• 농촌계획
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• 제28권2호
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• pp.87-96
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• 2022

As part of strengthening energy security and responding to climate change, the government has promoted various renewable energy measures to increase the development of renewable energy facilities. As a result, small-scale solar installations in rural areas have increased rapidly. The number of complaints from local residents is increasing. Therefore, in this study, deep learning technology is applied to high-resolution aerial images on the internet to detect solar power plants installed in rural areas to determine whether or not solar power plants are installed. Specifically, I examined the solar facility detector generated by training the YOLO(You Only Look Once) v2 object detector and looked at its usability. As a result, about 800 pieces of training data showed a high object detection rate of 93%. By constructing such an object detection model, it is expected that it can be utilized for land use monitoring in rural areas, and it can be utilized as a spatial data construction plan for rural areas using technology for detecting small-scale agricultural facilities.

• Nuclear Engineering and Technology
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• 제47권4호
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• pp.479-487
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• 2015

The thallium-doped sodium iodide [NaI(Tl)] scintillation detector is preferred as a gamma spectrometer in many fields because of its general advantages. A silicon photomultiplier (SiPM) has recently been developed and its application area has been expanded as an alternative to photomultiplier tubes (PMTs). It has merits such as a low operating voltage, compact size, cheap production cost, and magnetic resonance compatibility. In this study, an array of SiPMs is used to develop an NaI(Tl) gamma spectrometer. To maintain detection efficiency, a commercial NaI(Tl) $2^{\prime}{\times}2^{\prime}$ scintillator is used, and a light guide is used for the transport and collection of generated photons from the scintillator to the SiPMs without loss. The test light guides were fabricated with polymethyl methacrylate and reflective materials. The gamma spectrometer systems were set up and included light guides. Through a series of measurements, the characteristics of the light guides and the proposed gamma spectrometer were evaluated. Simulation of the light collection was accomplished using the DETECT 97 code (A. Levin, E. Hoskinson, and C. Moison, University of Michigan, USA) to analyze the measurement results. The system, which included SiPMs and the light guide, achieved 14.11% full width at half maximum energy resolution at 662 keV.

• 한국방사선학회논문지
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• 제11권3호
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• pp.123-129
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• 2017

Compton suppression system은 스펙트럼에서 Compton continuum으로 존재하는 영역을 억제하는 장치 이다. 본 연구에서는 HPGe-NaI(TI)의 기하학적인 구조 파악 및 이동에 따른 이 때 그 효과를 최적화 할 수 있는 배치구조를 찾기 위하여, Monte Carlo simulation을 통해 Compton suppression의 행태적 특성을 파악하고, 몇 가지 배치구조에 대한 비교를 해보았다. 또한 거리에 따른 효율을 이용하여 환경 측정에 사용되는 실린더 비커에 적용해 보았다. ARF 값은 81.1 keV의 경우 약 1.65, 1332.4 에너지의 경우 약 1.9 정도로 나타내는 것을 확인할 수 있다. NaI(Tl) 검출기들의 위치 이동에 따라 특정한 영역에서 suppression이 일어나는 확인할 수 있다. Compton suppression system 구성의 목적에 비추어 볼 때, 결과 에너지 스펙트럼의 Compton continuum 영역 전반에 걸쳐 suppression이 이루어지는 것이 더욱 적절한 배치구조가 됨을 알 수 있다. 따라서 최적화된 구조를 통해 다양한 환경시료 측정에 적용할 수 있음을 확인 하였다.

• Journal of Radiation Protection and Research
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• 제39권1호
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• pp.54-60
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• 2014

IAEA는 핵물질 계량 관리 검사를 위해 다양한 방사선 검출기를 사용하고 있다. 주로 HPGe, NaI(Tl), CZT 등이 사용되며, 정확한 측정이 요구되는 검사에는 고분해능 HPGe 검출기 활용도가 높다. HPGe 검출기는 추가적인 냉각장치로 인하여 부피가 크고 무거우며, 사용하기 전에 충분히 냉각시켜야 하기 때문에 측정의 준비 시간이 많이 걸린다는 단점이 있다. 이러한 문제점을 해결하기 위해 가볍고 짧은 사용 전 냉각이 요구되는 휴대형 HPGe가 개발되었다. 본 논문은 개발된 휴대형 HPGe 검출기 시제품을 실제 IAEA 사찰 현장에 적용하여 얻은 성능평가 결과를 기술한다. 휴대형 HPGe로 얻은 방사선 스펙트럼은 핵물질 종류와 농축도에 따라 다른 특징을 보였고, 또한 $^{235}U$과 $^{238}U$의 붕괴 계열에서 방출되는 감마선 및 우라늄의 특성 x-선 차이도 확인할 수 있었다. 그리고 휴대형 HPGe 검출기 시제품으로 측정한 농축도는 핵물질 종류에 따라 실제값과 9 ~ 27%의 상대적 오차를 보였다. 휴대형이라는 소형 검출기의 한계 때문에 일부 핵물질은 IAEA에서 요구하는 정확도를 만족시키지 못하는 경우도 있었지만 향후 추가적인 연구의 수행으로 이러한 문제점은 해결 가능할 것으로 판단된다. 본 논문은 새로운 휴대형 HPGe 검출기를 안전조치에 적용한 사례와 측정한 스펙트럼을 농축도 분석 코드로 분석한 결과를 다룬다. 따라서 국내 원자력시설의 우라늄 농축도 검증을 위한 IAEA 안전조치 사찰 결과를 분석한 논문이 별로 발표되지 않은 상황에서, 본 논문은 안전조치 검사 결과 분석에도 유익할 것으로 판단된다. 개발된 방사선 검출기의 개선 사항도 함께 논의하였으므로 향후 관련 분야 방사선 검출기 개발에도 기여할 것으로 예상된다.

• 천문학논총
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• 제30권2호
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• pp.251-254
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• 2015

Low resolution spectra of Nova Delphini 2013 (V339 Del) in the optical range have been obtained at Bosscha Observatory, Indonesia during its maximum light (V = 4.3). Spectra were observed from August 16 to 27, 2013. The GAO-ITB RTS 20.3 cm telescope, and SBIG DSS-7 spectrograph and SBIG ST-7 XE as the detector have been employed throughout the observations. The spectra show P-Cygni profiles in Balmer, NaI'D' and Fe II lines, from which we determined shell expansion velocities of $1421.66{\pm}39.18km/s$, $1227.54{\pm}21.57km/s$ and 1402.86 km/s, respectively. Our spectroscopic observations followed the spectral evolution of V339 Del from the pre-maximum phase to early Orion phase. The characteristics of the nova Delphini 2013 resembles those of Fe II-type novae.

• 방사선산업학회지
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• 제6권1호
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• pp.41-47
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• 2012

A field tracer experiment using a radioisotope was conducted to analyze the transport and dispersion characteristics of pollutants in the coastal area near a Wolsung. A rod float including GPS was released to track the paths of radioisotope. NaI detector was installed to measure the released radioisotope from the boat, and measurements were performed with the real time. The measured tracer data by a field experiment can be used as the basic data for understanding the transport characteristics of pollutants and verifying numerical models near the offshore.

• Nuclear Engineering and Technology
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• 제53권12호
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• pp.4142-4149
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• 2021

In the radiation protection application, the metal-polymer composites have been developed for their radiation shielding properties. In this research, the elastomer composites doped by 10 ㎛ and 100nm size of lead, bismuth and tungsten particles as filler with 30 and 60 wt percentages were prepared. To survey the shielding properties of the polymer composites using gamma-ray emitted from 152Eu and 137Cs sources, the gamma flux was measured by using NaI(Tl) detector, then the linear attenuation coefficient was calculated. Also, the Monte Carlo simulation (MCs) method was used. The results showed a direct relationship between the linear attenuation coefficients of the absorbent and filler ratio. Also, the decrease in the particle size of the shielding material in each weight percentage improved the radiation shielding features. When the dimension of the particles was in the order of nano-size, more attenuation was achieved. At low energies used for medical diagnostic X-ray applications due to the predominance of the photoelectric effect, bismuth and lead were suitable selection as filler.

• 방사성폐기물학회지
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• 제20권2호
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• pp.243-253
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• 2022

Spent filters with a high radiation dose rate of 2 mSv·hr^-1 or more are not easily managed. So far, the Korean policy for spent filter disposal is to store them temporarily at nuclear power plants until the waste filters can be easily managed. Nuclear power plant decommissioning in Korea is starting with Kori unit 1. Volume reduction of waste generated during decommissioning can reduce the cost and optimize the space usage at disposal site. Therefore, efficient volume reduction is a very important factor during the decommissioning process. A conceptual method, based on the experiences of developing 200 and 800 ton compactors at Orion EnC, has been developed considering worker exposure with the followings a crusher (upgrade of compaction efficiency), an automatic dose measuring system with a NaI(Tl) detector, a shield box, an inner drum to prepare for easy handling of drums and packaging, a 30 ton compactor, and an automatic robot system. This system achieves a volume reduction ratio of up to 85.7%; hence, the system can reduce the disposal cost and waste volume. It can be applied to other types of wastes that are not easily managed due to high dose rates and remote control operation necessity.

• 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.

• Nuclear Engineering and Technology
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• 제56권2호
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• pp.666-672
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• 2024

In the present work, a new brick series based on the Vietnamese white clay minerals from the Bat Trang was fabricated to be applied in the radiation protection applications during the decommissioning of the nuclear power reactors. The bricks were constructed under various pressure rates varied from 7.61 MPa to 114.22 MPa. The influence of pressure rate on the physical and γ-ray shielding properties were investigated in the study. The experimental measurement for the material's density using the MH-300A density meter showed an enhancement in the prepared bricks' density by 22.5 % with increasing the applied pressure rate while the bricks' porosity reduced by 31.2 % when the pressure rate increased from 7.61 MPa to 114.22 MPa. The increase in the fabricated bricks density and the reduction in their porosities enhances the bricks' linear attenuation coefficients as measured by the NaI (Tl) detector along the energy range extended from 0.662 MeV to 1.332 MeV. The linear attenuation coefficient increased by 13.8 %, 17.6 %, 17.0 %, and 17.1 % at gamma ray energies of 0.662 MeV, 1.173 MeV, 1.252 MeV, and 1.332 MeV, respectively. The enhancement in the linear attenuation coefficient increases the bricks' radiation protection efficiency by 10.22 %, 14.48 %, 14.09 %, and 14.26 % at gamma ray energies of 0.662 MeV, 1.173 MeV, 1.252 MeV, and 1.332 MeV, respectively.