Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Analytical-numerical formula for estimating the characteristics of a cylindrical NaI(Tl) gamma-ray detector with a side-through hole

  • Thabet, Abouzeid A. (Department of Biomedical Equipment Technology, Faculty of Applied Health Sciences Technology, Pharos University in Alexandria) ;
  • Badawi, Mohamed S. (Department of Physics, Faculty of Science, Beirut Arab University)
  • Received : 2021.12.28
  • Accepted : 2022.04.25
  • Published : 2022.10.25
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Abstract

NaI(Tl) scintillation materials are considered to be one of many materials that are used exclusively for γ-ray detection and spectroscopy. The gamma-ray spectrometer is not an easy-to-use device, and the accuracy of the numerical values must be carefully checked based on the rules of the calibration technique. Therefore, accurate information about the detection system and its effectiveness is of greater importance. The purpose of this study is to estimate, using an analytical-numerical formula (ANF), the purely geometric solid angle, geometric efficiency, and total efficiency of a cylindrical NaI(Tl) γ-ray detector with a side-through hole. This type of detector is ideal for scanning fuel rods and pipelines, as well as for performing radio-immunoassays. The study included the calculation of the complex solid angle, in combination with the use of various points like gamma sources, located axially and non-axially inside the through detector side hole, which can be applied in a hypothetical method for calibrating the facility. An extended γ-ray energy range, the detector, source dimensions, "source-to-detector" geometry inside the side-through hole, path lengths of γ-quanta photons crossing the facility, besides the photon average path length inside the detector medium itself, were studied and considered. This study is very important for an expanded future article where the radioactive point source can be replaced by a volume source located inside the side-trough hole of the detector, or by a radioactive pipeline passing through the well. The results provide a good and useful approach to a new generation of detectors that can be used for low-level radiation that needs to be measured efficiently.

Keywords

Acknowledgement

The authors, as specialists in the field of radiation measurements and calibration methods, would like to thank SCIONIX Holland BV in the Netherlands, specialized in the design and manufacture of devices for detecting nuclear radiation based on the scintillation principle, for providing a geometric drawing of the detector, without which this study could not have been successfully carried out.

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