• Nuclear Engineering and Technology
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• 제54권2호
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• pp.437-441
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• 2022

In this study, we developed a neutron time-of-flight (nTOF) measurement system for a 1.7-MV tandem proton accelerator with a target covered with 300-nm-thick lithium (Li) layer. With implementation of beam chopping module after its ion source, the accelerator is configured to operate in pulsed-beam mode with a pulse width <50 ns at 20-kHz repetition rate. This enables the gamma flash-type nTOF measurement system to identify the neutron generated with 3-MeV proton beam energy. The nTOF system consists of a 30" cylindrical NaI(Tl) and four stilbene scintillation detectors. The NaI(Tl) scintillator is placed 50 cm from the Li target to measure the time of beam irradiation on the target, and the stilbene detectors are placed 2 and 2.4 m away to measure nTOF at each location. The nTOF system successfully measured the generated neutron energy at irradiated proton energies of 2.6 and 3.0 MeV with an average energy resolution of 15%.

• 한국방사선학회논문지
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• 제13권6호
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• pp.825-830
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• 2019

두 층의 섬광체와 각 층별 서로 다른 반사체의 사용과 섬광체와 감마선의 상호작용으로 발생한 빛 신호를 측정하기 위한 광센서로써 실리콘광전증배관(Silicon Photomultiplier, SiPM)을 사용하여 반응 깊이를 측정하는 검출기를 개발하였다. 층별 섬광 픽셀의 반사체의 종류를 다르게 사용함으로써 획득한 신호를 바탕으로 영상을 재구성할 경우 모든 섬광 픽셀이 서로 다른 위치에 기록되는 특징을 활용하여 섬광 픽셀과 감마선이 반응한 위치를 추적하였다. 아래층은 거울반사체를 사용하였으며, 위층은 난반사체를 사용하여 SiPM에서 획득되는 신호의 크기를 다르게 처리하였다. 섬광체 사이와 SiPM과 연결되는 부분은 광학적으로 연결되도록 광학 그리즈를 사용하여 급격한 굴절률 변화를 감소시켰다. 16개의 SiPM에서 획득한 신호는 앵거 방정식을 사용하여 4개의 신호로 감소시켰으며, 이를 사용하여 영상을 재구성하였다. 두 층으로 구성된 모든 섬광 픽셀이 재구성된 영상에 나타났으며, 이를 통해 섬광 픽셀과 감마선이 반응한 층을 구분할 수 있었다. 서로 다른 반사체를 사용하여 두 층의 반응 깊이를 측정하는 검출기를 전 임상용 양전자방출단층촬영기기에 적용할 경우 관심 시야 외곽에서 나타나는 공간분해능의 저하 현상을 해결할 수 있을 것으로 판단된다.

• 한국방사선학회논문지
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• 제17권1호
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• pp.31-36
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• 2023

소동물 전용의 영상 및 치료기기 중 양전자방출단층촬영기기(positron emission tomography, PET)는 관심 시야 내에서 공간분해능의 변화가 발생한다. 이는 작은 갠트리와 작고, 긴 섬광 픽셀을 사용함으로써 발생하는 현상으로 이를 해결하기 위해 반응 깊이를 측정하는 검출기들이 개발 및 연구되고 있다. 본 연구에서는 여러 개의 섬광체 블록과 서로 다른 반사체 패턴을 지닌 광가이드를 사용하여 반응 깊이를 측정하는 검출기를 설계하였다. 3 mm × 3 mm × 5 mm의 섬광 픽셀을 4 × 4 배열로 구성한 섬광체 블록이 4개의 층을 이루고, 각 층마다 광가이드를 삽입하여 전체 검출기를 구성하였다. 반응 깊이 측정 여부를 확인하기위해, 모든 섬광 픽셀의 중심에서 감마선 반응을 발생시켜 데이터를 획득 후 평면 영상으로 재구성하였다. 층 사이에 삽입된 광가이드의 반사체 패턴이 모두 달라 각 층별 섬광 픽셀의 위치가 서로 다른 곳에 형성되었다. 이렇게 형성된 섬광 픽셀의 위치를 모두 분리하여 영상의 재구성에 사용하면 관심시야 모든 영역에 걸쳐 고른 공간분해능을 달성할 수 있을 것으로 판단된다.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1999년도 추계학술대회 논문집 학회본부 B
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• pp.754-756
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• 1999

In this paper, we have developed a high-sensitivity SNRD(Semiconductor Nuclear Radiation Detector) using silicon PIN photodiode. The SNRD is constructed with silicon PIN photodiode(S3590-05), preamplifier and shaping amplifier. To show the effectiveness of SNRD, nuclear radiation experiments are conducted with $\gamma$-ray Ba-133, Cs-137 and Co-60. The SNRD is different in characteristics of the energy spectrum to scintillation detectors. However, the SNRD have a good linearity on $\gamma$-ray energy and activity. The results of this paper can be applied to electronic personal dosimeter.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2002년도 Proceedings
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• pp.35-37
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• 2002

Conceptual design of the next generation PET with both high sensitivity and high spatial resolution has been performed. A detector unit using a depth encoding scheme was designed and constructed for trial. The unit consists of four Gd$_2$SiO$\sub$5/:Ce crystal blocks in a 2x2x4 array coupled to a position-sensitive photomultiplier tube having metal channel dynodes and 4x4 multi-anodes. Our proposed detector is a very reliable and simple solution suitable for volume PET devices since the proposed depth encoding scheme does not need additional photo-detectors.

• Journal of Radiation Protection and Research
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• 제12권1호
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• pp.54-60
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• 1987

The quasi-exposure rate and the quasi-effective energy of the natural radiation in the field at 47 monitoring points around nuclear power plants have been studied with the pair filter thermoluminescence dosimeter system. The results of the six years observation showed that the relationship between the quasi-exposure rate $X_q$, and quasi-effective energy $E_q$ can be represented as a hyperbolic function: $X_q=A+C/(E_q-B)$, where the constants A and B correspond to the quasi-exposure rate of cosmic-rays and the minimum quasi-effective energy of natural radiation, respectively. Furthermore, the constant A is in close agreement with the values obtained by using ionization chambers and scintillation detectors. The constant B is approximately 0.68 MeV, closely corresponding to the mean energy of the photons emitted from natural uranium.

• Nuclear Engineering and Technology
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• 제53권4호
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• pp.1259-1265
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• 2021

In the present study, a large-area hybrid gamma imaging system was designed by adopting coded aperture imaging on the basis of a large-area Compton camera to achieve high imaging performance throughout a broad energy range (100-2000 keV). The system consisting of a tungsten coded aperture mask and monolithic NaI(Tl) scintillation detectors was designed through a series of Geant4 Monte Carlo radiation transport simulations, in consideration of both imaging sensitivity and imaging resolution. Then, the performance of the system was predicted by Geant4 Monte Carlo simulations for point sources under various conditions. Our simulation results show that the system provides very high imaging sensitivity (i.e., low values for minimum detectable activity, MDA), thus allowing for imaging of low-activity sources at distances impossible with coded aperture imaging or Compton imaging alone. In addition, the imaging resolution of the system was found to be high (i.e., around 6°) over the broad energy range of 59.5-1330 keV.

• Nuclear Engineering and Technology
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• 제55권9호
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• pp.3133-3139
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• 2023

Neutron imaging technology as a means of non-destructive detection of materials is complementary to X-ray imaging. Silicon photomultiplier (SiPM), a new type of optical readout device, has overcome some shortcomings of traditional photomultiplier tube (PMT), such as high-power consumption, large volume, high price, uneven gain response, and inability to work in strong magnetic fields. Its application in the field of neutron detection will be an irresistible general trend. In this paper, a thermal neutron imaging detector based on ⁶LiF/ZnS scintillation screen and SiPM array readout was developed. The design of the detector geometry was optimized by geant4 Monte Carlo simulation software. The optimized detector was evaluated with a step wedge sample. The results show that the detector prototype with a 48 mm × 48 mm sensitive area can achieve about 38% detection efficiency and 0.26 mm position resolution when using a 300 ㎛ thick ⁶LiF/ZnS scintillation screen and a 2 mm thick Bk7 optical guide coupled with SiPM array, and has good neutron imaging capability. It provides effective data support for developing high-performance imaging detectors applied to the China Spallation Neutron Source (CSNS).

• Journal of Radiation Protection and Research
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• 제43권3호
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• pp.85-96
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• 2018

Background: A variety of inorganic scintillators have been developed and improved for use in radiation detection and measurement, and in situ gamma-ray spectrometry in the environment remains an important area in nuclear safety. In order to verify the feasibility of promising scintillators in an actual environment, a performance test is necessary to identify gamma-ray peaks and calculate the radioactivity from their net count rates in peaks. Materials and Methods: Among commercially available scintillators, $LaBr_3(Ce)$ scintillators have so far shown the highest energy resolution when detecting and identifying gamma-rays. However, the intrinsic background of this scintillator type affects efficient application to the environment with a relatively low count rate. An algorithm to subtract the intrinsic background was consequently developed, and the in situ calibration factor at 1 m above ground level was calculated from Monte Carlo simulation in order to determine the radioactivity from the measured net count rate. Results and Discussion: The radioactivity of six natural radionuclides in the environment was evaluated from in situ gamma-ray spectrometry using an $LaBr_3(Ce)$ detector. The results were then compared with those of a portable high purity Ge (HPGe) detector with in situ object counting system (ISOCS) software at the same sites. In addition, the radioactive cesium in the ground of Jeju Island, South Korea, was determined with the same assumption of the source distribution between measurements using two detectors. Conclusion: Good agreement between both detectors was achieved in the in situ gamma-ray spectrometry of natural as well as artificial radionuclides in the ground. This means that an $LaBr_3(Ce)$ detector can produce reliable and stable results of radioactivity in the ground from the measured energy spectrum of incident gamma-rays at 1 m above the ground.

• 대한의용생체공학회:의공학회지
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• 제18권3호
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• pp.267-272
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• 1997

3.6cm${\times}$2.0cm (지름 ${\times}$ 두께) 크기의 $BaF^2$ 섬광체로 검출기를 제작하여 감마 카메라등 의료용 진단장치에서 센서로 사용되고 있는 NaI(씨)검출기와 방사선 검출특성을 비교하여 보았다. 특정에 사용된 선원은 $^{22}Na,\;^{54}Mn,\;^{57}Co,\;^{137}Cs$의 ${\gamma}$선 방출선원으로 검출기와 선원간의 거리를 7cm로 유지하였다. 시간특성을 분석하기 위하여 511keV의 양전자 방출선원을 사용하여 NaI(Tl)(1" ${\times}$ 1"), NaI(Tl)(3" ${\times}$ 3")순으로 $BaF^2$가 가장 빠르게 나타났으며, $BaF^2$ 검출기의 효율은 500keV에서 가장 높게 측정되었다.