• 한국정보통신학회논문지
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• 제24권11호
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• pp.1519-1527
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• 2020

일반적인 방사선 측정장치는 방사능 오염원에 대한 선량률을 측정하는 공간 선량률 탐지 장치와 방사능 오염정보에 대한 2차원 또는 3차원 영상화 장치의 형태로 개발되었다. 이러한 방사선 계측 기법은 각각의 장단점을 가지고 있으나 방사능 사고 지역에서 인명피해를 최소화하며, 빠른 제염을 위해서는 두 가지 탐지 장치의 장점이 모두 필요하다. 방사능 오염원으로부터 방사능 피해를 최소화하기 위해서는 방출되는 방사선에 대한 선량률 뿐만 아니라 어디에서 방출되고 있는지를 빠르게 확인해야 하기 때문이다. 본 논문에서는 방사능 오염원 탐지를 위한 검출 센서와 회전체, 방향성을 갖는 콜리메이터를 이용하여 방사능 오염원에 대한 선량률 및 방향 정보를 실시간으로 측정 할 수 있는 기법을 고안하였다. 회전형 기반의 방사능 탐지 장치는 탐지 센서를 둘러싼 회전체가 회전하며 개구부와 일치할 때 획득되는 방사능 정보와 회전체의 위치정보를 통해 선량률과 방향을 확인할 수 있도록 구성하였으며, 다수개의 홀을 통해 수직, 수평 방향에 대한 측정 기법을 제안하였다. 탐지 결과 수평 방향에서의 탐지 시 방향 정보에 대한 측정오차는 1% 미만으로 확인하였다.

• 대한의용생체공학회:학술대회논문집
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• 대한의용생체공학회 1997년도 추계학술대회
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• pp.172-175
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• 1997

Outline contour is detected firstly to simulate dose distribution in radiation therapy planning system. In this paper, we developed automatic contour detection system using temporal and spatial relationships of image sequences. The low level image analysis involves the use of directional gradient edge operators and Laplacian operator. The High level portion of algorithm uses a knowledge-based strategy that incorporates fuzzy resoning method.

• 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.

• 한국영양학회:학술대회논문집
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• 한국영양학회 2001년도 춘계연합학술대회 초록
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• pp.200.2-200
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• 2001

• 전기학회논문지
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• 제62권5호
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• pp.639-642
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• 2013

In this paper, proposed NED(nuclear event detectors) for detection of a transient radiation. Nuclear event detector was blocked of power temporary for defence of critical damage at a electric device when a induced transient radiation. Conventional NED consist of BJT, resistors and capacitors. The NED supply voltage of 5V and MCM(Multi Chip Module) structures. The proposed NED were designed for low supply voltage using 0.18um CMOS process. The response time of proposed NED was 34.8ns. In addition, pulse radiation experiments using a electron beam accelerator, the output signal has occurred.

• Nuclear Engineering and Technology
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• 제55권11호
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• pp.4039-4047
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• 2023

This contribution describes the application of HPGe detector for the airborne quantitative analysis. The hardware of the airborne HPGe system was designed from the commercial components with only exception of the newly designed AirHPGeSpec special software to control, measure and process the data. The system was calibrated for the local air kerma rates measured on helicopter board and its conversion to the air kerma rates at 1 m above the ground was proposed. Two examples of the air kerma rates measured over the former uranium mining areas are presented and compared with the results of other airborne system on the board. This airborne HPGe system could be also used for measuring the surface activities in a radiation event. The nuclides of ¹³¹I, ¹³²Te - ¹³²I, ¹³³I, ¹³⁴I, ¹³⁵I, ¹³⁷Cs, ¹³⁴Cs, ⁸⁸Rb and ¹⁰³Ru were selected from possible nuclear power plant emergency scenarios. The Monte Carlo simulation was used to calculate HPGe detector efficiencies for the flight altitudes from 25 to 300 m for the energies from 300 keV to 3 MeV of the nuclides in question. Also, the detection limits according to the Currie method as well as ISO 11929-2010 for selected nuclides are presented.

• 한국산업보건학회지
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• 제27권3호
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• pp.170-179
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• 2017

Objectives: This study aims to investigate the occupational radiation exposures of emergency medical technicians(EMTs) in emergency medical centers in Korea. The results will provide a basis for developing prevention programs to minimize adverse health effects relating to radiation exposure among emergency medical technicians working in this area. Methods: Radiation exposure doses were measured for twenty-two EMTs working in six emergency medical centers. Thermo Luminescent Dosimeters(TLD) were placed on three representative body parts, including chest, neck, and a finger. Measurements were conducted over the entire working hours of the participants for foor weeks. Dosimeters were analyzed according to a standard method by a KFDA-designated lab. Detection rate, annual radiation exposure dose, and relative levels to dose limit were derived based on the measured doses from the dosimeters. SPSS/Win 18.0 software(IBM, US) was used for statistical analysis. Results: Detection rates were 45.5%, 36.4%, and 45.5% for the dosimeters sampled from chest, neck, and a finger, respectively. The average annual doses were $2.39{\pm}3.44mSv/year$(range 0.38-10.0 mSv/year) for the chest, $2.72{\pm}3.05mSv/year$(2.00-11.34) for the neck, and $20.98{\pm}17.57mSv/year$(1.25-53.50) for the hand dose. The average annual eye dose was estimated to $3.61{\pm}2.37mSv/year$(1.50-8.34). The exposure dose levels of EMTs were comparable to those of radiologists, who showed relatively higher radiation dose among health care workers, as reported in another study. Conclusions: EMTs working in emergency medical centers are considered to be at risk of radiation exposure. Although the radiation exposure dose of EMTs does not exceed the dose limit, it is not negligible comparing to other professionals in health care sectors.

• Journal of Radiation Protection and Research
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• 제42권1호
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• pp.48-55
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• 2017

Background: Simultaneous detection of neutrons and gamma rays have become much more practicable, by taking advantage of good gamma-ray discrimination properties using pulse shape discrimination (PSD) technique. Recently, we introduced a commercial CLYC system in Korea, and performed an initial characterization and simulation studies for the CLYC detector system to provide references for the future implementation of the dual-mode scintillator system in various studies and applications. Materials and Methods: We evaluated a CLYC detector with 95% $^6Li$ enrichment using various gamma-ray sources and a $^{252}Cf$ neutron source, with validation of our Monte Carlo simulation results via measurement experiments. Absolute full-energy peak efficiency values were calculated for gamma-ray sources and neutron source using MCNP6 and compared with measurement experiments of the calibration sources. In addition, behavioral characteristics of neutrons were validated by comparing simulations and experiments on neutron moderation with various polyethylene (PE) moderator thicknesses. Results and Discussion: Both results showed good agreements in overall characteristics of the gamma and neutron detection efficiencies, with consistent ~20% discrepancy. Furthermore, moderation of neutrons emitted from $^{252}Cf$ showed similarities between the simulation and the experiment, in terms of their relative ratios depending on the thickness of the PE moderator. Conclusion: A CLYC detector system was characterized for its energy resolution and detection efficiency, and Monte Carlo simulations on the detector system was validated experimentally. Validation of the simulation results in overall trend of the CLYC detector behavior will provide the fundamental basis and validity of follow-up Monte Carlo simulation studies for the development of our dual-particle imager using a rotational modulation collimator.

• 대한전기학회논문지:시스템및제어부문D
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• 제54권9호
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• pp.556-558
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• 2005

The effect of high irradiation on inspection systems in a nuclear power plant can be severe, especially to electronic components such as control hoards. The effect may lead to a critical malfunction or trouble to a underwater robot for inspection and maintenance of nuclear reactor. However, if information on the total accumulated dose on the sensitive parts of the robot is available, a prediction of robot's behavior in radiation environments becomes possible. To know how much radiation the robot has encountered, a dosimeter to measure the total accumulated dose is necessary. This paper describes the development effort of a dual radiation monitoring system using a SiC diode as a dose-rate meter and a p-type power MOSFET as a dose meter. This attempt using two sensors which detect same radiation improves reliability and stability at high intensity radiation detection in nuclear facilities. It uses the concept of diversity and redundancy.

• 대한디지털의료영상학회논문지
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• 제13권1호
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• pp.7-11
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• 2011

As applications of radiation grow wider from use in the early detection of lesions and preventive diagnosis purposes to the treatment of diseases, the possibilities for patients and working professionals to be exposed to radiation are becoming greater than ever. This can not only directly bring about an increase in patient's individual radiation exposure, but also brings about an increase in the annual radiation dose of working professionals. Therefore, research and countermeasures to reduce radiation dosage are required. In this study, space dosimetry has been divided into two separate measuments with an understanding of the increasing number of angiography procedures: front perspective and side perspective. According to the results of the isodose curve, a way to minimize radiation exposure in working professionals has been suggested. This was made possible by workers through awareness of suitable working positions.