• 전자공학회논문지
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• 제51권4호
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• pp.193-200
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• 2014

본 논문에서는 방사성 의약품의 자동합성장치에 사용되는 단채널 감마선 분광기를 보드 형태로 설계, 제작하고 그 특성을 측정 분석하였다. 감마선 검출을 위해 CZT (CdZnTe) spear 검출기를 이용하였고 아날로그 방식을 적용한 신호처리 보드의 형태로 감마선 분광기를 제작하였다. 측정을 위하여 방사성 물질인 Co-60을 시료로 사용하였으며, 최대 1173keV까지의 감마선 에너지 스펙트럼을 얻을 수 있었다. 아날로그 보드는 CZT spear 검출기에서 감마선을 검출하여 출력하는 신호를 적절히 변화시켜주기 위한 SF (shaping filter) 및 PHA (peak and hold amplifier)와 수치화된 감마선 신호 데이터를 계산하기 위한 ADC(analog to digital converter)와 FPGA (field programmable gate array)로 구성되었다.

• Journal of Radiation Protection and Research
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• 제9권1호
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• pp.11-18
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• 1984

Well type 전리함과 미세전류 측정희로를 사용하여 표준 감마선 전리함 장치를 개발하였다. 미세전류는 automatic Townsend balance with stepwise compensation방법을 사용하여 측정하였다. $^{226}Ra$을 기준 선원으로 택하여 감마 방출핵종인 $^{241}Am,\;^{133}Ba,\;^{60}Co,\;^{134}Cs,\;^{137}Cs^{22}Na$에 대한 비교 교정인자를 산출하였으며, 감마에너지의 함수로서 검출 효율 곡선을 구하였다.

• 센서학회지
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• 제9권4호
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• pp.274-280
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• 2000

본 논문은 감마선 방사선 선량을 측정하기 위하여 상용 반도체를 응용하기 위한 실험적 연구에 대하여 다루었다. 실리콘 포토 다이오드는 값이 싸고 작으며 높은 효율과 견고하여 광검출기로 잘 이용되기 때문에 감마선과 같은 방사선 측정에 효과적으로 이용될 수 있다. 대부분의 PN 포토 다이오드는 이 증가함에 따라 역 방향 전류의 증가하는 특성을 가지고 있다. 그러므로 이 소자들의 공핍층이 역 방향 전류에 영향을 주므로 이 공핍층의 면적이 큰 PIN 포토 다이오드를 선택하였다. 이 연구에서는 방사선량을 검출하고 감마선 선량계를 개발하는데 적용하기 위하여, PIN 다이오드에 대해 몇 가지 실험이 수행되었다. NEC사의 PH 302와 SIEMENS사의 BPW 34와 같은 2가지 종류의 포토 다이오드를 반도체 분석장치를 사용하여 $\gamma$선 방사선원인 Co-60의 저준위 시설에서 시험하였다. 그 결과, 방사선 선량률과 다이오드의 전류 사이에 양호한 선형적 함수 관계가 나타나는 것을 확인할 수 있었다. 따라서, 이들 실리콘 PIN 포토 다이오드들은 $\gamma$선 선량계를 설계하는데 적합하게 이용될 수 있을 것이다.

• 한국산업융합학회 논문집
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• 제27권2_2호
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• pp.437-443
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• 2024

The purpose of radiological Dispersal Device(RDD) is to kill people by explosives and to cause radiation exposure by dispersing radioactive materials. And It is a form of explosive that combines radioactive materials such as Co-60 and Ir-192 with improvised explosives. In this study, we tested and evaluated whether it was possible to read the internal structure of an explosive using X-rays in a radioactive explosive situation. The improvised explosive device was manufactured using 2 lb of model TNT explosives, one practice detonator, one 9V battery, and a timer switch in a leather briefcase measuring 41×35×10 cm³. The radioactive material used was the Co-60 source used in the low-level gamma ray irradiation device operated at the Advanced Radiation Research Institute of the Korea Atomic Energy Research Institute. The radiation dose used was gamma ray energy of 1.17 MeV and 1.33 MeV from a Co-60 source of 2208 Ci. The dose rates are divided into 0.5, 1, 2, and 4 Gy/h, and the exposure time was divided into 1, 3, 5, and 10 minutes. Co-60 source was mixed with the manufactured explosive and X-ray image reading was performed. As a result of the experiment, the X-ray image appeared black in all conditions divided by dose rate and time, and it was impossible to confirm the internal structure of the explosive. This is because γ-rays emitted from radioactive explosives have higher energy and stronger penetrating power than X-rays, so it is believed that imaging using X-rays is limited By blackening the film. The results of this study are expected to be used as basic data for research and development of X-ray imaging that can read the internal structure of explosives in radioactive explosive situations.

• 비파괴검사학회지
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• 제26권3호
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• pp.169-173
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• 2006

In-service diagnoses of pipeline facilities are important for a systematic maintenance of them. Field applications by using sealed gamma-ray sources $(^{60}Co,\;^{137}Cs)$ were performed to identify the heterogeneous zone in the pipelines of a distillation tower and a flare stack respectively. From the results, the heterogeneous zones in the pipelines were successfully identified. In the case of the pipeline connected to the distillation tower, a vapor pocket was detected in the fluid under hydrodynamic conditions, which could explain the reason for a decrease of the flow rate. In another case, an area with some amount of catalyst deposits was found at the bottom of the gas pipeline which was connected to the flare stack. And these findings provided important information for the process operators. Diagnosis technique by using gamma radiation sources has been proven to be an effective and reliable method for providing information on a media distribution in a facility.

• Nuclear Engineering and Technology
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• 제14권2호
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• pp.64-69
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• 1982

동시섬광분석기를 써서, 각도범위 90$^{\circ}$에서 180$^{\circ}$에 대하여, Co-60 및 Cs-134 감마선의 방향상관을 측정하였다. 그리고, 방향-편극상관의 측정에는 컴프턴산란효과를 응용한 감마선 편광분광기를 병용하였다. 이론적인 배경과 더불어 실험방법이 기술되었으며, 측정값이 이론적인 개산치와 일치함을 보이기위해 실험결과를 도식적으로 나타내었다.

• Radiation Oncology Journal
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• 제2권2호
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• pp.271-280
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• 1984

The peripheral dose, defined as the dose outside therapeutic photon fields, which is responsible for the functional damage of the critical organs, fetus, and radiation. induced carcinogenesis, has been investigated for $^{60}Co\;\gamma$ ray and 10 MV Xray. It was measured by silicon diode controlled by semiautomated water phantom without any shielding or with lead plate of HVL thickness put horizontally or vertically to shield stray radiations. Authors could obtain following results. 1. The peripheral dose was larger than $0.7\%$ of central axis maximum dose even at 20cm distance from field margin. That is clinically significant, so it should be reduced. 2. Even for square fields of 10 MV Xray, radial peripheral dose distribution did not coincide with transverse distribution, because of the position of collimator jaws. 3. Between surface and $d_m$, the peripheral dose distributions show a pattern of the dose distribution of electron beams and the maximum doss was approximately proportional to the length of a side of square field. 4. The peripheral doses depended on radiation quality, field size, distance from field margin and depth in water. Distance from field margin was the most important factor. 5. Except for near surface, the peripheral dose from phantom was approximately equal to that from therapy unit. 6. To reduce the surface dose outside fields, therapist should shield stray radiations from therapy unit by lead plate of at least one HVL for 10 MV X-ray and by bolus equivalent to tissue of 0.5cm thickness for $^{60}Co$. 7. To reduce the dose at depth deeper than $d_m$, it is desirable to shield stray radiations from therapy unit by lead.

• Nuclear Engineering and Technology
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• 제52권6호
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• pp.1259-1265
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• 2020

A beta ray scanner was proposed for in-situ discrimination of beta and gamma ray radioactivity. This scanner is based on the principle that gamma and beta rays experience different changes in detection efficiency in scintillators with different geometries, especially with regard to the scintillator thickness. The ratios of the counting rates of gamma rays (R_gamma), beta rays (R_beta), and sample measurements (R_total) in a thick scintillator to those in a thin one are reported. The parameter X_thick, which represents the counting rate contributed by beta rays to the total counting rate in the thick scintillator, was derived as a function of those ratios. The values of R_gamma and R_beta for ⁶⁰Co and ⁹⁰Sr sources were estimated as 3.2 ± 0.057 and 0.99 ± 0.0049, respectively. The estimated beta ray contributions had relative standard deviations of 2.05-4.96%. The estimated range of the beta rays emitted from ⁹⁰Sr was 19 mm as per the Monte Carlo N-Particle simulation, and this value was experimentally verified. Homogeneous and surface contaminations of ⁶⁰Co and ⁹⁰Sr-⁹⁰Y were simulated for application of the proposed method. The counting rate contributed by the beta rays was derived and found to be proportional to the concentration of ⁹⁰Sr-⁹⁰Y contamination.

• 센서학회지
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• 제27권4호
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• pp.232-236
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• 2018

A radiation detection sensor was developed and characterized by combining three types of CsI(Tl) scintillators and an array-type SiPM to detect the radioactive contamination of discharged water in real time. The characterization results showed that type 3 exhibited the most desirable characteristics in response linearity (R-square: 0.97889) according to detection sensitivity and incident radiation dose. Furthermore, in terms of spectral characteristics, type 3 exhibited 16.54% at 0.356 MeV (the emission gamma ray energy of $^{133}Ba$), 10.28% at 0.511 MeV (the emission gamma ray energy of $^{22}Na$), 9.68% at 0.356 MeV (the emission gamma ray energy of $^{137}Cs$), and 2.55% and 4.80% at 1.173 MeV and 1.332 MeV (the emission gamma ray energies of $^{60}Co$), respectively. These measurements confirmed the good energy characteristics. The results were used to evaluate the spectral characteristics and energy linearity in a mixed source using type 3 with the best detection characteristics. It was confirmed that the gamma ray peaks of $^{133}Ba$, $^{22}Na$, $^{137}Cs$, and $^{60}Co$ were well resolved. Moreover, it was confirmed that R-square, which is an indicator of energy linearity, was 0.99986. This indicates a good linearity characteristic. Based on this study, further commercialization studies will contribute to measurements in real time and to the management of the contamination caused by radioactive wastewater or radioactive material leakage, which originate from facilities that use radioactive isotopes or care facilities.

• E2M - 전기 전자와 첨단 소재
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• 제1권3호
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• pp.269-277
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• 1988

P형 Si(100)로 제작한 MOS 커패시터에 $Co^{60}$-.gamma.선을 주사한 후 고주파 C-V특성 곡선으로 부터 방사선 조사에 의해 유발된 산화막안의 트랩전하의 거동 및 Si- $SiO_{2}$계면에서의 트랩밀도 분포의 변화를 검토하였다. 산화막 느랩전하는 .gamma.선 흡수선량 증가와 더불어 증가하다가 $10^{7}$ rad 부근에서부터 서서히 포화하는 경향이 나타났으며 게면트랩밀도의 분포모양은 흡수선량의 증가와 더불어 전형적인 이그러진 W자형에서 넓혀진 V자형 분포로 변화하였으나 최소값은 항상 진성페르미준위( $E_{i}$)부근에 있었으며 그 밀도는 1.0*$10^{11}$~7.5*$10^{11}$[개/$cm^{2}$/eV]로 계산되었다. 또한, 일정 바이어스전압하에서의 조사선량에 따른 $V_{fb}$ 의 변화는 현저하지는 않았으나 바이어스 전압을 +12V로 인가할 때 변화방향의 반전상태가 관측되었다. 그 이유로는 Si측의 계면 부근에서 일어난 눈사태 전자가 산화막내로 주입됨에 따라 도너형 양전하의 수가 감소되기 때문으로 추정되었다.되었다.