• Title/Summary/Keyword: Gamma-ray source

검색결과 276건 처리시간 0.027초

Analytical-numerical formula for estimating the characteristics of a cylindrical NaI(Tl) gamma-ray detector with a side-through hole

  • Thabet, Abouzeid A.;Badawi, Mohamed S.
    • Nuclear Engineering and Technology
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    • 제54권10호
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    • pp.3795-3802
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    • 2022
  • NaI(Tl) scintillation materials are considered to be one of many materials that are used exclusively for γ-ray detection and spectroscopy. The gamma-ray spectrometer is not an easy-to-use device, and the accuracy of the numerical values must be carefully checked based on the rules of the calibration technique. Therefore, accurate information about the detection system and its effectiveness is of greater importance. The purpose of this study is to estimate, using an analytical-numerical formula (ANF), the purely geometric solid angle, geometric efficiency, and total efficiency of a cylindrical NaI(Tl) γ-ray detector with a side-through hole. This type of detector is ideal for scanning fuel rods and pipelines, as well as for performing radio-immunoassays. The study included the calculation of the complex solid angle, in combination with the use of various points like gamma sources, located axially and non-axially inside the through detector side hole, which can be applied in a hypothetical method for calibrating the facility. An extended γ-ray energy range, the detector, source dimensions, "source-to-detector" geometry inside the side-through hole, path lengths of γ-quanta photons crossing the facility, besides the photon average path length inside the detector medium itself, were studied and considered. This study is very important for an expanded future article where the radioactive point source can be replaced by a volume source located inside the side-trough hole of the detector, or by a radioactive pipeline passing through the well. The results provide a good and useful approach to a new generation of detectors that can be used for low-level radiation that needs to be measured efficiently.

감마선을 이용한 단열배관의 실시간 두께측정시스템 개발 (Development of Real-Time Thickness Measuring System for Insulated Pipeline Using Gamma-ray)

  • 장지훈;김병주;김기동;조경식
    • 비파괴검사학회지
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    • 제22권5호
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    • pp.500-507
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    • 2002
  • 본 연구에서는 감마선과 섬광체 및 광 다이오드로 구성된 64 채널의 선형 디텍터 어레이를 이용하여 보온재로 싸인 배관의 두께를 실시간으로 측정하는 시스템을 개발하였다. 본 측정시스템은 감마선원으로 Ir-192를 사용하였으며, 디텍터는 BGO 섬광체와 광다이오드로 구성하였다. Ir-192 방사선원은 배관의 한쪽 편에, 그리고 디텍터 어레이는 배관을 중심으로 그 반대편에 위치하며 컴퓨터로 제어되는 주행 시스템에 실려 배관을 따라 이송되는 동안 배관과 단열재를 투과한 방사선의 강도는 각 디텍터에서 측정된다. 측정된 디텍터 어레이의 출력은 증폭기에서 증폭된 후 케이블에 의해 컴퓨터로 전송되며 주행시스템이 진행하는 동안 컴퓨터는 수집된 신호를 분석 및 계산하여 실제의 두께를 나타내며 주사간격을 1mm로 할 경우의 최대 측정속도는 분당 120cm이다.

What we have learned about Gamma-ray bright AGNs using the iMOGABA program

  • Lee, Sang-Sung
    • 천문학회보
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    • 제42권2호
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    • pp.45.1-45.1
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    • 2017
  • A Korean VLBI Network Key Science Program, the Interferometric Monitoring of Gamma-ray Bright AGNs (iMOGABA) program continues to aim at revealing the origins of the gamma-ray flares that are often detected in active galactic nuclei (AGNs). Here in this presentation, we would like to present what we have learned about the Gamma-ray bright AGNs based on the recent results of the Korean VLBI Network Key Science Program: the iMGOABA. The results will include a) the source properties of the whole samples obtained from a single-epoch observation, and b) some of scientific highlights for the iMOGAGBA on specific sources. From those highlighted works, we find that the Gamma-ray bright AGNs become fainter at higher frequencies, yielding optically thin spectra at mm wavelengths. Based on the studies on specific sources, taking into account the synchrotron self-absorption model of the relativistic jet, we estimated the magnetic field strength in the mas emission region during the observing period.

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Region-wise evaluation of gamma-ray exposure dose in decontamination operation after a nuclear accident

  • Jeong, Hae Sun;Hwang, Won Tae;Han, Moon Hee;Kim, Eun Han;Lee, Jo Eun;Lee, Cheol Woo
    • Nuclear Engineering and Technology
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    • 제53권8호
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    • pp.2652-2660
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    • 2021
  • The gamma-ray exposure doses in decontamination operation after a nuclear accident were evaluated with a consideration of various geometrical conditions and specific gamma-ray energies. The calculation domain is organized with three residence types and each form is divided into two kinds of geometrical arrangements. The position-wise air KERMA values were calculated with an assumption of evenly distributed gamma-ray source based on Monte Carlo radiation transport analysis using the MCNP code. The radioactivity is initially set to be unity to be multiplied by the deposition value measured in the actual accident condition. The workforce data set depending on the target object was determined by modifying the Fukushima report. The external exposure doses for decontamination workers were derived from the calculated KERMA values and the workforce analysis. These results can be used to efficiently determine the workforce required by the characteristics of the area and the structure to be decontaminated within the dose limits.

SCALE-ORIGEN-ARP를 이용한 사용후핵연료 내 중성자 및 감마선원 분석 (An analysis of neutron sources and gamma-ray in spent fuels using SCALE-ORIGEN-ARP)

  • 차소희;박광헌
    • 한국표면공학회지
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    • 제56권1호
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    • pp.84-93
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    • 2023
  • The spent nuclear fuel is burned during the planned cycle in the plant and then generates elements such as actinide series, fission products, and plutonium with a long half-life. An 'interim storage' step is needed to manage the high radioactivity and heat emitted by nuclides until permanent-disposal. In the case of Korea, there is no space to dispose of high-level radioactive waste after use, so there is a need for a period of time using interim storage. Therefore, the intensity of neutrons and gamma-ray must be determined to ensure the integrity of spent nuclear fuel during interim storage. In particular, the most important thing in spent nuclear fuel is burnup evaluation, estimation of the source term of neutrons and gamma-ray is regarded as a reference measurement of the burnup evaluation. In this study, an analysis of spent nuclear fuel was conducted by setting up a virtual fuel burnup case based on CE16×16 fuel to check the total amount and spectrum of neutron, gamma radiation produced. The correlation between BU (burnup), IE (enrichment), and CT (cooling time) will be identified through spent nuclear fuel burnup calculation. In addition, the composition of nuclide inventory, actinide and fission products can be identified.

Efficiency calibration and coincidence summing correction for a NaI(Tl) spherical detector

  • Noureddine, Salam F.;Abbas, Mahmoud I.;Badawi, Mohamed S.
    • Nuclear Engineering and Technology
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    • 제53권10호
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    • pp.3421-3430
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    • 2021
  • Spherical NaI(Tl) detectors are used in gamma-ray spectrometry, where the gamma emissions come from the nuclei with energies in the range from a few keV up to 10 MeV. A spherical detector is aimed to give a good response to photons, which depends on their direction of travel concerning the detector center. Some distortions in the response of a gamma-ray detector with a different geometry can occur because of the non-uniform position of the source from the detector surface. The present work describes the calibration of a NaI(Tl) spherical detector using both an experimental technique and a numerical simulation method (NSM). The NSM is based on an efficiency transfer method (ETM, calculating the effective solid angle, the total efficiency, and the full-energy peak efficiency). Besides, there is a high probability for a source-to-detector distance less than 15 cm to have pulse coincidence summing (CS), which may occur when two successive photons of different energies from the same source are detected within a very short response time. Therefore, γ-γ ray CS factors are calculated numerically for a 152Eu radioactive cylindrical source. The CS factors obtained are applied to correct the measured efficiency values for the radioactive volumetric source at different energies. The results show a good agreement between the NSM and the experimental values (after correction with the CS factors).

감마선원의 공간분포 가시화 및 3D모델링을 위한 운용환경 개발 (Development of High-Sensitivity Detection Sensor and Module for Spatial Distribution Measurement of Multi Gamma Sources)

  • 송근영;임지석;최정혁;육영호;황영관;이남호
    • 한국정보통신학회:학술대회논문집
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    • 한국정보통신학회 2017년도 추계학술대회
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    • pp.702-704
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    • 2017
  • 원전 해체 및 사고 시 신속한 제염작업을 위해서는 감마선원에 대한 정확한 정보가 필수적이다. 제거해야할 감마선원의 위치를 보다 효율적으로 나타내기 위하여 실측영상을 기반으로 한 공간영역을 생성하고. 방사선원의 분포를 표현함으로써 보다 신속하게 감마선원의 제염작업을 수행할 수 있다. 기 개발된 감마선 영상화 장치는 감마선원에 대한 탐지 후 가시영상과 중첩하여 2차원 영상만을 제공하고 있지만 선원까지의 거리정보 등은 나타내지 못하고 있다. 본 논문에서는 보다 효율적인 제염작업을 위해 감마선원에 대한 분포정보와 함께 거리값을 기반으로 한 3차원 모델링 결과의 산출하고 사용자가 직접 확인할 수 있는 가시화 및 운용환경 개발에 대하여 연구하였다. 본 논문의 결과는 향후 스테레오기반의 감마선 탐지장치의 성능개선을 위해 활용될 것이다.

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Source and LVis based coincidence summing correction in HPGe gamma-ray spectrometry

  • Lee, Jieun;Kim, HyoJin;Kye, Yong Uk;Lee, Dong Yeon;Kim, Jeung Kee;Jo, Wol Soon;Kang, Yeong-Rok
    • Nuclear Engineering and Technology
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    • 제54권5호
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    • pp.1754-1759
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    • 2022
  • The activity of gamma-ray emitting nuclides is calculated assuming that each gamma-ray is detected individually; thus, the magnitude of the coincidence summing signal must be considered during activity calculations. Here, the correction factor for the coincidence summing effect was calculated, and the detection efficiencies of two HPGe detectors were compared. The CANBERRA Inc. GC4018 high-purity Ge detector provided an estimate for the peak-to-total ratio using a point source to determine the coincidence summing correction factor. The ORTEC Inc. GEM60 high-purity Ge detector uses EFFTRAN in LVis to obtain the parameters of the detector and source model and the gamma-gamma and gamma-X match estimates, in order to determine the coincidence summing correction factor. Nuclide analyses, radioactivity comparisons, and analyses of reference material samples were performed utilizing certified reference materials to accurately determine the detection efficiencies. For both Co-60 and Y-88, the detection efficiency for a point source increased by an average of at least 12-13%, whereas the detection efficiency determined using LVis increased by an average of at least 13-15%. The calculated radioactivity values of the certified reference material and reference material samples were accurate to within 3% and 6% of the measured values, respectively.

Exploring the Extra Component in the Gamma-ray Emission of the New Redback Candidate 3FGL J2039.6-5618

  • Ng, Cho-Wing;Cheng, Kwong-Sang;Takata, Jumpei
    • Journal of Astronomy and Space Sciences
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    • 제33권2호
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    • pp.93-99
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    • 2016
  • A redback system is a binary system composed of a pulsar and a main sequence star. The inverse Compton (IC) scattering between the stellar soft photons and the relativistic pulsar wind will generate orbital-modulating GeV photons. We look for these IC emissions from redback systems. A multi-wavelength observation of an unassociated gamma-ray source, 3FGL J2039.6-5618, by Salvetti et al. (2015) detected an orbital modulation with a period of 0.2 days in both X-ray and optical cases. They suggested 3FGL J2039.6-5618 to be a new redback candidate. We analyzed the gamma-ray emission of 3FGL J2039.6-5618 using the data from the Fermi large area telescope (Fermi-LAT) and obtained the spectrum in different orbital phases. We propose that the spectrum has orbital dependency and estimate the characteristic energy of the IC emission from the stellar-pulsar wind interaction.

감마선 및 전자선 조사에 따른 톳 자숙액 에탄올 추출물의 색상 및 생물학적 활성 변화 비교 (The Comparison of Color and Physiological Properties of Hizikia fusiformis Cooking Juice Ethanol Extract Irradiated with Gamma Ray and Electron Beam)

  • 최종일;김현주
    • KSBB Journal
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    • 제27권3호
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    • pp.195-198
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    • 2012
  • This study was carried out to assess the effect of radiation on the changes of Hizikia fusiformis cooking juice ethanol extract and to compare the effect of gamma ray and electron beam. On the applying radiation, the dark color of cooking juice became changed with higher brightness and lower redness and yellowness. But, there was no difference between gamma ray radiation and electron beam radiation. 1,1-Diphenyl-2-picryl-hydrazyl radical scavenging activity and tyrosinase inhibitory activity of cooking juice were shown to be increased by radiation independent on the radiation source types. The reason for the increased biological activities was caused by higher content of total phenolic compounds. The results could be applied to investigate the effect of radiation source on the color and antioxidant activity of biomaterials, and it was thought that irradiation could be an promising method for enhancing the biological activity of biomaterials.