• 제목/요약/키워드: Radiation Detection Energy Response

검색결과 30건 처리시간 0.024초

Distribution of ddr (DNA damage response) Genes among Species of Deinococcus

  • Lim, Sangyong;Jung, Sunwook;Joe, Minho;Kim, Dongho
    • 방사선산업학회지
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    • 제4권3호
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    • pp.289-295
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    • 2010
  • The bacterium Deinococcus radiodurans is one of the most resistant organisms to the effects of ionizing radiation and other DNA-damaging agents. In this study, distributions of 10 ddr (DNA damage response) genes were investigated in 8 species of Deinococcus by polymerase chain reaction (PCR). We have compared the sequences of ddr genes of D. radiodurans, D. geothermalis and D. deserti, and selected primers which are suitable for the detection of ddr in different species of Deinococcus. A sequence homology search and PCR assay showed that ddrO, which encodes a global regulator of the radiation-desiccation response, was most well conserved in the Deinococcus lineage.

반도체 검출기를 이용한 Hybrid 전치증폭기형 전자식 개인선량계 개발 (Development of Electronic Personal Dosimeter with Hybrid Preamplifier using Semiconductor Detector)

  • 이봉재;김봉환;장시영;김종수;노승용
    • Journal of Radiation Protection and Research
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    • 제27권1호
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    • pp.51-57
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    • 2002
  • 반도체 검출기를 이용하여 Hybrid 전치증폭기를 갖는 전자식 개인선량계를 설계 제작하고, 방사선 검출 반응특성과 기계적 및 주변 환경 요건에 따른 각종 성능을 평가하였다. $^{137}Cs$ 감마 방사선을 이용한 방사선 조사 시험결과 감도는 $3.8\;cps/Gy{\cdot}h^{-1}$이고, $10{\mu}Sv{\sim}4Sv$ 범위의 선량당량 조사시 선량계의 지시값은 오차 8%이하에서 선형성이 잘 유지되었다. 방향의존성을 ${\pm}60^{\circ}$ 이내에서 4%이하이며, ISO 기준선장에 의한 에너지 반응영역은 $60{\sim}1,250\;keV$로 나타났으며, IEC 61526에 의한 선량계의 성능검사시 9개 영역의 시험항목에 대한 국제기준을 만족하였다.

CHARACTERISTICS OF FABRICATED SiC RADIATION DETECTORS FOR FAST NEUTRON DETECTION

  • Lee, Cheol-Ho;Kim, Han-Soo;Ha, Jang-Ho;Park, Se-Hwan;Park, Hyeon-Seo;Kim, Gi-Dong;Park, June-Sic;Kim, Yong-Kyun
    • Journal of Radiation Protection and Research
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    • 제37권2호
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    • pp.70-74
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    • 2012
  • Silicon carbide (SiC) is a promising material for neutron detection at harsh environments because of its capability to withstand strong radiation fields and high temperatures. Two PIN-type SiC semiconductor neutron detectors, which can be used for nuclear power plant (NPP) applications, such as in-core reactor neutron flux monitoring and measurement, were designed and fabricated. As a preliminary test, MCNPX simulations were performed to estimate reaction probabilities with respect to neutron energies. In the experiment, I-V curves were measured to confirm the diode characteristic of the detectors, and pulse height spectra were measured for neutron responses by using a $^{252}Cf$ neutron source at KRISS (Korea Research Institute of Standards and Science), and a Tandem accelerator at KIGAM (Korea Institute of Geoscience and Mineral Resources). The neutron counts of the detector were linearly increased as the incident neutron flux got larger.

이동형 핵종 분석 장치용 CZT 반도체 검출기의 완충전극에 대한 연구 (A Study of Interface Layer on CdZnTe Radiation Sensor for Potable Isotope Identifier)

  • 조윤호;박세환;김용균;하장호
    • 방사선산업학회지
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    • 제5권1호
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    • pp.95-99
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    • 2011
  • The electrical and mechanical properties of electrode for radiation detection are very important. In general, Au electrode and CZT crystal are combined to form ohmic contacts, and the best energy resolution is shown at the Au electrode. The metal contacts are fabricated by electroless deposition method, sputtering deposition method and thermal evaporation method. The electrode fabrication is easy with use of the thermal evaporation method, while an adhesive strength is weak. Thus interface materials such as Ag, Al and Ni were investigated to overcome defects generated by the this method. The thickness of the interface material between the Au electrode and the CZT crystal was 100 Angstroms, the Au electrode with thickness of 400 Angstroms was deposited. The Al+Au electrode is shown that the results of current-voltage and radiation response are similar to results of Au electrode.

과도방사선 검출을 위한 핵폭발 검출기 제작 및 검증 (A Nuclear Event Detectors Fabrication and Verification for Detection of a Transient Radiation)

  • 정상훈;이승민;이남호;김하철;조성익
    • 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.

Influence of the Thin-Film Ag Electrode Deposition Thickness on the Current Characteristics of a CVD Diamond Radiation Detector

  • Ban, Chae-Min;Lee, Chul-Yong;Jun, Byung-Hyuk
    • Journal of Radiation Protection and Research
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    • 제43권4호
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    • pp.131-136
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    • 2018
  • Background: We investigated the current characteristics of a thin-film Ag electrode on a chemical vapor deposition (CVD) diamond. The CVD diamond is widely recognized as a radiation detection material because of its high tolerance against high radiation, stable response to various dose rates, and good sensitivity. Additionally, thin-film Ag has been widely used as an electrode with high electrical conductivity. Materials and Methods: Considering these properties, the thin-film Ag electrode was deposited onto CVD diamonds with varied deposition thicknesses (${\fallingdotseq}50/98/152/257nm$); subsequently, the surface thickness, surface roughness, leakage current, and photo-current were characterized. Results and Discussion: The leakage current was found to be very low, and the photo-current output signal was observed as stable for a deposited film thickness of 98 nm; at this thickness, a uniform and constant surface roughness of the deposited thin-film Ag electrode were obtained. Conclusion: We found that a CVD diamond radiation detector with a thin-film Ag electrode deposition thickness close to 100 nm exhibited minimal leakage current and yielded a highly stable output signal.

방류수의 방사능 오염 측정을 위한 배열형 SiPM 기반 방사선 검출 센서 제작 (Development of Radiation Sensor Based on Array SiPM for Measurement of Radioactive Contamination in Effluent)

  • 김정호;박혜민;주관식
    • 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.

A Review of Dose Rate Meters as First Responders to Ionising Radiation

  • Akber, Aqeel Ahmad;Wiggins, Matthew Benfield
    • Journal of Radiation Protection and Research
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    • 제44권3호
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    • pp.97-102
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    • 2019
  • Background: Dose rate meters are the most widely used, and perhaps one of the most important tools for the measurement of ionising radiation. They are often the first, or only, device available to a user for an instant check of radiation dose at a certain location. Throughout the world, radiation safety practices rely strongly on the output of these dose rate meters. But how well do we know the quality of their output? Materials and Methods: This review is based on the measurements 1,158 commercially available dose rate meters of 116 different makes and models. Expected versus the displayed dose patterns and consistency was checked at various dose rates between $5{\mu}Gy{\cdot}h^{-1}$ and $2mGy{\cdot}h^{-1}$. Samples of these meters were then selected for further investigation and were exposed to radiation sources covering photon energies from 50 keV to 1.5 MeV. The effect of detector orientation on its reading was also investigated. Rather than focusing on the angular response distribution that is often reported by the manufacturer of the device, this study focussed on the design ergonomics i.e. the angles that the operator will realistically use to measure a dose rate. Results and Discussion: This review shows the scope and boundaries of the ionising radiation dose rate estimations that are made using commonly available meters. Observations showed both inter and intra make and model variations, occasional cases of instrument failure, instrument walk away, and erroneous response. Conclusion: The results indicate the significance of selecting and maintaining suitable monitors for specific applications in radiation safety.

Development and Performance of a Hand-Held CZT Detector for In-Situ Measurements at the Emergency Response

  • Ji, Young-Yong;Chung, Kun Ho;Kim, Chang-Jong;Yoon, Jin;Lee, Wanno;Choi, Geun-Sik;Kang, Mun Ja
    • Journal of Radiation Protection and Research
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    • 제41권2호
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    • pp.87-91
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    • 2016
  • Background: A hand-held detector for an emergency response was developed for nuclide identification and to estimate the information of the ambient dose rate in the scene of an accident as well as the radioactivity of the contaminants. Materials and Methods: To achieve this, the most suitable sensor was first selected as a cadmium zinc telluride (CZT) semiconductor and the signal processing unit from a sensor and the signal discrimination and storage unit were successfully manufactured on a printed circuit board. Results and Discussion: The performance of the developed signal processing unit was then evaluated to have an energy resolution of about 14 keV at 662 keV. The system control unit was also designed to operate the CZT detector, monitor the detector, battery, and interface status, and check and transmit the measured results of the ambient dose rate and radioactivity. In addition, a collimator, which can control the inner radius, and the airborne dust sampler, which consists of an air filter and charcoal filter, were developed and mounted to the developed CZT detector for the quick and efficient response of a nuclear accident. Conclusion: The hand-held CZT detector was developed to make the in-situ gamma-ray spectrometry and its performance was checked to have a good energy resolution. In addition, the collimator and the airborne dust sampler were developed and mounted to the developed CZT detector for a quick and efficient response to a nuclear accident.

CCD 카메라를 이용한 방사선 탐지기의 영상화 기술 연구 (Design and Implementation of an optical wavelength analyzer)

  • 박성훈;박종원;이남호
    • 한국정보통신학회:학술대회논문집
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    • 한국정보통신학회 2013년도 춘계학술대회
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    • pp.811-813
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    • 2013
  • 방사선을 측정하기 위해서는 여러 종류의 센서가 있다. 그 센서들 중에서 콜리메이터와 신틸레이터 통해 CCD 센서에서 감도나 센싱 방법을 사용하였다. 본 연구에서는 해상도가 높은 CCD 센서를 이용하여 방사선을 검출하는데, 신틸레이터 통해 CCD에 들어오는 영상에서 방사선에 반응하여 생기는 가시광선을 처리하여 방사선량을 측정하고 공간상에서 방사선이 가장 많이 나오는 포인터를 제시하는 것이다. 추후 영상을 스테레오 카메라 방식의 구현하여 방사선원까지 거리 산출하고 영상화하는 것이다.

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