HPGe well detector calibration procedure by MCNP5 Monte Carlo computer code

Santo, Aline S.E.; Wasserman, Francis Gabriel; Conti, C.C.

doi:10.1016/j.anucene.2012.03.037

Cited by 20 publications

(5 citation statements)

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“…Traditionally, the response of a HPGe detector for gamma/X-rays is determined empirically using radioactive sources of known activities. In recent years, there is a growing trend in utilizing Monte-Carlo simulations to study properties related to the detection and quantification of gamma/X-ray by radiation detectors, including detection efficiency, cascade summing effect, evaluation of detector internal dimensions, impact of shielding materials over the MDA, optimization of detector configuration and the full reconstruction of a gamma-ray spectrum [1][2][3][4][5][6][7][8][9]. The main advantages of using numerical calculations are versatility, reduced cost and avoiding the risks associated with handing of radioactive materials.…”

Section: Introductionmentioning

confidence: 99%

Monte-Carlo simulations of the full-energy-peak efficiency for a broad-energy germanium detector—a comparison between GEANT4 and FLUKA

Aviv

Elia

2020

J. Inst.

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The detection efficiency of a broad-energy germanium detector was determined empirically and compared to predictions by the Monte-Carlo software GEANT4 and FLUKA . The considered source geometries were point-like, filter paper and a water beaker. Calculations were performed in the photon energy range of 30–1836 keV . Simulated detection efficiencies obtained from both Monte-Carlo software were found to be in a good agreement (typically <5%) with experimental results for the considered source geometries. A comparison between the detection efficiencies obtained with GEANT4 and FLUKA codes exhibited a good agreement with a robust average of approximately 1%.

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Section: Introductionmentioning

confidence: 99%

Monte-Carlo simulations of the full-energy-peak efficiency for a broad-energy germanium detector—a comparison between GEANT4 and FLUKA

Aviv

Elia

2020

J. Inst.

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“…It does not require chemical separation and can be measured in bulk form (Conti et al, 2013, Santo et al, 2012. HPGe detectors are widely used for gamma spectrometry, mainly because of the high sensitivity and energy resolution, especially for low-level activity materials.…”

Section: Introductionmentioning

confidence: 99%

Using lattice tools and unfolding methods for hpge detector efficiency simulation with the Monte Carlo code MCNP5

Querol

Gallardo

Ródenas

et al. 2015

Radiation Physics and Chemistry

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ElsevierQuerol Vives, A.; Gallardo Bermell, S.; Ródenas Diago, J.; Verdú Martín, GJ. (2015). Using lattice tools and unfolding methods for hpge detector efficiency simulation with the Monte Carlo code MCNP5. Radiation Physics and Chemistry. 116:219-225. doi:10.1016/j.radphyschem.2015.01.027. USING LATTICE TOOLS AND UNFOLDING METHODS FOR HPGE DETECTOR EFFICIENCY SIMULATION WITH THE MONTE CARLO CODE MCNP5A. Querol 1 , S. Gallardo, J. Ródenas and G. Verdú Instituto de Seguridad Industrial, Radiofísica y Medioambiental (ISIRYM)Universitat Politècnica de València, Valencia, Spain. AbstractIn environmental radioactivity measurements, High Purity Germanium (HPGe) detectors are commonly used due to their excellent resolution. Efficiency calibration of detectors is essential to determine activity of radionuclides. The Monte Carlo method has been proved to be a powerful tool to complement efficiency calculations. In aged detectors, efficiency is partially deteriorated due to the dead layer increasing and consequently, the active volume decreasing. The characterization of the radiation transport in the dead layer is essential for a realistic HPGe simulation. In this work, the MCNP5 code is used to calculate the detector efficiency. The F4MESH tally is used to determine the photon and electron fluence in the dead layer and the active volume. The energy deposited in the Ge has been analyzed using the *F8 tally. The F8 tally is used to obtain spectra and to calculate the detector efficiency. When the photon fluence and the energy deposition in the crystal are known, some unfolding methods can be used to estimate the activity of a given source. In this way, the efficiency is obtained and serves to verify the value obtained by other methods.

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“…Semiconductor detectors are widely used for these purposes. However, they all introduce a measurement error and detected spectra are somewhat distorted [7][8][9] and [10]. The distortion is characterized by additional escape peaks, changes in impulse height, and symmetric and asymmetric peak broadening [10] and depends, among other things, on detector material, shape and electrical characteristics.…”

Section: Introductionmentioning

confidence: 99%

“…To unfold the measured spectrum it is necessary first to obtain the detector response function that is generated by recording detector response to monochromatic photons. Monte Carlo (MC) simulation is a standard method used to acquire the response function [6,8,[10][11][12] and [13].…”

Section: Introductionmentioning

confidence: 99%

Toward utilization of MCNP5 particle track output file for simulation problems in photon spectrometry

Antić-Stanković

Marinkovic

Ciraj-Bjelac

et al. 2015

Computer Physics Communications

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HPGe well detector calibration procedure by MCNP5 Monte Carlo computer code

Cited by 20 publications

References 1 publication

Monte-Carlo simulations of the full-energy-peak efficiency for a broad-energy germanium detector—a comparison between GEANT4 and FLUKA

Monte-Carlo simulations of the full-energy-peak efficiency for a broad-energy germanium detector—a comparison between GEANT4 and FLUKA

Using lattice tools and unfolding methods for hpge detector efficiency simulation with the Monte Carlo code MCNP5

Toward utilization of MCNP5 particle track output file for simulation problems in photon spectrometry

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