• Nuclear Engineering and Technology
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• 제49권4호
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• pp.776-780
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• 2017

To avoid imaging artifacts and interpretation mistakes, an improvement of the uniformity in gamma camera systems is a very important point. We can expect excellent uniformity using cadmium zinc telluride (CZT) photon counting detector (PCD) because of the direct conversion of the gamma rays energy into electrons. In addition, the uniformity performance such as integral uniformity (IU), differential uniformity (DU), scatter fraction (SF), and contrast-to-noise ratio (CNR) varies according to the energy window setting. In this study, we compared a PCD and conventional scintillation detector with respect to the energy windows (5%, 10%, 15%, and 20%) using a $^{99m}Tc$ gamma source with a Geant4 Application for Tomography Emission simulation tool. The gamma camera systems used in this work are a CZT PCD and NaI(Tl) conventional scintillation detector with a 1-mm thickness. According to the results, although the IU and DU results were improved with the energy window, the SF and CNR results deteriorated with the energy window. In particular, the uniformity for the PCD was higher than that of the conventional scintillation detector in all cases. In conclusion, our results demonstrated that the uniformity of the CZT PCD was higher than that of the conventional scintillation detector.

• Journal of Radiation Protection and Research
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• 제35권2호
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• pp.69-76
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• 2010

현재 개발중에 있는 이중 산란형 컴프턴 카메라는 두 대의 산란부 검출기(양면 실리콘 스트립 검출기, DSSD)와 하나의 흡수부 검출기(NaI(Tl) 섬광 검출기)로 구성되며, 소형이면서도 높은 영상해상도를 제공할 수 있는 구조를 가지고 있다. 본 연구에서는 이중 산란형 컴프턴 카메라를 구성하고 있는 감마선 검출기들의 에너지 분해능 및 시간 분해능을 평가하고, 산란부 검출기의 에너지 분해능에 영향을 미치는 인자들을 등가 노이즈 전하(equivalent noise charge)를 통하여 분석하였다. DSSD-1은 평균적으로 59.5 keV 피크($^{241}Am$)에 대하여 $25.2keV{\pm}0.8keV$ FWHM의 에너지 분해능을 보였으며, DSSD-2는 $31.8keV{\pm}4.6keV$ FWHM의 에너지 분해능 지니고 있는 것으로 확인되었다. DSSD의 시간 분해능은 57.25 ns FWHM으로 평가되었고, NaI(Tl) 섬광 검출기의 시간 분해능은 7.98 ns FWHM이었다. 또한 이중산란형 컴프턴 카메라를 이용하여 $^{137}Cs$ 점선원에 대한 컴프턴 영상을 획득한 후 성능을 평가하였다. 이번 실험을 통해서 영상해상도 8.4 mm FWHM (각 분해능 $8.1^{\circ}$ FWHM)을 획득하였고, 영상감도는 $1.5{\times}10^{-7}$(고유 효율=$1.9{\times}10^{-6}$)으로 나타났다.

• 대한화학회지
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• 제6권2호
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• pp.155-157
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• 1962

A tiny dust found at the balcony of the Institute indicated about 8,0000 counts per minute by T.G.C.-2 Geiger-Muller tube (1.8mg/$cm^2$ window-thickness) at the distance of 2cm from the window. The main fission fragments, as identified by the present analysis, are 12.5day Ba-140 and 33.1 day Ce-141. The gamma energies were determined using $2"{\times}2"$ NaI(Tl) scintillation detector connected to RCL-256 channel pulse heigt analyzer. The beta energies were evaluated by Feather plot.

• 한국방사선학회논문지
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• 제14권5호
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• pp.511-515
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• 2020

본 연구의 목적은, 새롭게 제안된 Gadolinium Aluminum Gallium Garnet (GAGG) 기반 감마카메라를 Geant 4 Application for Tomographic Emission (GATE) 모사 도구(simulation tool)를 통해 설계하고, National Electrical Manufacturers Association International Electrotechnical Commission에서 제작한 몸통 팬텀 모사를 통해 기존의 사용되고 있는 NaI(Tl) 섬광체 기반 감마카메라 시스템과 99mTc 방사성동위원소를 이용해 900 초 동안 영상을 획득했다. Contrast to noise ratio (CNR) 과 Coefficient of variation (COV) 의 정량분석 방법을 사용해 해당 관심영역에 대해 영상을 평가하였다. CNR 과 COV 결과에 따라, 결과적으로 GAGG 기반 감마 영상의 질이 우수함을 확인하였다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(2)
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• pp.464-469
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• 1998

A coincidence gamma-ray spectroscopy method was applied to reduce the background radioactivity for measuring the activity of radioisotopes in a sample in the presence of environmental natural radioactivity. A HPGe detector was used for the coincident spectrum as a main detector and a NaI(Tl) scintillation detector for gating purposes as an associated detector. For coincidence spectroscopy the whole energy spectrum of associated detector was used instead of gate signals. The coincident events obtained from the gating spectrum was evaluated by a coincidence computer program in this study instead of timing circuit. In this work, the background of detection environment was reduced to factor 100 and peaks to be determined was reduced to factor 30 using the coincidence gamma-ray spectroscopy.

• Journal of Radiation Protection and Research
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• 제42권3호
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• pp.158-165
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• 2017

Background: Nuclear facilities in South Korea have generally adopted pressurized ion chambers to measure ambient gamma ray exposure rates for monitoring the impact of radiation on the surrounding environment. The rates assessed with pressurized ion chambers do not distinguish between natural and man-made radiation, so a further step is needed to identify the cause of abnormal variation. In contrast, using NaI(Tl) scintillation detectors to detect gamma energy rates can allow an immediate assessment of the cause of variation through an analysis of the energy spectra. Against this backdrop, this study was conducted to propose a more effective way to monitor ambient gamma exposure rates. Materials and Methods: The following methods were used to analyze gamma energy spectra measured from January to November 2016 with NaI detectors installed at the Korea Atomic Energy Research Institute (KAERI) dormitory and Hanbat University. 1) Correlations of the variation of rates measured at the two locations were determined. 2) The dates, intervals, duration, and weather conditions were identified when rates increased by $5nSv{\cdot}h^{-1}$ or more. 3) Differences in the NaI spectra on normal days and days where rates spiked by $5nSv{\cdot}h^{-1}$ or more were studied. 4) An algorithm was derived for automatically calculating the net variation of the rates. Results and Discussion: The rates measured at KAERI and Hanbat University, located 12 kilometers apart, did not show a strong correlation (coefficient of determination = 0.577). Time gaps between spikes in the rates and rainfall were factors that affected the correlation. The weather conditions on days where rates went up by $5nSv{\cdot}h^{-1}$ or more featured rainfall, snowfall, or overcast, as well as an increase in peaks of the gamma rays emitted from the radon decay products of $^{214}Pb$ and $^{214}Bi$ in the spectrum. This study assumed that $^{214}Pb$ and $^{214}Bi$ exist at a radioactive equilibrium, since both have relatively short half-lives of under 30 minutes. Provided that this assumption is true and that the gamma peaks of the 352 keV and 1,764 keV gamma rays emitted from the radionuclides have proportional count rates, no man-made radiation should be present between the two energy levels. This study proved that this assumption was true by demonstrating a linear correlation between the count rates of these two gamma peaks. In conclusion, if the count rates of these two peaks detected in the gamma energy spectrum at a certain time maintain the ratio measured at a normal time, such variation can be confirmed to be caused by natural radiation. Conclusion: This study confirmed that both $^{214}Pb$ and $^{214}Bi$ have relatively short half-lives of under 30 minutes, thereby existing in a radioactive equilibrium in the atmosphere. If the gamma peaks of the 352 keV and 1,764 keV gamma rays emitted from these radionuclides have proportional count rates, no man-made radiation should exist between the two energy levels.

• Journal of Radiation Protection and Research
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• 제48권3호
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• pp.153-161
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• 2023

Background: Fukushima Medical University (FMU) is located 57 km northwest of the Fukushima Daiichi Nuclear Power Plant. Our laboratory has been conducting environmental radiation measurements continuously before and after the nuclear accident. We aimed to report the observed behavior of radiation originating from the released radioactive materials due to the accident, predict future trends, and disseminate the results to the local residents. Materials and Methods: Measurements of the counting rate by a diameter of 76 mm and a length of 76 mm thallium-doped sodium iodide (NaI[Tl]) scintillation detector (S-1211-T; Teledyne Brown Engineering Environmental Services) in the central part of the laboratory, and the dose rate outward at the window by NaI(Tl) scintillation detector and digital processor (EMF211; EMF Japan Co. Ltd.) were conducted. Results and Discussion: Measurements by Teledyne S-1211-T showed that in the early stages, radiation from radioactive isotopes with short half-lives was dominant, while radiation from radioactive isotopes with longer half-lives became dominant as the measurement period became longer. Through nonlinear least squares regression, both short and long half-lives were successfully determined. It was also possible to predict how the radiation dose would decrease. The environmental radiation trends around FMU were measured by the EMF211. Both measurements were affected by rainfall and snow accumulation. Decontamination work on the FMU campus impacted measurements by the EMF211 especially. Conclusion: The results of two types of measurements, one at the center and the other at the window side of the laboratory, were presented. By applying a simplified model, radiation from radioactive isotopes with short and long half-lives was identified. Based on these results, future trends were predicted, and the information was used for public communication with the local residents.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1997년도 한국자동제어학술회의논문집; 한국전력공사 서울연수원; 17-18 Oct. 1997
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• pp.1371-1374
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• 1997

We had developed the on-line environmental monitoring system which has installed around Kori Nuclear Power Plants and will be taken the place of the existing system. The system consists of a main computer and 11 sets of radiation monitoring post equipments. Nal(Tl) scintillation detectro was adopted in addition to ion-chamber detector and implemented with DCU(Dose Conversion Unit) and SCA(Single Channel Analyzer). Compared with the existing system, it has revised feature in the radiation measurements which are detection of artificial radioactivity and 2-ways of the radiatiion detectors. The field test trsults show that the developed radiation detecting equipments can measure environmental radiation withn 5.0% of the theoretical value.

• 전기전자학회논문지
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• 제21권4호
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• pp.408-411
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• 2017

본 논문에서는 중성자, 감마선, 엑스선 등의 방사선을 측정하는 통합 제어 시스템을 제안한다. 제안하는 시스템은 원격 또는 네트워크상으로 측정 및 분석한 데이터를 디스플레이를 통해 모니터링 및 제어할 수 있는 장비로서, 현장에 가지 않고도 시스템 각 구성 부분의 상태를 보고 변경하여 원격으로 감시 및 관리할 수 있다. 제안하는 시스템은 감마선/엑스선 센서부, 중성자 센서부, 주제어 임베디드 시스템부, 전용 디스플레이 장치 및 GUI부, 원격 UI부 등으로 구성된다. 감마선/엑스선 센서부는 NaI(Tl) Scintillation Detector를 사용하여 저준위의 감마선 및 엑스선을 측정한다. 중성자 센서부는 Proportional Counter Detector(저준위 중성자)와 Ion Chamber Type Detector(고준위 중성자)를 사용하여 중성자를 측정한다. 주제어 임베디드 시스템부는 방사선을 검출하여 초단위로 샘플링하고 누적된 펄스 및 전류값에 대한 방사선량으로 변환한다. 전용 디스플레이 장치 및 GUI부는 방사선 측정 결과와 변환된 방사선량 및 방사능량 측정 수치를 출력하고, 사용자에게 제어 조건 설정 및 검출부에 대한 캘리브레이션 기능을 제공한다. 원격 UI부는 측정된 값들을 취합, 저장하여 원격 감시 시스템에 전달한다. 제안된 시스템의 성능을 평가하기 위하여 공인시험기관에서 실험한 결과는 중성자 검출부는 ${\pm}8.2%$ 이하의 측정 불확도가 측정되었고, 감마선, 엑스선 검출부는 7.5%이하의 불확도가 측정되어 국제 표준인 ${\pm}15%$ 이하에서 정상동작 됨이 확인되었다.

• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2640-2645
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• 2021

We report the development of a gamma-ray imaging device, named Large-Area Hybrid Gamma Imager (LAHGI), featuring high imaging sensitivity and good imaging resolution over a broad energy range. A hybrid collimation method, which combines mechanical and electronic collimation, is employed for a stable imaging performance based on large-area scintillation detectors for high imaging sensitivity. The system comprises two monolithic position-sensitive NaI(Tl) scintillation detectors with a crystal area of 27 × 27 cm² and a tungsten coded aperture mask with a modified uniformly redundant array (MURA) pattern. The performance of the system was evaluated under several source conditions. The system showed good imaging resolution (i.e., 6.0-8.9° FWHM) for the entire energy range of 59.5-1330 keV considered in the present study. It also showed very high imaging sensitivity, successfully imaging a 253 µCi ¹³⁷Cs source located 15 m away in 1 min; this performance is notable considering that the dose rate at the front surface of the system, due to the existence of the ¹³⁷Cs source, was only 0.003 µSv/h, which corresponds to ~3% of the background level.