• 대한방사선방어학회:학술대회논문집
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• 대한방사선방어학회 2009년도 춘계 학술발표
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• pp.130-131
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• 2009

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• 설비공학논문집
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• 제18권8호
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• pp.672-677
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• 2006

The steady cooling characteristics of a cryochamber for infrared (IR) detector have been investigated analytically, considering radiation shields. The thermal modeling considers the conduction heat transfer through cold finger, the gaseous conduction due to out-gassing, and the radiation heat transfer. The cooling load of the cryochamber is obtained by using a fin equation. The results obtained indicate that the gaseous conduction plays an important role in determining the steady cooling load. The steady cooling load is increased as the gas pressure is increased. It is also found that the cooling load is substantially decreased with a radiation shield. The most thermal load of a cryochamber occurs through the cold finger.

• 한국정보통신학회:학술대회논문집
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• 한국정보통신학회 2016년도 춘계학술대회
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• pp.778-779
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• 2016

본 논문에서는 공간상에 분포된 방사선원에 대해 화소단위로 방사선 신호를 탐지하기 위한 섬광 검출기를 설계하고, 탐지신호를 취득하기 위한 모듈을 설계하여 방사선 영상화를 위한 연구를 수행하였다. 방사선 분포측정을 위해 적용한 검출기는 CsI(Tl) 섬광체와 결합효율이 높은 수광센서로 구성하였으며, 수광센서를 통해 획득된 신호를 처리하기 위해 펄스 신호를 증폭, 성형 한 후 임계치를 기준으로 펄스를 계수하기 위한 장치를 구현하였다. 제작된 검출기의 성능을 검증하기 위해 감마선 교정시설을 이용하여 검출기에 대한 성능 시험을 수행하고 그 결과를 분석하였다. 본 논문의 결과는 제작된 검출기에 방향성을 부여하기 위한 차폐체 및 조사부를 적용한 후 방향을 이동시켜 개별적인 영역의 값을 2차원 적으로 나타냄으로써 선원의 분포측정을 위한 기초자료로 활용될 것이다.

• Journal of Radiation Protection and Research
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• 제25권4호
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• pp.197-205
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• 2000

실리콘 PIN 다이오드 검출기를 이용하여 전자선량계(PED)를 설계 및 제작하고, 전자신호회로의 성능과 방사선 검출 반응특성을 평가하였다. 전자회로의 성능검사에서는 방사선에 의한 검출기의 신호가 신호처리회로에서 양호하게 출력되었으며, $^{137}Cs$ 감마 방사선을 이용한 방사선조사 시험결과 선량계의 반응도 및 분산계수는 각각 1.85 cps/$Gy{\cdot}h^{-1}$ 및 19.3%로 측정되어 전자선량제의 성능기준을 만족하는 것으로 나타났다. 본 전자선량계의 시작품은 향후 전자회로의 성능향상과 작동 프로그램을 보완 및 개선함으로써 개인 방사선 모니터링에 활용될 것으로 기대된다.

• 제어로봇시스템학회논문지
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• 제9권4호
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• pp.296-303
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• 2003

A personal portable type electronic dosimeter using silicon PIN photodiode and small GM tube is recently attracting much attention due to its advantages such as an immediate indication function of dose and dose rate, alerting function, and efficient management of radiation exposure history and dose data. We designed and manufactured a semiconductor radiation detector aimed to directly measure X-ray and v-ray irradiated in silicon PIN photodiode, without using high-priced scintillation materials. Using this semiconductor radiation detector, we developed an active electronic dosimeter, which measures the exposure dose using pulse counting method. In this case, it has a shortcoming of over-evaluating the dose that shows the difference between the dose measured with electronic dosimeter and the dose exposed to the human body in a low energy area. We proposed an energy compensation filter and developed a dose conversion algorithm to make both doses indicated on the detector and exposed to the human body proportional to each other, thus enabling a high-precision dose measurement. In order to prove its reliability in conducting personal dose measurement, crucial for protecting against radiation, the implemented electronic dosimeter was evaluated to successfully meet the IEC's criteria, as the KAERI (Korea Atomic Energy Research Institute) conducted test on dose indication accuracy, and linearity, energy and angular dependences.

• 한국방사선학회논문지
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• 제14권6호
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• pp.725-731
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• 2020

구(sphere)형의 섬광체를 사용한 방사선 스펙트로스코피 검출기를 설계하였고, 여러 대의 검출기를 사용하여 방사선원의 위치를 추적하는 시스템을 개발하였다. 방사선원의 위치 추적은 방사선의 수는 거리의 역자승 법칙에 따라 감소하는 이론을 바탕으로 위치 추적 알고리듬을 설계하였으며, 여러 위치의 방사선원에서 발생된 방사선의 수를 측정하여 알고리듬을 통해 위치를 계산하였다. 방사선원에서 발생되는 방사선은 각 검출기에서 서로 다른 계수로 검출되며, 이러한 검출되는 계수의 차이는 거리의 역자승에 비례하여 달라진다. 설계한 방사선원 위치 추적 시스템의 성능을 검증 및 평가하기 위해 Geant4 Application for Tomographic Emission (GATE) 시뮬레이션을 실시하였으며, 서로 다른 위치에 놓이 방사선원에서 발생된 방사선을 각 검출기로 계수하였다. 측정된 방사선의 수는 방사선원 위치 추적 알고리듬을 통해 위치가 추적되었으며, 실제 방사선원의 위치와 알고리듬으로 계산된 위치와의 오차를 평가하였다. 실제 방사선원의 위치와 계산된 위치와의 오차는 평균 X축 0.11%, Y축 0.37%로 측정되었으며, 매우 정확하게 위치를 측정할 수 있음이 검증되었다.

• Journal of Radiation Protection and Research
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• 제43권4호
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• pp.154-159
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• 2018

Background: To prevent small leakage accidents, a real-time and direct detection system for small leaks with a detection limit below that of existing systems, e.g. $0.5gpm{\cdot}hr^{-1}$, is required. In this study, a small-size beta detector, which can be installed inside the reactor containment (CT) building and detect small leaks directly, was suggested and its feasibility was evaluated using MCNPX simulation. Materials and Methods: A target nuclide was selected through analysis of radiation from radionuclides in the reactor coolant system (RCS) and the spectrum was obtained via a silicon detector simulated in MCNPX. A window was designed to reduce the background signal caused by other nuclides. The sensitivity of the detector was also estimated, and its shielding designed for installation inside the reactor CT. Results and Discussion: The beta and gamma spectrum of the silicon detector showed a negligible gamma signal but it also contained an undesired peak at 0.22 MeV due to other nuclides, not the $^{16}N$ target nuclide. Window to remove the peak was derived as 0.4 mm for beryllium. The sensitivity of silicon beta detector with a beryllium window of 1.7 mm thickness was derived as $5.172{\times}10^{-6}{\mu}Ci{\cdot}cc^{-1}$. In addition, the specification of the shielding was evaluated through simulations, and the results showed that the integrity of the silicon detector can be maintained with lead shielding of 3 cm (<15 kg). This is a very small amount compared to the specifications of the lead shielding (600 kg) required for installation of $^{16}N$ gamma detector in inside reactor CT, it was determined that beta detector would have a distinct advantage in terms of miniaturization. Conclusion: The feasibility of the beta detector was evaluated for installation inside the reactor CT to detect small leaks below $0.5gpm{\cdot}hr^{-1}$. In future, the design will be optimized on specific data.

• Nuclear Engineering and Technology
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• 제41권5호
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• pp.723-728
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• 2009

The response property of the CZT detector ($5{\times}5{\times}5\;mm^3$), widely used in photon spectroscopy, was evaluated by considering the charge collection efficiency, which depends on the interaction position of incident radiation, A quantitative analysis of the energy spectra obtained from the CZT detector was also performed to investigate the tail effect at the low energy side of the full energy peak. The collection efficiency of electrons and holes to the two electrodes (i.e., cathode and anode) was calculated from the Hecht equation, and radiation transport analysis was performed by two Monte Carlo codes, Geant4 and MCNPX. The radiation source was assumed to be 59.5 keV gamma rays emitted from a $^{241}Am$ source into the cathode surface of this detector, and the detector was assumed to be biased to 500 V between the two electrodes. Through the comparison of the results between the Geant4 calculation considering the charge collection efficiency and the ideal case from MCNPX, an pronounced difference of 4 keV was found in the full energy peak position. The tail effect at the low energy side of the full energy peak was confirmed to be caused by the collection efficiency of electrons and holes. In more detail, it was shown that the tail height caused by the charge collection efficiency went up to 1000 times the pulse height in the same energy bin at the calculation without considering the charge collection efficiency. It is, therefore, apparent that research considering the charge collection efficiency is necessary in order to properly analyze the characteristics of CZT detectors.

• Nuclear Engineering and Technology
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• 제49권7호
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• pp.1489-1494
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• 2017

The use of a room-temperature gamma spectrometer is an issue in environmental radiation monitoring. To monitor radionuclides released around a nuclear power plant, suitable instruments giving fast and reliable information are required. High-pressure xenon (HPXe) chambers have range of resolution and efficiency equivalent to those of other medium resolution detectors such as those using NaI(Tl), CdZnTe, and $LaBr_3:Ce$. An HPXe chamber could be a cost-effective alternative, assuming temperature stability and reliability. The CEA LIST actively studied and developed HPXe-based technology applied for environmental monitoring. Xenon purification and conditioning was performed. The design of a 4-L HPXe detector was performed to minimize the detector capacitance and the required power supply. Simulations were done with the MCNPX2.7 particle transport code to estimate the intrinsic efficiency of the HPXe detector. A behavioral study dealing with ballistic deficits and electronic noise will be utilized to provide perspective for further analysis.

• 방재기술
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• 통권29호
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• pp.39-45
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• 2000

All objects emit thermal radiation and this radiation is the basis of the techniques used to detect flames. The usual phenomena occurring in the initial stage of a fire are generally invisible products of a combustion and visible smoke. Liquid or gaseous materials do not undergo a smoldering stage such fires develop very rapidly. Also, the heat generated by the initial flames is usually not sufficient to active a heat detector. In this case the most effective criterion for automatic fire detection is the flame. In fire regulation of korea, the compulsory standard provided that a flame detector shall be installed a place of the attachment hight of detector is higher than 20 m, chemical plants, hangar, refinery, etc.. The result of the research and development are discriminated between a flame and other radiant emitters, developed PZT pyroelectric element is based on the use of photo-voltanic cell, developed IR band-pass filter that only allow a 4.3 radiation wavelength to reach the sensors and developed IR flame detector.