• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.249-253
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• 2001

Neutron dose assessment in criticality accidents using Whole Body Counter (WBC) was proved to be an effective method as rapid neutron dose estimation at the JCO criticality accident in Tokai-mura. The 1.36MeV gamma-ray of $^{24}Na$ in a body can be detected easily by a germanium detector. The Minimum Detectable Activity (MDA) of $^{24}Na$ is approximately 50Bq for 10miniute measurement by the germanium-type whole body counter at JNC Tokai Works. Neutron energy spectra at the typical shielding conditions in criticality accidents were calculated and the conversion factor, whole body activity-to-organ mass weighted neutron absorbed dose, corresponding to each condition were determined. The conversion factor for uncollied fission spectrum is 7.7 $[(Bq^{24}Na/g^{23}Na)/mGy]$.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2003년도 학술회의 논문집 정보 및 제어부문 B
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• pp.793-796
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• 2003

The electronics of a mobile robot ill nuclear facilities is required to satisfied the reliability to sustain survival in its radiation environment. To know how much radiation the robot has been encountered to replace sensitive electronic parts, a dosimeter to measure total accumulated dose is necessary. Among many radiation dosimeters or detectors, semiconductor radiation sensors have advantages in terms of power requirements and their sires over conventional detectors. This paper describes the use of the radiation-induced threshold voltage change of a commercial power pMOSFET as an accumulated radiation dose monitoring mean and that of the photo-current of a commercial PIN Diode as a dose-rate measurement mean. Commercial p-type power MOSFETs and PIN Diodes were tested in a Co-60 gamma irradiation facility to see their capabilities as radiation sensors. We found an inexpensive commercial power pMOSFET that shows good linearity in their threshold voltage shift with radiation dose and a PIN diode that shows good linearity in its photo-current change with dose-rate. According to these findings, a radiation hardened hybrid electronic radiation dosimeter for nuclear robots has been developed for the first time. This small hybrid dosimeter has also an advantage in the point of view of reliability improvement by using a diversity concept.

• Journal of Microbiology and Biotechnology
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• 제11권3호
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• pp.524-528
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• 2001

The measurement of radiation response using simple and informative techniques would be of great value in studying the genetic risk following occupational, therapeutic, or accidental exposure to radiation. When patients receive radiation therapy, many suffer from side effects. Since each patient receives a different dose due to different physical conditions, it is important to measure the exact dose of radiation received by each patient to lessen the side effects. Even though several biological dosimetric systems have already been developed, there is no ideal system that can satisfy all the criteria for an idean dosimetric system, especially for low-dose radiation as used in radiation therapy. In this study, an SOS Chromotest of E. coli PQ37 was evaluated as a novel dosimeter for low-dose gamma-rays. E. coli PQ37 was originally developed to screen chemical mutagens using the SOS Chromotest-a colorimtric assay, based on the induction of ${\beta}$-galactosidase ue to DNA damage. The survival fraction of E. coli PQ37 decreased dose-dependently with an increasing dose of cobalt-60 gamma-rays. Also, a good linear correlation was found between the biological damage revealed by the ${\beta}$-galactosidase expression and the doses of gamma-rays. The expression of ${\beta}$-galactosidase activity that responded to low-dose radiation under 1 Gy was $Y=0.404+(0.089{\pm}0.3)D+(-0.018{\pm}0.16)D^2$ (Y, absorbance at 420 nm; D, Dose of irradiation) as calculated using Graph Pad In Plot and Excel. When a rabbit was fed with capsules containing an agar block embdded with E. coli PQ37 showed a linear response to the radiation doses. Accordingly, the results confirm that E. coli PQ37 can be used as a sensitive biological dosimeter fro cobalt-60 gamma-rays. To the best of our knowledge, this is the first time that a bacterium has been used as a biological dosimeter, especially for low-dose radiation.

• Radiation Oncology Journal
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• 제2권1호
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• pp.129-137
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• 1984

In brachytherapy, it is important to determine the positions of the radiation sources which are inserted into a patient and to estimate the dose resulting from the treatment. Calculation of the dose distribution throughout an implant is so laborious that it is rarely done by manual methods except for model cases. It is possible to calculate isodose distributions and tumor doses for individual patients by the use of a microcomputer. In this program, the dose rate and dose distributions are calculated by numerical integration of point source and the localization of radiation sources are obtained from two radiographs at right angles taken by a simulator developed for the treatment planning. By using microcomputer for brachytherapy, we obtained the result as following 1. Dose calculation and irradiation time for tumor could be calculated under one or five seconds after input data. 2. It was same value under$\pm2\%$ error between dose calculation by computer program and measurement dose. 3. It took about five minutes to reconstruct completely dose distribution for intracavitary irradiation. 4. Calculating by computer made remarkly reduction of dose errors compared with Quimby's calculation in interstitial radiation implantation. 5. It could calculate the biological isoffect dose for high and low dose rate activities.

• 대한의용생체공학회:학술대회논문집
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• 대한의용생체공학회 1996년도 추계학술대회
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• pp.15-17
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• 1996

In this paper, the therapy radiation dose measurement system has been implemented by using a microcomputer after radiation was irradiated on diodes from the MM22 microtron accelerator. We have displayed 7-channel diode output values on the LCD after processing those in the 80196 MCU(Micro Computer Unit). Signal processing has been performed in the pulse mode because we can process the signal fast and use it to perform portal image by increasing a number of diode channels in the future. In order to verify the microcomputer based radiation measurement system of diodes, diode output values were compared with that of semiconductor.

• Radiation Oncology Journal
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• 제13권3호
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• pp.285-289
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• 1995

목적 : 6 MeV의 전자선에 대하여 Monte-Carlo기법을 이용한 모의계산(simulation)과 측정을 함으로써 측정값과 계산값을 서로 비교하고, 이러한 모의계산이 측정을 대신할 수 있을 만큼의 정확도가 있는지를 확인하고자 하였다. 방법 : 선형가속기에서 출력되는 전자선의 심부량 백분율(percent depth dose)을 물팬톰에서 반도체 검출기를 이용하여 조사야 $50{\times}50,\;100{\times}100,\;150{\times}150,\;200{\times}200\;mm^2$에 대하여 측정하였다. 전자선에 대한 선량을 결정하기 위한 모의계산은 EGS4 프로그램을 사용하였다. 결과 : 측정값과 계산값은 유사한 형태로 나타났는데 $100{\times}100\;mm^2$ 조사야 에서 선축상최대선량은 측정값과 계산값이 각각 14mm 와 15mm, 표면선량율은 각각 $76.94\%$ 와 $65.52\%$였다. 모의계산에서 표면선량율의 조사야에 따른 변화는 $64.43\%-66.99\%$이고 선축상최대선량은 15mm-18mm 였다. 결론 : 모의계산을 한 결과, 계산값이 측정값과 비교적 잘 일치한다는 것을 알았다. 표면선량율의 차이만을 제거하고 결과를 살펴보면 선축상 최대치등 방사선 치료에 주로 이용되는 부츤의 선량율에서는 모의계산이 측정을 대신할 수 있을 만큼의 정확도가 있다는 것을 확인하였다.

• 대한방사선치료학회지
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• 제10권1호
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• pp.88-93
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• 1998

Multileaf collimator is essential equipment in conformal radiation therapy, however the use is limitted by increase of penumbra width and undulating dose distribution at the field edge. The purpose of this study is to improve the penumbra and dose distribution in the multileaf collimator field edge. Measurement were performed with X-omat V film in solid water phantom using 6MV photon beam from Siemens linear accelerator. All the measurement were made along the central axis of $5{\times}5cm,\;10{\times}10cm$ circular field for constant SSD of 100 cm. To improve the penumbra and dose distribution collimator was rotated by 15 degrees from 0 to 90 degrees (collimator rotation method) and center was shifted to the longitudinal direction by fourth of lead width (center shift method). We compare the penumbra and dose distribution at the field edge to alloy block. Dose distribution and penumbra width at the feild edge of MLC showed undulated dose pattern and increased penumbra compared with alloy block. However, in the collimator rotation method and center shift method we abtained simular results with alloy block. Through the study we expected that clinical use of MLC will be increase.

• 대한방사선기술학회지:방사선기술과학
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• 제45권1호
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• pp.49-55
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• 2022

This study is to develop a mobile type environmental radiation measurement system for emergency response or environmental radiation monitoring of local governments near nuclear facilities. A mobile radiation measurement system can monitor radiation by field beyond the spatial constraints of a fixed environmental radiation monitor. If installed in local government infrastructure such as public transportation, environmental radiation can be monitored without additional manpower and measurement work. In addition, it is designed to enable monitoring and measurement of radiation from low to high doses as well as the environment in preparation for radioactive disasters such as nuclear power plant accidents. It is expected that this system will be utilized not only in normal times but also in the event of a radiation accident to improve the disaster prevention capabilities of local governments.

• 대한방사선기술학회지:방사선기술과학
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• 제41권4호
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• pp.289-295
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• 2018

When using a mobile X-ray unit, primary radiation creates medical images and secondary radiation scatters in many directions, which reduces image quality and causes exposure to patients, care givers and medical personnel. The purpose of this study was to develop a radiation shielding system for effectively shielding secondary radiation and evaluate its effectiveness. Using a mobile X-ray unit, spatial dose according to presence of human equivalent phantom and spatial dose using the developed shielding device were measured, and the phantom at 80 cm equidistance from center of X-ray was compared with spatial dose according to use of a shield. Measurements were taken at intervals of 10 cm every $30^{\circ}$ from the head direction($-90^{\circ}$) to the body direction($+90^{\circ}$). In the spatial dose measurement with and without the phantom, when the human equivalent Phantom was used, the spatial dose was increased by 40% in all directions from 40 cm to 100 cm from the central X-ray, and about 88% of the space dose was reduced when using the developed shields with the phantom. The equidistance dose at 80 cm from the central X-ray was increased by 39% from $5.1{\pm}0.26{\mu}Gy$ to $7.1{\pm}0.15{\mu}Gy$ when the human equivalent phantom was used, and when phantom was used and shielding was used, the spatial dose was reduced by about 90% from $7.1{\pm}0.15{\mu}Gy$ to $0.7{\pm}0.07{\mu}Gy$. The spatial dose of natural radiation was measured to be about $0.2{\pm}0.04{\mu}Gy$ when using the developed shielding with Phantom at a distance of 1 m or more. It is expected that by using the developed shielding system, it will be possible to effectively reduce secondary radiation dose received in all directions and to ensure safe imaging.

• 한국방사선학회논문지
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• 제15권6호
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• pp.795-801
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• 2021

원전 해체 작업장의 요구에 따라 드론 기반 무인 원격 방사선 검출 모듈을 개발하였다. 사람이 접근해서 방사선을 측정할 수 없는 원자력 발전소 격납용기 내부 상공 및 외부로 누설되는 방사선 측정을 위한 목적으로 저준위에 민감한 GM-tube를 사용하여 제작하였다. 드론 기반 방사선 검출 모듈의 무게는 200g 미만으로 원자력 발전소 격납용기 내부의 상공과 외부 공중에서도 운용이 가능하다. 설계된 장비의 성능 확인을 위해 국제 기준 (IEC60864)을 참고하여 성능평가 실험을 시행하였다. 현장의 요구에 맞게 설계된 방사선 검출 모듈의 안정성은 측정 정확도를 평가하기 위한 변동률 실험에서 반복 측정에 의한 통계적 변동률은 ±4.6%. 선량률 의존성을 평가하기 위한 선형성 실험에서 정확도 ± 7.3%, 전체 선형도는 ± 3.5%이며 성능평가를 위한 국제기준을 만족하였다. 본 연구에서 개발한 무인 원격 방사선 검출 모듈은 원전 해체 작업장 맞춤형 장비로, 방사선 분진이 많은 현장에서 정확한 공간선량률의 측정과 방사선 작업장 안전관리에 도움을 줄 수 있을 것으로 확신한다.