• Title/Summary/Keyword: 감마선 검출

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Measuring Circuit Design of RI-Gauge for Compaction Control (성토시공관리용 방사성 동위원소 이용계기의 측정회로설계)

  • Kil, Gyung-Suk;Song, Jae-Yong;Kim, Ki-Joon;Whang, Joo-Ho;Song, Jung-Ho
    • Journal of Sensor Science and Technology
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    • v.6 no.5
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    • pp.385-391
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    • 1997
  • An objection of this study is to develop a measuring circuit of a gauge using radioisotope for compaction control. The gauge developed in this study makes use of radioisotope with the activity exempted from domestic atomic law and consists of measuring circuits for gamma-rays and thermal neutrons, a high voltage supply unit, and a microprocessor. To obtain meaningful numbers of pulse counts, parallel five and two circuits are provided for gamma-rays and thermal neutrons, respectively. Being simple in electrical characteristics of G-M detector for gamma-rays, pulses are counted through only a shaping circuit. Very small pulses generated from He- 3 proportional detector for thermal neutrons are amplified to the maximum of 50 [dB] and a window comparator accepts only pulses with meaning. To minimize effects of natural environmental radiation and electrical noise, circuits are electrostatically shielded and pulses made by ripples are eliminated by taking frequency of high voltage supplied to the circuit and pulse height of ripples into consideration. One-chip microprocessor is applied to process various counts, results are stored and the gauage is made capable to communicate with PC. Enough and meaningful numbers of pulses are counted with the prototype gauage for compaction control.

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The Study on Design of Semiconductor Detector for Checking the Position of a Radioactive Source in an NDT (비파괴검사 분야에서 방사선원의 위치 확인을 위한 반도체 검출기 설계에 관한 연구)

  • Kim, Kyo-Tae;Kim, Joo-Hee;Han, Moo-Jae;Heo, Ye-Ji;Ahn, Ki-Jung;Park, Sung-Kwang
    • Journal of the Korean Society of Radiology
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    • v.11 no.3
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    • pp.171-175
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    • 2017
  • In the non-destructive inspection field, we invest a lot of time and resources in developing the radiation source system to ensure the safety of the workers. However, the probability of accidents is still high. In order to prevent potential radiation accidents in advance, it is necessary to directly verify the position of the radiation source, but the research is still insufficient. In this study, we developed a monitoring system that can detect the position of the radiation source in the source guide tube in the gamma-ray irradiator. The characteristics of the radiation detector are estimated by monte carlo simulation. As a result, the radiation detector for Ir-192 gamma-ray energy was analyzed to have secondary electron equilibrium at $150{\mu}m$ regardless of the semiconductor material. Also, it is expected that the gamma ray response characteristic is the best in $HgI_2$. These results are expected to be used as a basis for determining the optimal thickness of the radiation detector located in the detection part of the future monitoring system. In addition, when developing a monitoring system based on this, radiation workers can easily recognize the danger and secure safety, as well as prevent and preemptively respond to potential radiation accidents.

GAMMA-RAY BURST FORMATION ENVIRONMENT: COMPARISON OF REDSHIFT DISTRIBUTIONS OF GRB AFTERGLOWS (감마선 폭발체의 생성 환경: 에너지 영역별 잔유휘광의 거리 분포 비교)

  • Kim, Sung-Eun;Chang, Heon-Young
    • Journal of Astronomy and Space Sciences
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    • v.22 no.4
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    • pp.377-384
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    • 2005
  • Since gamma-ray bursts(GRBs) have been first known to science societites in 1973, many scientists are involved in their studies. Observations of GRB afterglows provide us with much information on the environment in which the observed GRBs are born. Study of GRB afterglows deals with longer timescale emissions in lower energy bands (e.g., months or even up to years) than prompt emissions in gamma-rays. Not all the bursts accompany afterglows in whole ranges of waveleogths. It has been suggested as a reason for that, for instance, that radio and/or X-ray afterglows are not recorded mainly due to lower sensitivity of detectors, and optical afterglows due to extinctions in intergalactic media or self-extinctions within a host galaxy itself. Based on the idea that these facts may also provide information on the GRE environment, we analyze statistical properties of GRB afterglows. We first select samples of the redshift-known GRBs according to the wavelength of afterglow they accompanied. We then compare their distributious as a function of redshift, using statistical methods. As a results, we find that the distribution of the GRBs with X-ray afterglows is consistent with that of the GRBs with optical afterglows. We, therefore, conclude that the lower detection rate of optical afterglows is not due to extinctions in intergalactic media.

Dose rate conversion factor for soil by the beta-rays and gamma-rays from 238,235U, 232Th and 40K (238,235U, 232Th과 40K의 베타선 및 감마선에 의한 토양의 흡수선량 환산 인자)

  • Kim, Gi-Dong;Eum, Chul-Hun;Bang, Jun-Hwan
    • Analytical Science and Technology
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    • v.20 no.6
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    • pp.460-467
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    • 2007
  • Dose rate conversion factor was calculated to estimate the absorbed effective annual doses for soils for the beta-rays and gamma-rays, which were emitted from $^{238,235}U$, $^{232}Th$, and $^{40}K$ isotopes. The most recent data of the emitted energies per decay, half-lifes, and branching ratios, which were obtained from National Nuclear Data Center, were used. When this factor and the effective annual doses for the beta-rays and the gamma-rays of natural radioisotopes were compared with those of Aitken, these of $^{238}U$, $^{232}Th$ and $^{40}K$ are estimated to have good agreements but a large difference is shown in this for $^{235}U$. Through the calculations of effective annual doses by using these factor and the measurements of gamma-ray spectra for soils, which were extracted from prehistoric remains (Mansuri) on Osong, Chungchengbuk-do, The annual effective doses were obtained to be 3.8~5.9 mGy/yr. Also, when these doses including decay elements upper Rn were compared with those on all isotopes, the differences within 9~30 % were obtained. The analysis method of the annual effective doses for the beta-rays and the gamma-rays of the natural isotopes of soils was established by this dose rate conversion factor.

Development of Gamma Camera System for Small Animal Imaging and Environmental Radiation Detection (소동물 영상화 및 환경 방사선 검출을 위한 감마카메라 개발)

  • Baek, Cheol-Ha
    • The Journal of the Korea Contents Association
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    • v.14 no.2
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    • pp.475-481
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    • 2014
  • The aim of this work was to develop the gamma camera system for small animal gamma imaging and environmental radiation monitoring imaging using a parallel hole collimator and pinhole collimator. The small gamma camera system consists of a CsI(Tl) scintillation crystal with 6 mm in thickness and $50{\times}50mm$ in area coupled with a Hamamatsu H8500C PSPMT, are resistive charge divider, pre-amplifiers, charge amplifiers, nuclear instrument modules (NIMs), an analog to digital converter and a computer for control and display. We have developed a radiation monitoring system composed of a combined pinhole gamma camera and a charge-coupled devices (CCD) camera. The results demonstrated that the parallel hole collimator and pinhole collimator gamma camera designed in this study could be utilized to perform small animal imaging and environmental radiation monitoring system. Consequently in this paper, we proved that our gamma detector system is reliable for a gamma camera which can be used as small animal imaging and environmental radiation monitoring system.

Design a Four Layer Depth-Encoding Detector Using Quasi-Block Scintillator for High Resolution and Sensitivity (고분해능 및 고민감도를 위한 준 블록 섬광체를 사용한 네 층의 반응 깊이 측정 검출기 설계)

  • Seung-Jae Lee;Byungdu Jo
    • Journal of the Korean Society of Radiology
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    • v.18 no.2
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    • pp.65-71
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    • 2024
  • To achieve high resolution and sensitivity of positron emission tomography (PET) for small animals, the detector is constructed using very thin and long scintillation pixels. Due to the structure of these scintillation pixels, spatial resolution deterioration occurs outside the system's field of view. To solve this problem, we designed a detector that could improve spatial resolution by measuring the interaction depth and improve sensitivity by using a quasi-block scintillator. A quasi-block scintillator size of 12.6 mm x 12.6 mm x 3 mm was arranged in four layers, and optical sensors were placed on all sides to collect light generated by the interaction between gamma rays and the scintillator. DETECT2000 simulation was performed to evaluate the performance of the designed detector. Flood images were acquired by generating gamma-ray events at 1 mm intervals from 1.3 mm to 11.3 mm within the scintillator of each layer. The spatial resolution and peak-to-peak distance for each location were measured in an 11 x 11 array of flood images. The average measured spatial resolution was 0.25 mm, and the average distance between peaks was 1.0 mm. Through this, it was confirmed that all locations were separated from each other. In addition, because the light signals of all layers were measured separately from each other, the layer of the scintillator that interacted with the gamma rays could be completely separated. When the designed detector is used as a detector in a PET system for small animals, it is considered that excellent spatial resolution and sensitivity can be achieved and image quality can be improved.

Comparative Measurement of Radioactivity with Standard Gamma-ray Ionization Chamber System (표준 감마선 전리함 장치에 의한 방사능 비교 측정)

  • Park, Tae-Soon;Woo, Dong-Ho;Oh, Pil-Jae;Hwang, Sun-Tae
    • Journal of Radiation Protection and Research
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    • v.9 no.1
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    • pp.11-18
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    • 1984
  • A Standard gamma-ray ionization chamber system was developed with a well type ionization chamber and micro current measuring circuit. Micro current was measured by the automatic Townsend balance with stepwise compensation method. For gamma emitting nuclides such as $^{241}Am,\;^{133}Ba,\;^{60}Co,\;^{134}Cs,\;^{137}Cs,\;and\;^{22}Na$ relative calibration factors to $^{226}Ra$ reference source were calculated and detection .efficiency curve was determined as a fudnction of gamma energy.

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Enrichment Measurement of Nuclear Materials by Passive Gamma-ray Analysis (수동적 감마선분석에 의한 핵물질 농축도 측정)

  • Hong, Jong-Sook;Cha, Hong-Ryul;Park, Hyoung-Nae;Lee, Byung-Doo;Park, Ho-Joon
    • Nuclear Engineering and Technology
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    • v.23 no.2
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    • pp.233-240
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    • 1991
  • U-235 enrichment has been measured non-destructively by passive gamma-ray pulse height analysis. Measurement source is 185.7 keV gamma-ray which is emitted from uranium sample during alpha decay of U-235 in it. Factors influencing the measurement such as sample composition, attenuation effect of container wall, collimation effect and counting efficiency were evaluated. Under the optimized counting system, the measured relative errors were~8%, ~8% and~1% from Tag values at 95% confidence level for depleted UF$_{6}$ cylinders, depleted UO$_2$powder, and natural UO$_2$powder respectively.

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A Study on Spine and Rib Properties for Standoff Compensation, Density Log (밀도검층 이격 보정을 위한 기준선과 이격선의 특성 연구)

  • Kim, Yeonghwa;Kim, Jongman
    • Geophysics and Geophysical Exploration
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    • v.15 no.4
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    • pp.190-198
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    • 2012
  • A series of density log data were obtained from the standoff experiments made in the four physical model boreholes of different densities, and the properties of spine and rib curves have been derived by the analysis of the gamma-gamma data. Particularly, the shape of gamma ray propagation path between source and detector, the geometrical property of spine and rib curves, the influence of borehole density and the detector combination on the properties of the curves, and the adequate detector combination for standoff compensation could be discussed. It was also confirmed that spine and rib slopes can be expressed as proportional to source-to-detector distance ratio between far and near detectors. The result of this experiment was also effectively applied for understanding the basic concept of spine and rib slopes.

Effects of Ozone Treatment and Gamma Irradiation on the Quality Properties of Dried-Spirullina and Dried-Sea Tangle Powders (오존처리와 감마선 조사가 스피루리나와 다시마 분말의 품질특성에 미치는 영향)

  • Byun, Myung-Woo;Yook, Hong-Sun;Kwon, Oh-Jin;Jo, Sung-Kee;Lee, Sung-Hee
    • Korean Journal of Food Science and Technology
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    • v.29 no.4
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    • pp.764-770
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    • 1997
  • For the purpose of improving hygienic quality of dried-spirullina and dried-sea tangle powders as raw materials of health food, the comparative effects of ozone treatment and gamma irradiation on the microbial and physicochemical properties were investigated. Gamma irradiation at 7.5 kGy resulted in sterilization of total aerobic bacteria, coliforms and molds below detective levels $(<10^{1}\;CFU/g\;sample)$, while ozone treatment for 8 hr up to 18 ppm could not sufficiently eliminate the microorganisms of the samples. Physicochemical properties including compositions of fatty acid and amino acid, minerals, pH and natural pigments were not changed by gamma irradaition up to 10 kGy, whereas, ozone treatment caused changes in pH, TBA value, natural pigments and fatty acid compositions. Especially, ozone treatment markedly decreased unsaturated fatty acid of the samples.

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