Monte Carlo EGS5 simulationsof High Purity Germanium (HPGe) detector

2015 ◽  
Author(s):  
Kamran Arif ◽  
Azhar H. Malik
Keyword(s):  
Monte Carlo ◽  
High Purity ◽  
Hpge Detector ◽  
High Purity Germanium

Monte Carlo simulation of gamma-ray interactions in an over-square high-purity germanium detector for in-vivo measurements

2016 ◽  
Vol 44 ◽  
pp. 1660225
Author(s):  
Mirela Angela Saizu
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
High Purity ◽  
Hpge Detector ◽  
Germanium Detector ◽  
Efficiency Calibration ◽  
Gamma Energy ◽  
High Purity Germanium ◽  
The Monte Carlo Method

The developments of high-purity germanium detectors match very well the requirements of the in-vivo human body measurements regarding the gamma energy ranges of the radionuclides intended to be measured, the shape of the extended radioactive sources, and the measurement geometries. The Whole Body Counter (WBC) from IFIN-HH is based on an “over-square” high-purity germanium detector (HPGe) to perform accurate measurements of the incorporated radionuclides emitting X and gamma rays in the energy range of 10 keV–1500 keV, under conditions of good shielding, suitable collimation, and calibration. As an alternative to the experimental efficiency calibration method consisting of using reference calibration sources with gamma energy lines that cover all the considered energy range, it is proposed to use the Monte Carlo method for the efficiency calibration of the WBC using the radiation transport code MCNP5. The HPGe detector was modelled and the gamma energy lines of [Formula: see text]Am, [Formula: see text]Co, [Formula: see text]Ba, [Formula: see text]Cs, [Formula: see text]Co, and [Formula: see text]Eu were simulated in order to obtain the virtual efficiency calibration curve of the WBC. The Monte Carlo method was validated by comparing the simulated results with the experimental measurements using point-like sources. For their optimum matching, the impact of the variation of the front dead layer thickness and of the detector photon absorbing layers materials on the HPGe detector efficiency was studied, and the detector’s model was refined. In order to perform the WBC efficiency calibration for realistic people monitoring, more numerical calculations were generated simulating extended sources of specific shape according to the standard man characteristics.

scholarly journals Cross Sections for the \(^{nat}\)Zr\((p,xn)^{89,90}\)Nb Reactions Induced by 27.7 MeV Protons

2015 ◽  
Vol 25 (3) ◽  
pp. 257 ◽  
Author(s):  
Pham Duc Khue ◽  
Nguyen Van Do ◽  
Le Tuan Anh
Keyword(s):  
Proton Beam ◽  
Cross Sections ◽  
High Purity ◽  
Hpge Detector ◽  
Nuclear Reactions ◽  
Medical Science ◽  
Activation Method ◽  
Reaction Products ◽  
High Purity Germanium ◽  
Mev Protons

The cross-sections for the formation of \(^{89}\)Nb and  \(^{90}\)Nb radionuclides in proton induced nuclear reactions on zirconium  were measured by using the well known activation method. The natural  zirconium (\(^{nat}\)Zr) target and copper (\(^{nat}\)Cu) monitor foils were  irradiated by 27.7 MeV proton beam at the MC50 Cyclotron of the Korea  Institute of Radiological and Medical Science (KIRAMS), Korea. The induced  gamma activities of the reaction products were measured by a coaxial high  purity germanium (HPGe) detector coupled to a PC-based multichannel  analyzer. The obtained cross sections for each nuclide are compared with  those existing in literature and with the theoretical cross sections  calculated by the TALYS - 1.4 code.

An overview on radiometric assessment and excess lifetime cancer risk of soil in Pakistan by using High Purity Germanium (HPGe) detector

2020 ◽  
Vol 35 (4) ◽  
pp. 531-543
Author(s):  
Jalil ur Rehman ◽  
Iftikhar Alam ◽  
Nisar Ahmad ◽  
Aslam Hameed ◽  
Alia Nazir ◽  
...  
Keyword(s):  
Cancer Risk ◽  
Gamma Rays ◽  
Human Body ◽  
Natural Radioactivity ◽  
High Purity ◽  
Hpge Detector ◽  
Permissible Limit ◽  
Radioactive Elements ◽  
Naturally Occurring ◽  
High Purity Germanium

AbstractObjectivesThe aim of this study is to compare the natural radioactivity and excess life time cancer risk (ELCR) factor of soil in different regions of Pakistan during last decade. Soil contains various elements and compounds including naturally occurring radioactive elements (238U, 232Th, 40K and 137Cs). Human being, animals and plants are in health risk by contaminations of natural radioactivity in soil and environmental radiometric pollution. Transferring of large amount of the natural radioactive elements in human body by nutrients may cause carcinogenic effects in human body. Pakistani soil has six types as Indus Basin Soil, Bongar Soil, Khaddar Soil, Indus delta soil, Mountainous soil and Sandy Desert Soil. In some northern region of Pakistan, naturally occurring radioactive rocks like uranuium-238 and iridium concentrations present in Gharwandi, Aram, Kingri S, Vitakri Fort Munro, Dera Bugti, Kohlu and Sibbi districts.MethodsIn this reviewed data, gamma rays spectroscopy used to determine the concentrations of 238U, 232Th and 40K with the help of High Purity Germanium (HPGe) detectors. Only the data of HPGe detector collected because of comparisons of different regions of Pakistan.Results and conclusionsMostly, different gamma rays energy peaks of relevant daughter radionuclides of radioactive element were used such as the energy peak lines of daughter radionuclides 214Pb (295.21 and 352 KeV) and 214Bi (609 and 1,120 KeV) used for calculating the 226Ra concentration in soil. In the recent study, it is concluded that average values of concentrations of natural radioactivity in soil in central and north regions of Pakistan are higher than permissible limit but found permissible range in south region of Pakistan. Mean values of ELCR factor were found higher, equal and lower in central, north and south regions than permissible limit, respectively. Generally, no serious health hazard due to natural radioactivity in soil were found.

scholarly journals Ratio of spectral averaged cross sections measured in standard 252Cf(sf) and 235U(nth,f) neutron fields

2020 ◽  
Vol 239 ◽  
pp. 19004
Author(s):  
Martin Schulc ◽  
Michal Kostal ◽  
Roberto Capote ◽  
Evzen Novak ◽  
Nicola Burianova ◽  
...  
Keyword(s):  
Cross Section ◽  
Cross Sections ◽  
High Purity ◽  
Hpge Detector ◽  
High Volume ◽  
Reaction Rates ◽  
Fission Neutron ◽  
Neutron Field ◽  
High Threshold ◽  
High Purity Germanium

The results of systematic evaluations of spectrum averaged cross section (SACS) measurements in the fission neutron fields of 252Cf and 235U are presented. The data form a complete database of high-threshold experimental SACS measured in the same installation under the same conditions and using the same high purity germanium gamma spectrometer. This is crucial to reduce the uncertainty of the ratio and the data scattering and therefore, to minimize discrepancies compared to cross section measured under different conditions in different laboratories. This new dataset complements and extends earlier experimental evaluations. The total emission of the 252Cf neutron source during the experiments varied from 9.5E8 to 4.5E8 neutrons per second. The emission was derived in accordance to the data in the Certificate of Calibration involving absolute flux measurements in a manganese sulphate bath. Concerning 235U fission neutron field, the irradiations were carried out in a specifically designed core assembled in the zero power light water LR-0 reactor. This special core has a well described neutron field. After the irradiation, the low volume irradiated samples to be measured by gamma spectrometry were placed directly on the upper cap of a coaxial high purity germanium (HPGe) detector in a vertical configuration (ORTEC GEM35P4). High volume samples were homogenized and strewn into the Marinelli beaker. The HPGe detector is surrounded by the lead shielding box with a thin inner copper cladding and covered with rubber for suppression of background signal and bremsstrahlung. The experimental reaction rates were derived for irradiated samples from the Net Peak Areas (NPA) measured using the semiconductor HPGe detector. The measured reaction rates are used to derive the spectrum-averaged cross sections. Furthermore, measured reaction rates are also compared with MCNP6 calculations using various nuclear data libraries, in particular IRDFF evaluations.

Development of gamma spectrometric method for the determination of thorium in phosphoric acid solution

2010 ◽  
Vol 98 (5) ◽  
Author(s):  
N. N. Mirashi ◽  
Satyajeet Chaudhury ◽  
S. K. Aggarwal
Keyword(s):  
Phosphoric Acid ◽  
Acid Solution ◽  
High Purity ◽  
Hpge Detector ◽  
Phosphoric Acid Solution ◽  
Spectrometric Method ◽  
High Purity Germanium

AbstractGamma spectrometric determination of thorium in sintered thoria dissolved in strong phosphoric acid was studied using a high purity germanium (HPGe) detector.

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