Nuclear Engineering and Technology

  • 제55권5호
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  • Pages.1718-1733
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  • 2023
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Positional correction of a 3D position-sensitive virtual Frisch-grid CZT detector for gamma spectroscopy and imaging based on a theoretical assumption

  • Younghak Kim (Health Science Research Center, Korea University) ;
  • Kichang Shin (Department of Health and Safety Convergence Science, Korea University) ;
  • Aleksey Bolotnikov (Instrumentation Division, Brookhaven National Laboratory) ;
  • Wonho Lee (School of Health and Environmental Science, Korea University)
  • 투고 : 2022.08.11
  • 심사 : 2023.01.15
  • 발행 : 2023.05.25
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⟨ 이전 논문 다음 논문 ⟩

초록

The virtual Frisch-grid method for room-temperature radiation detectors has been widely used because of its simplicity and high performance. Recently, side electrodes were separately attached to each surface of the detectors instead of covering the entire detector surface with a single electrode. The side-electrode structure enables the measurement of the three-dimensional (3D) gamma-ray interaction in the detector. The positional information of the interaction can then be utilized to precisely calibrate the response of the detector for gamma-ray spectroscopy and imaging. In this study, we developed a 3D position-sensitive 5 × 5 × 12 mm3 cadmium-zinc-telluride (CZT) detector and applied a flattening method to correct detector responses. Collimated gamma-rays incident on the surface of the detector were scanned to evaluate the positional accuracy of the detection system. Positional distributions of the radiation interactions with the detector were imaged for quantitative and qualitative evaluation. The energy spectra of various radioisotopes were measured and improved by the detector response calibration according to the calculated positional information. The energy spectra ranged from 59.5 keV (emitted by 241Am) to 1332 keV (emitted by 60Co). The best energy resolution was 1.06% at 662 keV when the CZT detector was voxelized to 20 × 20 × 10.

키워드

과제정보

This work was supported by the Nuclear Safety Research Program through the National Research Foundation of Korea (NRF) granted by the Ministry of Science and ICT (MSIT) of the Republic of Korea (No. 2020R1A2C1005924, No. 2021M2E8A1046041), and the Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korean government (MOTIE) (20214000000070, Promoting Expert for Energy Industry Advancement in the Field of Radiation Technology).

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