• 한국정밀공학회지
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• 제12권7호
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• pp.46-52
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• 1995

This paper proposes methodologies for the development of radiation thermometer using InSb photo-detector of which spectral sensitivity is excellent over the wave length range of 2 .mu. m .approx. 5 .mu. m. The proposed radiation thermometer has broad measurement range from normal to high, up to more than 1000 .deg. C, with high accuracy, and can measure temperature on the material surface or heat emission noncontactely with high speed. Optical system was consisted of two convex lens with foruslength of 15.2mm for infrared lay focusing, Ge filter to cut the short wave length components and sapphire filter to cut the long wave length components. The cold shielded was installed in the whole surface of the light-absorbing element to remove the error- mometer, calibration using black body furnace which has temperature range of 90 .deg. C .approx. 1100 .deg. C was carried out, and temperature calaibration curve was obtained by exponential function curvefitting. The result shows maximum error less than 0.24%(640K .+-. 1.6K) over the measurement range of 90 .deg. C .approx. 700 .deg. C, and from this result the usefulness of the developed thermometer has been confirmed.

• Journal of Radiation Protection and Research
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• 제30권1호
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• pp.35-37
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• 2005

한국원자력연구소의 방사선 검출기 연구팀에서는 가스 전자 증폭기를 이용하여 고효율 중성자 검출기를 개발하고 있다. 이중 가스 전자 증폭기를 제작하였고 Ar/Isobutane 혼합기체에서 동작시켰다. 고효율 중성자 검출기에 적용하기 위해서 다중 가스 전자 증폭기 포일 양면에 중성자 변환 물질인 $^6Li$ 또는 $^{10}B$를 코팅하는 것이 고려되었다. 중성자 검출을 위한 박막의 최적화된 두께를 MCNP와 SRIM으로 계산하였다. 중성자 검출 효율은 박막을 구성하는 화합물과 박막 두께를 변화시키면서 계산하였다. 열중성자는 drift plate에 중성자 반응 박막을 입힌 GEM 검출기에 의해서 측정되있다.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2002년도 Proceedings
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• pp.411-414
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• 2002

The CdTe semiconductor detector has a higher detection efficiency for x-rays and $\square$amma rays and a wider energy band gap compared with Si and Ge semiconductor detectors. Therefore, the size of the detector element can be made small, and can be operated at room temperature. The interaction between a CdTe detector and incident x-rays is mainly photoelectric absorption in the photon energy range of up to 100 keV. In this energy range, Compton effects are almost negligible. We have developed a 256 channel CdTe array detector system for monochromatic x-ray CT using synchrotron radiation. The CdTe array detector system, the element size of which is 1.98 mm (h) x 1.98 mm (w) x 0.5 mm (t), was operated in photon counting mode. In order to improve the spatial resolution, we tilted the CdTe array detector against the incident parallel monochromatic x-ray beam. The experiments were performed at the BL20B2 experimental hutch in SPring-8. The energy of incident monochromatic x-rays was set at 55 keV. Phantom measurements were performed at the detector angle of 0, 30 and 45 degrees against the incident parallel monochromatic x-rays. The linear attenuation coefficients were calculated from the reconstructed CT images. By increasing the detector angle, the spatial resolutions were improved. There was no significant difference between the linear attenuation coefficients which were corrected by the detector angle. It was found that this method was useful for improving the spatial resolution in a parallel monochromatic x-ray CT system.

• Journal of Radiation Protection and Research
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• 제35권4호
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• pp.167-171
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• 2010

Fixed radiation portal monitors (RPMs) deployed at border, seaport, airport and key traffic checkpoints have played an important role in preventing the illicit trafficking and transport of nuclear and radioactive materials. However, the RPM is usually large and heavy and can't easily be moved to different locations. These reasons motivate us to develop a mobile radiation detection system. The objective of this paper is to report our experience on developing the mobile radiation detection system for search and detection of nuclear and radioactive materials during road transport. Field tests to characterize the developed detection system were performed at various speeds and distances between the radioactive isotope (RI) transporting car and the measurement car. Results of measurements and detection limits of our system are described in this paper. The mobile radiation detection system developed should contribute to defending public's health and safety and the environment against nuclear and radiological terrorism by detecting nuclear or radioactive material hidden illegally in a vehicle.

• Nuclear Engineering and Technology
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• 제50권5호
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• pp.801-805
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• 2018

In this study, an underwater radiation detector was built using a GAGG(Ce) scintillator and silicon photomultiplier to establish an underwater radiation exposure monitoring system. The GAGG(Ce) scintillator is suitable for small radiation detectors as it strongly absorbs gamma rays and has a high light emission rate with no deliquescent properties. Additionally, the silicon photomultiplier is a light sensor with characteristics such as small size and low applied voltage. Further, a program and mobile app were developed to monitor the radiation coefficient values generated from the detector. According to the results of the evaluation of the characteristics of the underwater radiation monitoring system, when tested for its responsiveness to radiation intensity and reactivity, the system exhibited a coefficient of determination of at least 0.99 with respect to the radiation source distance. Additionally, when tested for its underwater environmental temperature dependence, the monitoring system exhibited an increase in the count rate up to a certain temperature because of the increasing dark current and a decrease in the count rate because of decreasing overvoltage. Extended studies based on the results of this study are expected to greatly contribute to immediate and continuing evaluation of the degree of radioactive contamination in underwater environments.

• 한국의학물리학회지:의학물리
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• 제20권4호
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• pp.191-198
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• 2009

이 연구의 목적은 소조사면 선량계측을 위하여 엣지검출기의 성능을 평가하기 위함이다. 다양한 소조사면과 깊이에서 엣지검출기(Model 1118 Edge)를 이용하여 6 MV 광자선의 선량 직선성, 선량률 의존도, 출력 계수, 선량 측면도 및 심부선량 백분율을 따라 측정하였으며, 이를 표준용적의 이온전리함(CC13)과 광자선 다이오드 검출기(PFD)와 비교하였다. 선량 직선성을 일차 선형 맞춤 함수와 비교하였을 때, 세 검출기 모두 1% 미만의 차이를 나타냈으며, 엣지검출기는 -0.08~0.08%의 가장 낮은 차이를 보였다. 선량율의 변화(100~600 MU/min)에 따라 PFD와 엣지검출기의 정규화된 반응비는 1% 미만의 일정한 값을 보였으나, CC13은 100 MU/min에서 약 -5%의 변화를 나타냈다. 조사면의 크기($4{\times}4\;cm^2{\sim}10{\times}10\;cm^2$)에 따른 출력계수는 세 검출기 모두 거의 같은 값을 보였으나, $4{\times}4\;cm^2$ 이하의 소조사면에서는 엣지검출기와 PFD의 출력 계수가 CC13과 최대 21%의 차이보였다. 각 조사면에서 20~80%의 반음영 폭을 측정하였을 때, 평균적으로 CC13은 엣지검출기보다 2배, PFD는 약 30% 정도 더 넓게 나타났다. 또한 10~90%의 반음영의 경우, CC13과 PFD가 각각 55%와 19% 정도 더 넓은 폭을 나타냈다. 엣지검출기는 선량 측면도의 반치폭이 조사면의 크기와 거의 일치하였으나, 다른 두 검출기는 조사면의 크기보다 약 8~10% 더 크게 나타났으며, 심부선량백분율은 각 조사면에서 세 검출기 모두 거의 일치하였다. 엣지검출기의 성능평가를 위한 선량특성을 분석한 결과, $4{\times}4\;cm^2$ 이하의 소조사면에서 가장 적합한 특성을 나타냈으며, CC13과 PFD와 같은 검출기는 조사면이 작을수록 상당한 오차를 나타낼 수 있음을 알 수 있었다.

• 한국전기전자재료학회:학술대회논문집
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• 한국전기전자재료학회 2007년도 하계학술대회 논문집 Vol.8
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• pp.328-328
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• 2007

Large area matrix-addressed image detectors are a recent technology for x-ray imaging with medical diagnostic and other applications. The imaging properties of x-ray pixel detectors depend on the quantum efficiency of x-rays, the generated signal of each x-ray photon and the distribution of the generated signal between pixels. In a phosphor coated detector the light signal is generated by electrons captured in the phosphor screen. In our study we simulated the lateral spread distributions for phosphor coupled detector by Monte Carlo simulations. Most simulations of such detectors simplify the setup by only taking the conversion layer into account neglecting behind. The Monte Carlo code MCNPX has been used to simulate the complete interaction and subsequent charge transport of x-ray radiation. This has allowed the analysis of charge sharing between pixel elements as an important limited factor of digital x-ray imaging system. The parameters are determined by lateral distribution of x-ray photons and x-ray induced electrons. The primary purpose of this study was to develop a design tool for the evaluation of geometry factor in the phosphor coupled optical imaging detector. In order to evaluate the spatial resolution for different phosphor material, phosphor geometry we have developed a simulation code. The developed code calculates the energy absorption and spatial distribution based on both the signal from the scintillating layer and the signal from direct detection of x-ray in the detector. We show that internal scattering contributes to the so-called spatial resolution drop of the image detector. Results from the simulation of spatial distribution in a phosphor pixel detector are presented. The spatial resolution can be increased by optimizing pixel size and phosphor thickness.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2006년도 제33회 추계학술대회 발표논문집
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• pp.114-114
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• 2006

• 대한전자공학회:학술대회논문집
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• 대한전자공학회 2000년도 하계종합학술대회 논문집(5)
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• pp.106-109
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• 2000

The diode characteristics for therapy radiation sensor have been studied by irradiating therapy radiation from the MM22 microtron accelerator. Signal processing has been performed in the pulse mode which can process the signal fast. We have designed integrator, peak detector and synchronization circuit to detect diode signal in the pulse mode for implementation of portal image. We also read the diode signal by A/D board and displayed the peak value with LabView program. Because the quality of portal image obtained by film in the case of therapy radiation is much worse than that of diagnostic film, Digital radiography system by rectifier diode detector was suggested for portal Image.

• Nuclear Engineering and Technology
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• 제55권12호
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• pp.4329-4334
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• 2023

In this research, a prompt gamma neutron activation analysis (PGNAA) system is designed and constructed based on the use of a low power research reactor. For this purpose, despite the fact that this reactor did not include beam tubes, a thermal neutron beam line is installed inside the reactor tank. The extraction of the beam line from inside the tank made it possible to provide the neutron flux from the order of 106 n.cm^-2.s^-1. Also, because the beam line is installed in a tangential position to the reactor core, its gamma level has been minimized. Also, a suitable radiation shield is considered for the detector to minimize the background radiation and prevent radiation damage to the detector. Calculations and measurements are done in order to characterize this system, as well as spectrometry of several samples. The results of evaluations and experiments show that this system is suitable for performing PGNAA.