Monte Carlo calculations of the HPGe detector efficiency for radioactivity measurement of large volume environmental samples

A novel method to estimate the dead layer of HPGe detector for Monte Carlo FEPE computation

In this study, a novel method to determine the surface and lateral dead layers of p-type HPGe detector is proposed to compute the full energy peak efficiency (FEPE). The method employed standard radioactive point sources 241Am, 133Ba and FEPE measurement at low energies to estimate the thickness of frontal and lateral dead layers. The method is simple to apply, requires only two standard radioactive sources to estimate the optimum thickness of frontal and lateral dead layers. The proposed method is validated by measuring the efficiency of various point sources and a volume source in the energy range from 59 to 1408 keV. The measured efficiencies agree to simulation with relative deviation less than 4.0% at each energy. The proposed detector model enables to calibrate the detector for environmental radioactivity measurement without standard volume sources.

Comparison of MCC-MT and EffMAKER software packages for in SITU field measurements with Monte Carlo simulations

This work is devoted to comparing the Monte Carlo simulation tools: Monte Carlo Calculation-Multi Track (MCC-MT) software and EffMaker software, in terms of the efficiency when using them in field applications for measurement of radioactive waste or their free release from control. The detection efficiency of volumetric gamma sources' reference samples in the form of a metal cylinder, a rod, and a rod placed in a 200-L barrel with sand, in the energy range of 50-1500 keV, has been simulated. Comparison of simulation results with in-situ measurements by a mobile HPGe spectrometer showed that the discrepancy between calculation and experiment for all measurement geometries is larger for EffMaker, which is associated with a less accurate detector model than in MCC-MT. Both programs give acceptable results in terms of accuracy and are recommended for calibrating gamma spectrometers in the case of field measurements.

X-ray radiography of HPGe detectors for Monte Carlo simulations

The results of the development of a radiographic installation that allows to control the size of the internal elements of HPGe detectors' cryostats for simulation by Monte Carlo method, are presented. Calibration and assessment of image quality value of the developed radiographic installation were carried out in accordance with ISO Standards 19232-1 and 19232-5. Simulation of the HPGe detector's registration efficiency in the range of 50 keV-3 MeV with the MCC-MT program showed that the discrepancy between the calculated and experimental results when adjusting the detector model using radiological measurement data does not exceed 3% in geometry for point sources and 5% for the Eu-152 source in the Marinelli beaker geometry.

Monte Carlo simulation study on the cause of the formation of the efficiency curve at low energies in germanium detectors

Detector efficiency is a measure of the detectors' ability to detect radiation. It is known that the efficiency values, which are important and affect the activity calculation in germanium detectors, decrease rapidly at low energies. This study focuses on the reasons for this handicap in the low energy region of the efficiency curve. The Monte Carlo simulation was carried out with four setups: germanium only, germanium with a dead layer, germanium with aluminum holders, and finally germanium with a dead layer and aluminum holders. The effect of each setup on the efficiency curve was observed. As a result, it was seen that the main cause of the handicap was the dead layer. For this reason, it was concluded that the current value of the dead layer, which is known to change over time, should be taken into account in detector calibrations or characterizations.

Re-construction of a HPGe detector precise modeling for efficiency calibration

High purity germanium (HPGe) detector is a preferred choice for determining the activity of the radioactive samples for nuclear diagnostics of Inertial Confinement Fusion (ICF) experiments. Although the amounts of the radiochemical sample are limited, activity measurement at a close distance between the detector window and the radioactive source is a feasible method. Efficiency calibration of gamma rays at a close distance from the surface of a HPGe detector is crucial. Considering the problem of the coincidence at a close distance, the alternative way is to construct a precise model of the HPGe detector and then to calculate efficiency accurately at an arbitrary distance from the surface of the HPGe detector using Monte Carlo method. In this paper, internal geometry and structure except for dead layers of the HPGe detector is obtained by X-ray radiography and 3D reconstruction. The optimal dead layers of the germanium crystal are determined by tracing the minimal sum squared residual (SSR) of gamma-ray efficiencies between calculations and measurements for standard planar sources. Nonhomogeneous distribution of the dead layer is supposed according to the inner structure on the Ge crystal. The final results show that the corrected model improves the accuracy of the calculated efficiencies.

Study of coincidence summing effect using Monte Carlo simulation to improve large samples measurement for environmental applications

A new measurement model composed of High Purity Germanium detector HPGe including Lead Shield with a mixed source of Am-241, Cd-109, …in a soil matrix packed in a cylindrical container was developed by Monte Carlo N-Particles code MCNP5. The Monte Carlo models being largely used for efficiencies calculations in routine environmental radioactivity measurements of high volume soil samples. In order to validate the simulation, a multi-radionuclides soil matrix source in a cylindrical container is prepared. Comparing the simulated results to the experimental ones, allows us to correct coincidence summing in the soil standard and study its effect in activity measurements where a good agreement is found between corrected activities and results found by another geometry and show how uncorrected efficiency curves lead to erroneous activity calculation. Finally, the developed model is applied to study the distribution of natural and artificial radioactivity in a forest site in Bainem, northern of Algeria, these results are invested for radiological impact and soil erosion studies in the study Area.

Optimization of the marinelli beaker dimensions using genetic algorithm

A computational code, based on the genetic algorithm and MCNPX version 2.6 code was developed and used to investigate the effects of some important parameters of HPGe detector (such as Al cap thickness, dead-layer thickness and Ge hole size) on optimum dimensions of marinelli beaker. In addition, the effects of detector material on optimal beaker dimensions were also investigated. Finally, the optimized beaker dimensions at various beaker volumes (300, 500, 700, 1000 and 1500 cm³) were determined for some conventional Ge detectors with different crystal sizes (16 sizes). These sets of data then were used to drive mathematical formulas (obtained by best fitting to data sets). The results showed that, there is no meaningful correlation between the optimum dimensions of the beaker and each of the dead-layer thickness, Al cap thickness and the Ge-crystal hole size. On the other hand, the optimum beaker radius increases with decreasing the density of the detector material while the beaker height decreases.