Energy Resolution of a 3"x3" NaI(Tl) Detector

MCNP-X Monte Carlo Code Application for Mass Attenuation Coefficients of Concrete at Different Energies by Modeling 3 × 3 Inch NaI(Tl) Detector and Comparison with XCOM and Monte Carlo Data

Spectrum correction algorithm for detectors in airborne radioactivity monitoring equipment NH-UAV based on a ratio processing method

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