• Journal of Radiation Protection and Research
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• 제40권2호
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• pp.73-78
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• 2015

본 연구에서는 실리콘 광 증배소자(Silicon photomultiplier)와 Ce:GAGG 섬광체 단결정을 이용한 섬광검출기를 제작하고, 감마선 분광특성 분석을 통해 기존에 상용화된 LYSO, CsI:Tl 섬광체와의 분광특성을 비교하였다. 섬광체 단결정의 크기는 $3{\times}3{\times}20mm^3$ 이며 $3{\times}3mm^2$ 실리콘 광 증배소자를 이용하여 섬광검출기를 제작한 후, 표준 감마선원인 $^{133}Ba$, $^{22}Na$, $^{137}Cs$, $^{60}Co$에 대한 에너지 분해능을 각각 측정하고 비교하였다. 그 결과 Ce:GAGG 섬광검출기의 감마선에 대한 에너지 분해능은 $^{133}Ba$ 0.356 MeV에서 13.5%, $^{22}Na$ 0.511 MeV에서 6.9%, $^{137}Cs$ 0.662 MeV에서 5.8% 그리고 $^{60}Co$ 1.33 MeV에서 2.3%의 분광 특성을 확인 할 수 있었다.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2564-2571
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• 2022

SiPMs are generally coupled into whole columns in gamma energy spectrum measurement, but the relationship between the distribution of whole SiPM columns and the energy resolution of the measured energy spectra is rarely reported. In this work, ∅ 3 × 3 inch NaI scintillator is placed on an 8 × 8 SiPM array, and the energy resolution of the ¹³⁷Cs peak at 662 keV corresponding to the γ-ray is selected as a reference. Each SiPM is switched to explore the influence of the number of SiPM arrays, distribution position, and reflective layer on the energy resolution of SiPMs. Results show that without coupling, the energy resolution is greatly improved when the number of SiPMs ranges from 4 to 32. However, after 32 slices (the area covered by SiPMs relative to the scintillator reaches 25.9%), the improvement in energy resolution and total pulse count is not obvious. In addition, the position of SiPMs relative to the scintillator does not exert much impact on the energy resolution. Results also indicate that by adding a reflective film (ESR), the energy resolution of the tested group increases by 10.38% on average. This work can provide a reference for the design and application of miniaturized SiPM gamma spectrometers.

• Nuclear Engineering and Technology
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• 제55권3호
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• pp.1045-1051
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• 2023

In this study, we fabricated a liquid light-guide-based radiation sensor with a LaBr₃:Ce scintillator for remote gamma-ray spectroscopy. We acquired the energy spectra of Cs-137 and Co-60 using the proposed sensor, estimated the energy resolutions of the full energy peaks, and compared the scintillation light output variations. The major peaks of the radionuclides were observed in each result, and the estimated energy resolutions were similar to that of a general NaI(Tl) scintillation detector without a liquid light guide. Moreover, we showed the relationships of energy resolution and analog-to-digital channel regarding the number of photoelectrons produced and confirmed the effects of light guide length on remote gamma-ray spectroscopy. The proposed sensor is expected to be utilized to perform remote gamma-ray spectroscopy for distances of 3 m or more and would find application in many fields of nuclear facilities and industry.

• 한국의학물리학회지:의학물리
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• 제23권3호
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• pp.162-168
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• 2012

양성자 치료에서 치료의 목표를 달성하고 환자의 안전을 제고하기 위해 인체 내 양성자 빔의 분포를 확인하는 것이 중요하다. 양성자 선량분포와 밀접한 관계가 있는 즉발감마선의 2차원 분포 측정을 위하여 본 연구팀에서는 다수의 CsI(Tl) 섬광체가 1차원 종형으로 배열된 검출기 배열과 집속장치 및 다채널 신호처리 장치로 이루어진 측정장치를 개발하고 있다. 이에 본 연구에서 몬테칼로 기반의 MCNPX 코드를 이용하여 최적화된 측정 장치를 설계하고자 하였다. 즉발감마선을 효과적으로 측정하기 위해 CsI(Tl) 섬광체의 크기를 $6{\times}6{\times}50mm^3$로 결정하였으며, 배경감마선의 영향을 최소화하고 빔의 진행방향에서 수직방향으로 발생하는 즉발감마선만 측정하기 위해 집속장치의 구멍 크기는 면적 $6{\times}6mm^2$, 길이 150 mm로 최적화되었다. 150 MeV 양성자 빔에 대한 성능 예측 전산모사연구를 수행한 결과, 본 연구에서 최적화된 측정 장치를 통해 즉발감마선 2차원 분포를 측정할 수 있었으며, 1 mm 오차범위에서 양성자 빔의 비정을 결정할 수 있었다. 이를 바탕으로 현재 다채널의 신호처리 장치를 개발하고 있으며 실제 양성자 빔을 이용한 즉발감마선 분포측정을 통해 측정 장치의 성능을 검증할 것이다.

• 센서학회지
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• 제26권6호
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• pp.427-431
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• 2017

In this study, a foods radioactivity monitoring sensor was developed as a part of basic research for household radioactivity monitoring, and its performance was evaluated using a calibration source. The prototype of the sensor was based on a CsI:Tl scintillator using a crystal light guide and Si photomultiplier. The light guide was introduced to improve gamma-ray detection efficiency. For quantitative evaluation, tests were conducted using $^{134}Cs$ liquid source. In the performance evaluation, It was confirmed that analysis of $^{134}Cs$: 100 Bq/L(kg) was possible. Thus, result of this study is expected to contribute to research in the development of the household foods radioactivity monitoring system.

• Journal of Radiation Protection and Research
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• 제29권4호
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• pp.257-261
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• 2004

핀홀 감마카메라의 민감도를 향상시키기 위하여 픽셀화된 CsI(Tl) 섬광체와 위치민감형 광증배관을 이용하여 부호화 구경 감마카메라를 개발하였다. Rounded-hole로 이루어진 $13{\times}11$ 픽셀구조의 개조된 uniformly reductant array (URA) 가 계측기의 공간해상도를 고려하여 부호화된 마스크로 선택되었다. 부호화된 구경 카메라와 핀홀 카메라의 성능을 비교하기 위하여 Tc-99m 소스의 여러 가지 형태를 이용하여 테스트 하였으며, 신호 대 잡음비 또는 민감도의 향상에 대한 카메라의 성능을 분석하였다. 그 결과 공간해 상도에 있어서 약간의 저하가 있었으나 영상의 질은 매우 향상되었다. 비록 카메라의 개발과 테스트가 저에너지 영역에서 이루어졌지만, 부호화 구경 카메라의 구상은 방사성 물질 감시 그리고 다른 응용들에 있어서도 효과적으로 사용되어질 수 있을 것이다.

• 한국광학회지
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• 제20권4호
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• pp.201-206
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• 2009

본 연구에서는 무기섬광체와 광섬유를 이용하여 삼중수소 검출용 광섬유 방사선 센서를 제작하였다. 무기섬광체 선택을 위해 $Gd_2O_2S$ : Tb, $Y_3Al_5O_{12}$ : Ce, CsI : Tl을 이용하여 센서팁을 제작한 후, 금속 수소화물 형태의 삼중수소를 이용하여 섬광효율이 가장 좋은 섬광체를 선별하였다. 또한 선정된 섬광체를 사용하여 제작한 센서를 이용하여 삼중수소 선원으로부터 거리에 따른 섬광량을 계측하였고 선원의 방사능 세기에 따른 섬광량을 측정하여 표면 방사능 모니터의 결과와 비교 분석하였다.

• Nuclear Engineering and Technology
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• 제53권1호
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• pp.199-207
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• 2021

This paper deals with accurate image reconstruction of gamma camera using a coded-aperture mask based on pixel-type CsI(Tl) scintillator coupled with silicon photomultipliers (SiPMs) array. Coded-aperture imaging (CAI) system typically has a smaller effective viewing angle than Compton camera. Thus, if the position of the gamma source to be searched is out of the fully-coded field-of-view (FCFOV) region of the CAI system, artifacts can be generated when the image is reconstructed by using the conventional cross-correlation (CC) method. In this work, we propose an effective method for more accurate reconstruction in CAI considering the source distribution of partially-coded field-of-view (PCFOV) in the reconstruction in attempt to overcome this drawback. We employed an iterative algorithm based on compressed-sensing (CS) and compared the reconstruction quality with that of the CC algorithm. Both algorithms were implemented and performed a systematic Monte Carlo simulation to demonstrate the possiblilty of the proposed method. The reconstructed image qualities were quantitatively evaluated in sense of the root mean square error (RMSE) and the peak signal-to-noise ratio (PSNR). Our simulation results indicate that the proposed method provides more accurate location information of the simulated gamma source than the CC-based method.

• Nuclear Engineering and Technology
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• 제56권1호
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• pp.56-63
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• 2024

In high radiation fields, gamma cameras suffer from pulse pile-up, resulting in poor energy resolution, count losses, and image distortion. To overcome this problem, various methods have been introduced to reduce the size of the aperture or pixel, reject the pile-up events, and correct the pile-up events, but these technologies have limitations in terms of mechanical design and real-time processing. The purpose of this study is to develop a real-time gamma camera to evaluate the radioactive contamination in high radiation fields. The gamma camera is composed of a pinhole collimator, NaI(Tl) scintillator, position sensitive photomultiplier (PSPMT), signal processing board, and data acquisition (DAQ). The pulse pile-up is corrected in real-time with a field programmable gate array (FPGA) using the start time correction (STC) method. The STC method corrects the amplitude of the pile-up event by correcting the time at the start point of the pile-up event. The performance of the gamma camera was evaluated using a high dose rate ¹³⁷Cs source. For pulse pile-up ratios (PPRs) of 0.45 and 0.30, the energy resolution improved by 61.5 and 20.3%, respectively. In addition, the image artifacts in the ¹³⁷Cs radioisotope image due to pile-up were reduced.

• Nuclear Engineering and Technology
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• 제55권7호
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• pp.2662-2669
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• 2023

For the precise measurements of special nuclear materials (SNM) including Pu and Am isotopes, we have used phoswich detector combination of two single crystal scintillators of Gd₃Ga₃Al₂O₁₂:Ce and CsI:Tl. High detection efficiency and sensitivity along with high figure of merit for the discrimination of these phoswich detectors ensures the detection and discrimination of thermal neutrons and gammas from spontaneous fission of Pu and other isotopes in presence of high gamma background. Using this detector, the low energy gammas, which is stopped completely in 1mm thick disc of GGAG, can be also discriminated from high energies gamma and shows linearity in wide range of sample quantities. By changing only the appropriate shielding, the similar setup was used for thermal neutron detection and shows a very good linearity over wide range. The quantity of a test sample was also calculated accurately by using the measured calibrated plot.