scholarly journals HPGe Detector Energy Response Function Calculation Up to 400 keV Based on Monte Carlo Code

2010 ◽  
Vol 2 (3) ◽  
pp. 479 ◽  
Author(s):  
M. S. Rahman ◽  
G. Cho

A high purity germanium detector (HPGe) of crystal size of diameter 4.91 cm and length of 3.6 cm  was modeled in accordance with the Pop Top cryostat configuration (model no. GEM10P4). The energy response function was calculated in the air using Monte Carlo simulation with mono-energy g-ray photon up to 400 keV. The distance between the source and the front surface or end cap to detector was 20 cm and the source was assumed as an isotopic point source. The aluminum absorbing layers of thickness 0.127 cm was also taken into consideration in the simulation model. The input number of particles was 107 for each mono-energetic g-ray photon. The simulated energy response functions were verified with the measured energy response functions obtained using calibration sources in order to prove the accuracy of the modeling. The comparison between the measured energy response functions and the simulated energy response functions after normalization were also performed.  Keywords: HPGe; Gamma-ray spectrum; Monte Carlo. © 2010 JSR Publications. ISSN: 2070-0237 (Print); 2070-0245 (Online). All rights reserved. DOI: 10.3329/jsr.v2i3.4668                 J. Sci. Res. 2 (3), 479-483 (2010)  

2013 ◽  
Vol 772 ◽  
pp. 571-578
Author(s):  
Rahadi Wirawan ◽  
M. Djamal ◽  
A. Waris ◽  
Gunawan Handayani ◽  
Hong Joo Kim

Response function is a fundamental parameter for all detectors in order to analyze the energy distribution of gamma ray which undergoes scattering interaction with the material. The response functions of a 3 in. x 3 in. NaI(Tl) collimated detector for non axis detector-source geometry has been calculated using a Monte Carlo approach from GEANT4 simulation code with 0.662 MeV of mono-energetic of photon gamma ray. Collimated Pb with 4 cm thickness and 2 cm of holes diameter were employed for shielding. The source was assumed as an isotropic point source and it is placed at various positions to the detector axis. The comparison between the measured energy response functions and the simulated energy response functions after normalization were also performed in order to validate the modeling results.


2011 ◽  
Vol 26 (2) ◽  
pp. 140-146 ◽  
Author(s):  
Rahim Khabaz ◽  
Miri Hakimabad

The multi-sphere method, a neutron detection technique, has been improved with a BF3 long cylindrical counter as a thermal detector located in the center of seven spheres with a diameter range of 3.5 to 12 inches. Energy response functions of the system have been determined by applying the MCNP4C Monte Carlo code of 10-8 MeV to 18 MeV. A new shadow cone has been designed to account for scattered neutrons. Although the newly designed shadow cone is smaller in length, its attenuation coefficient has been improved. To evaluate the system, the neutron spectrum of a 241AM-Be source has been measured.


2008 ◽  
Vol 23 (2) ◽  
pp. 51-57
Author(s):  
Milijana Steljic ◽  
Miodrag Milosevic ◽  
Petar Belicev

The paper describes the procedure of adapting a coaxial high-precision germanium detector to a device with numerical calibration. The procedure includes the determination of detector dimensions and establishing the corresponding model of the system. In order to achieve a successful calibration of the system without the usage of standard sources, Monte Carlo simulations were performed to determine its efficiency and pulse-height response function. A detailed Monte Carlo model was developed using the MCNP-5.0 code. The obtained results have indicated that this method represents a valuable tool for the quantitative uncertainty analysis of radiation spectrometers and gamma-ray detector calibration, thus minimizing the need for the deployment of radioactive sources.


2002 ◽  
Vol 57 (4) ◽  
pp. 517-524 ◽  
Author(s):  
Hu-Xia Shi ◽  
Bo-Xian Chen ◽  
Ti-Zhu Li ◽  
Di Yun

2014 ◽  
Vol 27 ◽  
pp. 1460154 ◽  
Author(s):  
TRAVIS ZIPPERER ◽  
FARZAD RAHNEMA ◽  
DINGKANG ZHANG

A new incident flux response expansion method (IFLEX) is developed to perform on-the-fly detector pulse height spectra calculations with Monte Carlo accuracy. Given the flux incident on the detector window, the method uses pre-computed continuous energy Monte Carlo based response functions to generate the pulse height tallies. B-spline functions are selected for the expansion of the incident flux in the energy phase space. Response functions are generated for a CsI(Na) crystal using an energy dependent B-spline form of the IFLEX method. The method is verified for two incident flux spectra on the crystal. Results of the energy dependent B-spline form of the method are compared to the solutions generated using the direct Monte Carlo code MCNP5. The method is shown to be several orders faster than MCNP5 while maintaining paralleled accuracy.


2022 ◽  
Vol 2155 (1) ◽  
pp. 012020
Author(s):  
I V Prozorova

Abstract A standard procedure for characterizing the high-purity germanium detector (HPGe), manufactured by Canberra Industries Inc [1], is performed directly by the company using patented methods. However, the procedure is usually expensive and must be repeated because the characteristics of the HPGe crystal change over time. In this work, the principles of a technique are developed for use in obtaining and optimizing the detector characteristics based on a cost-effective procedure in a standard research laboratory. The technique requires that the detector geometric parameters are determined with maximum accuracy by the Monte Carlo method [2] in parallel with the optimization based on evolutionary algorithms. The development of this approach facilitates modeling of the HPGe detector as a standardized procedure. The results will be also beneficial in the development of gamma spectrometers and/or their calibrations before routine measurements.


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