Modeling of detection efficiency of HPGe semiconductor detector by Monte Carlo method

Over the past ten years following the gradual adoption of new legislative standards for protection against ionizing radiation was significant penetration of gamma-spectrometry between standard radioanalytical methods. In terms of nuclear power plant gamma-spectrometry has shown as the most effective method of determining of the activity of individual radionuclides. Spectrometric laboratories were gradually equipped with the most modern technical equipment. Nevertheless, due to the use of costly and time intensive experimental calibration methods, the possibilities of gamma-spectrometry were partially limited. Mainly in late 90-ies during substantial renovation and modernization works. For this reason, in spectrometric laboratory in Nuclear Power Plants Bohunice in cooperation with the Department of Nuclear Physics FMPI in Bratislava were developed and tested several calibration procedures based on computer simulations using GEANT program. In presented thesis the calibration method for measuring of bulk samples based on auto-absorption factors is described. The accuracy of the proposed method is at least comparable with other used methods, but it surpasses them significantly in terms of efficiency and financial time and simplicity. The described method has been used successfully almost for two years in laboratory spectrometric Radiation Protection Division in Bohunice nuclear power. It is shown by the results of international comparison measurements and repeated validation measurements performed by Slovak Institute of Metrology in Bratislava.