• 대한원격탐사학회지
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• 제37권5_1호
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• pp.1083-1094
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• 2021

접근불능지역에 대한 핵활동 모니터링을 위해서는 고해상도 위성영상을 이용하여 핵활동 관련 객체의 변화양상을 분석하는 방법론의 수립이 필요하다. 그러나, 위성영상을 이용한 전통적인 객체탐지 및 변화탐지 기법들은 영상 취득 시 계절, 날씨 등의 영향에 의하여 탐지 결과물들을 다양한 활용분야에 적용하기에 어려움이 있다. 따라서, 본 연구에서는 딥러닝 모델을 이용하여 위성영상에서 관심객체를 탐지하고, 이를 활용하여 다시기 위성영상 내의 객체 변화를 분석하고자 하였다. 이를 위하여, 객체탐지를 위한 공개데이터셋을 이용하여 딥러닝 모델의 선행학습을 수행하고, 관심지역에 대한 학습자료를 직접 제작하여 전이학습에 적용하였다. 다시기·다종 위성영상 내의 객체를 개별적으로 탐지한 후, 이를 활용하여 영상 내 객체의 변화양상을 탐지하였다. 이를 통해 접근불능지역에 대한 핵 활동 관련 모니터링을 위하여 다양한 위성영상에 대한 객체탐지 결과를 직접적으로 변화탐지에 활용할 수 있는 가능성을 확인하였다.

• Nuclear Engineering and Technology
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• 제51권4호
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• pp.1169-1175
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• 2019

The minimum detectable activity (MDA) value was derived according to the flow rate of the sample and degree of amplification of the device by sending the sample directly from the collection site to the detection part through a pump. This method can lead to reduction in time and cost compared to the existing measurement method that uses a pre-treatment process. In this study, experiments were conducted on $^3H$ and $^{90}Sr$, which are the major pure beta-emitting radionuclides, by setting the sample flow rate and the amplification gain as factors. The MDA values were derived according to the flow rates, considering that the flow rate can affect the MDA values. There were no change in the MDA under different flow rates of 0, 600, 800, and 1000 mL/min. Therefore, it was confirmed that the flow rate may not be considered when collecting samples for monitoring in actual field. As the degree of amplification of the amplifier increased, the time required to reach the target MDA decreased. When the amplification was quadrupled, the detection efficiency increased by approximately 23.4 times, and the time to reach the MDA decreased to approximately 1/550 times. This method offers the advantage of real-time on-site monitoring.

• Journal of Korean Society for Atmospheric Environment
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• 제10권E호
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• pp.299-302
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• 1994

At a nuclear power plant, environmental radioactivity monitoring is routine work for the radiation safety management For the environmental monitoring of tritium($^3$H) activity in water sampled liquid scintillation counting( LSC) method is applied to measure low- energy beta activity from tritium in the samples. The $^3$H activity is measured using the BECKMAN 5801 system at the KRISS( Korea Research Institute of Standards and Science) for evaluating the lower limits of detection( LLD) of $^3$H measurement and the measuring capability of low-level $^3$H activity at four nuclear Power Plant sites. The LSC systems used for low-level $^3$H activity measurements at the nuclear Power Plants are confirmed to satisfy throughout an intercomparison study under the experimental arrangements by the KRISS.

• 대한원격탐사학회지
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• 제38권6_1호
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• pp.991-1005
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• 2022

위성 영상은 핵 활동 탐지와 검증을 위한 효율적인 보조자료로 핵시설과 같이 접근이 어렵고 정보가 제한된 지역에 매우 유용하다. 특히 장비의 이동 또는 시설물의 변화와 같이 핵실험을 준비하는 과정은 시계열 분석을 통해 충분히 식별 가능하다. 본 연구에서는 핵 활동과 관련된 주요 객체의 변화를 탐지하기 위하여, 다시기 영상의 의미론적 분할 결과의 차이를 이용하였다. AIHub에서 제공하는 KOMPSAT 3/3A 영상으로 구성된 객체 판독 데이터셋에서 건물, 도로, 소형 객체의 정보를 추출하여 학습하였으며, U-Net, PSPNet, Attention U-Net에 대하여 주요 파라미터를 변경하며 대상 객체 추출에 적합한 의미론적 분할 모델을 분석하였다. 의미론적 분할 결과의 차영상으로 생성된 결과에 객체 정보를 포함하여 최종 변화 탐지를 수행하였으며, 제안 기법을 임의의 변화를 포함한 시뮬레이션 영상에 적용한 결과, 변화 객체를 효과적으로 추출할 수 있었다. 본 연구에서 제시된 변화 탐지 기법을 적용하기 위해서는, 의미론적 분할의 정확도가 우선적으로 확보되어야 하는 제약이 있으나, 추후 실험 대상 지역에 대한 학습데이터셋이 증가할 수록 적용 가능한 분석 범위가 증가할 것으로 기대된다.

• Nuclear Engineering and Technology
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• 제56권8호
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• pp.3188-3198
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• 2024

Efficient and secure decommissioning of nuclear facilities demands advanced technologies. In this context, gamma-ray detection and imaging are crucial in identifying radioactive hotspots and monitoring radiation levels. Our study is dedicated to developing a gamma-ray detection system tailored for integration into robotic platforms for nuclear decommissioning, offering a safe and automated solution for this intricate task and ensuring the safety of human operators by mitigating radiation exposure and streamlining hotspot localization. Our approach integrates a Compton camera based 3D reconstruction algorithm with a single Timepix3 detector. This eliminates the need for a second detector and significantly reduces system weight and cost. Additionally, combining a 3D camera with the setup enhances hotspot visualization and interpretation, rendering it an ideal solution for practical nuclear decommissioning applications. In a proof-of-concept measurement utilizing a 137Cs source, our system accurately localized and visualized the source in 3D with an angular error of 1° and estimated the activity with a 3% relative error. This promising result underscores the system's potential for deployment in real-world decommissioning settings. Future endeavors will expand the technology's applications in authentic decommissioning scenarios and optimize its integration with robotic platforms. The outcomes of our study contribute to heightened safety and accuracy for nuclear decommissioning works through the advancement of cost-effective and efficient gamma-ray detection systems.

• 분석과학
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• 제35권2호
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• pp.69-81
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• 2022

The method of measuring and classifying the energy category of neutrons directly using raw data acquired through a CZT detector is not satisfactory, in terms of accuracy and efficiency, because of its poor energy resolution and low measurement efficiency. Moreover, this method of measuring and analyzing the characteristics of low-energy or low-activity gamma-ray sources might be not accurate and efficient in the case of neutrons because of various factors, such as the noise of the CZT detector itself and the influence of environmental radiation. We have therefore developed an efficient method of analyzing radiation characteristics using a neutron and gamma-ray analysis algorithm for the rapid and clear identification of the type, energy, and radioactivity of gamma-ray sources as well as the detection and classification of the energy category (fast or thermal neutrons) of neutron sources, employing raw data acquired through a CZT detector. The neutron analysis algorithm is based on the fact that in the energy-spectrum channel of 558.6 keV emitted in the nuclear reaction ¹¹³Cd + ¹n → ¹¹⁴Cd + in the CZT detector, there is a notable difference in detection information between a CZT detector without a PE modulator and a CZT detector with a PE modulator, but there is no significant difference between the two detectors in other energy-spectrum channels. In addition, the gamma-ray analysis algorithm uses the difference in the detection information of the CZT detector between the unique characteristic energy-spectrum channel of a gamma-ray source and other channels. This efficient method of analyzing radiation characteristics is expected to be useful for the rapid radiation detection and accurate information collection on radiation sources, which are required to minimize radiation damage and manage accidents in national disaster situations, such as large-scale radioactivity leak accidents at nuclear power plants or nuclear material handling facilities.

• Nuclear Medicine and Molecular Imaging
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• 제41권4호
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• pp.337-338
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• 2007

A 20-year-old man underwent a Tc-99m HMPAO labeled leukocyte scan for the evaluation of an infection at the stump of an AK amputation, which was conducted due to an open communicated fracture of the left lower leg. Blood-flow and blood-pool images demonstrated a pseudoaneurysm with a focus of intense activity medial to the stump, and centered within a large photopenic defect by surrounding hematoma. Delayed image obtained at 3 hours post-injection showed persistent intense and slight increased activity, Contrast angiography confirmed the presence of a pseudoaneurysm arising from a branch of the left superficial femoral artery.

• Journal of Radiation Protection and Research
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• 제26권4호
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• pp.393-398
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• 2001

매년 병원에서 사용 후 폐기되는 비가연성 폐기물은 ${\gamma}$-선과 ${\beta}$-선을 방출하지만 방사능은 주변방사능 수준으로 매우 낮다. 이를 측정하기 위한 기존의 방법은 비효율적이고 복잡하므로, 좀더 간단한 방법이 긴요하다. 본 논문에서는 측정 방사선의 특성상 핵종에 따라 다른 측정방법을 사용하였는데, ${\gamma}$-선 방출 핵종은 표준시료로부터 효율곡선식을 도출하여 미지의 방사능을 측정하였다 ${\beta}$-선 방출 핵종은 Monte Carlo 시뮬레이션을 통해 계측 효율을 예측하고 표면장벽형계측기로 측정하여 미지의 방사능 양을 결정하는 새로운 방법을 제시하였다. 연구결과에 의하면 이론적 계산치와 표면장벽형 계측기를 이용하면 전처리를 필요로하는 액체섬광계수기를 이용하지 않고 또한 계측효율을 결정하기 위한 비경제적인 표준시료 측정시험과정 없이도 저에너지 방사선을 약 17% 오차 범위내에서 결정할 수 있다고 판단된다.

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1250-1253
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• 2024

Activity measurement of the primary circuit water of fission reactors is one method that can provide early detection of a damaged fuel assembly in the reactor core. This is an important aspect in the safe operation of the reactor and for radiation protection of staff. Radionuclides in the primary circuit water are produced by the activation of stable nuclides and the fission of fissile nuclides, mainly the isotope ²³⁵U. In the LVR-15 research reactor, measurement of the activity of the primary circuit water has been regularly undertaken since 1996. A water sample is taken from the primary circuit every week and the activities are measured four days later using gamma spectrometry. The results of these long-term measurements from 1996 to 2022 are presented. The activity time dependences of the individual radionuclides are discussed in relation to fuel assembly damage and for events connected to contamination of the water by objects inserted into the primary circuit during experiments carried out near the reactor core.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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• pp.12-27
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• 2004

Pretreatment process consisted of submerged hollow-fiber microfiltration(HMF) membrane and spiral-wound nanofiltration(SNF) membrane has been developed by NETEC, KHNP for the purpose of improving the impurities of liquid radioactive waste before entering Selective Ion Exchange System(SIES). The lab-scale combined system was installed at Kori NPP #2 nuclear power plant and demonstration tests using actual liquid radioactive waste were carried out to verify the performance of the combined system. The submerged HMF membrane was adopted for removal of suspended solid in liquid radioactive waste and the SNF membrane was used for removal of particulate radioisotope such as, Ag-l10m and oily waste because ion exchange resin can not remove particulate radioisotopes. The liquid waste in Waste Holdup Tank (WHT) was processed with HMF and SNF membrane, and SIES. The initial SS concentration and total activity of actual waste were 38,000ppb and $1.534{\times}10_{-3}{\mu}Ci/cc$, respectively. The SS concentration and total activity of permeate were 30ppb and lower than LLD(Lower Limit of Detection), respectively.