• Journal of Radiation Protection and Research
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• 제29권4호
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• pp.263-268
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• 2004

한국원자력연구소에서 감마선과 전자를 동시측정하기 위한 목적으로 제작된 Prototype phowich를 이용하여 감마선에 대한 섬광체의 비선형성에 대한 연구를 수행하였다. 제작된 Prototype phoswich는 $2'{\times}2'$ CsI(Tl)와 Plastic scintillator 그리고 하나의 PMT로 구성되어 있다. 몬테칼로 방법을 이용하여 $^{137}Cs$과 $^{60}Co$ 선원의 Prototype phoswich 계측기의 반응함수(Detector Response Function, 이하 DRF)를 구하였으며 이를 점증하기 위하여 제작된 Prototype phoswich를 이용, 실험을 통하여 DRF를 구한 뒤 비교하였다. 계측기의 DRF를 정확하게 모사하기 위하여 CsI(Tl) 섬광체의 Electron response와 섬광체 내에서의 광전효과를 고려하는 Simplified elec윤on cascade sequence 정보를 이용하여 CsI(Tl) 섬광체의 감마선에 대한 비선형성을 계산하였다. $^{137}Cs$ 선원의 경우 전산모사를 통하여 구한 DRF 결과는 실험값과 비교적 잘 일치함을 알 수 있었으나 $^{60}Co$의 경우에는 선원의 결과와는 달리 전산모사 결과와 실험값에 약간의 차이가 남을 알 수 있었다. 이는 $^{137}Cs$ 선원과는 달리 $^{90}Co$은 1.17 MeV와 1.13 MeV 두 개의 광자를 동시에 방출하기 때문에 동시효과에 의한 불착실성 등이 그 외 다른 불확실성 등과 함께 증폭되어 나타나기 때문이다. 본 연구를 통해 Phoswich내 CsI(Tl)의 감마선 비선형성에 대한 분석을 수행하였으며 이를 통하여 비선형성이 고려된 개선된 Phoswich DRF를 생산하고 이를 실험값과 비교 검증할 수 있었다. 섬광체의 Electron channel운g effect, Doppler broadening effect 및 Transfer resolution 등과 같은 후속연구가 추가된다면 좀더 정확한 Phoswich의 DRF를 전산 모사하는 것이 가능해질 것이다.

• 센서학회지
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• 제24권3호
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• pp.202-207
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• 2015

As a feasibility study on development of a gamma imaging probe, we developed a scintillating film-based gamma imaging detector that can obtain scintillation images with information of gamma-ray distribution. The scintillating film-based gamma imaging detector was composed of a sensing probe, an image intensifier, and a beam profiler. To detect and transmit scintillation image, the sensing probe was fabricated by coupling a scintillating film, a fiber-optic image conduit, and a fiber-optic taper, consecutively. First, the optical images of USAF 1951 resolution target were obtained and then, modulation transfer function values were calculated to test the image quality of the sensing probe. Second, we measured the scintillation images according to the activity of the 137Cs and the distance between the surface of 137Cs and the distal-end of sensing probe. Finally, the intensities of scintillating light as functions of the activity and the distance were evaluated from the region of interest in the scintillation image. From the results of this study, it is expected that a fiber-optic gamma imaging detector can be developed to detect gamma-rays emitted from radiopharmaceuticals during radioimmunoguided surgery.

• Journal of Radiation Protection and Research
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• 제40권2호
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• pp.73-78
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• 2015

본 연구에서는 실리콘 광 증배소자(Silicon photomultiplier)와 Ce:GAGG 섬광체 단결정을 이용한 섬광검출기를 제작하고, 감마선 분광특성 분석을 통해 기존에 상용화된 LYSO, CsI:Tl 섬광체와의 분광특성을 비교하였다. 섬광체 단결정의 크기는 $3{\times}3{\times}20mm^3$ 이며 $3{\times}3mm^2$ 실리콘 광 증배소자를 이용하여 섬광검출기를 제작한 후, 표준 감마선원인 $^{133}Ba$, $^{22}Na$, $^{137}Cs$, $^{60}Co$에 대한 에너지 분해능을 각각 측정하고 비교하였다. 그 결과 Ce:GAGG 섬광검출기의 감마선에 대한 에너지 분해능은 $^{133}Ba$ 0.356 MeV에서 13.5%, $^{22}Na$ 0.511 MeV에서 6.9%, $^{137}Cs$ 0.662 MeV에서 5.8% 그리고 $^{60}Co$ 1.33 MeV에서 2.3%의 분광 특성을 확인 할 수 있었다.

• Nuclear Engineering and Technology
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• 제7권4호
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• pp.285-293
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• 1975

30cm 직경 포리에티렌 구체내의 길이에 따른 선량분포중 최대흡수선량인 흡수선량지수를 주어진 감마방사선장내에서 열형광선량계를 이용하여 결정하였다. 열형광선량계내의 흡수선량과 주위 눈질내의 흡수선량간의 환산은 Burlin의 general cavity theory에 의거하였다. $^{60}$Co과 $^{137}$Cs에 의한 방사선장에서 구체내 최대흡수선량은 구체표면으로 부터 각각 0.5cm 및 0.3cm에 나타났으며 이 결과는 이론적으로 예상한 분포특성과 아주 근사하였다.

• Journal of Radiation Protection and Research
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• 제34권2호
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• pp.83-86
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• 2009

The single crystal scintillator of bismuth germinate ($Bi_4Ge_3O_{12}$:BGO) was successfully grown by the conventional Czochraski technique. The characteristics of the grown BGO were evaluated and presented on the excitation, emission responses and energy spectra of the $\gamma$-rays from $^{241}Am$, $^{133}Ba$, $^{57}Co$, $^{22}Na$, $^{137}Cs$ and $^{54}Mn$ radio-isotopes. The energy resolution of grown BGO, $\Delta$E/E, was estimated to be 12.1% at 662 keV of $\gamma$-ray for $^{137}Cs$ nuclide. Compared to the commercial BGO crystal, we confirmed that the grown BGO has a good performance and is comparable to reference one.

• Journal of Radiation Protection and Research
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• 제41권2호
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• pp.179-183
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• 2016

Background: As an important detecting device, TLD is a widely used in the radiation monitoring. It is essential for us to study the property of detecting element. The aim of this study is to calculate the thermo-luminescence efficiency of TL elements. Materials and Methods: A batch of thermo-luminescence elements were irradiated by the filtered X-ray beams of average energies in the range 40-200 kVp, 662 keV $^{137}Cs$ gamma rays and then the amounts of lights were measured by the TL reader. The deposition energies in elements were calculated by theory formula and Monte Carlo simulation. The unit absorbed dose in elements by photons with different energies corresponding to the amounts of lights was calculated, which is called the thermo luminescent efficiency (${\eta}^{(E)}$). Because of the amounts of lights can be calculated by the absorbed dose in elements multiply ${\eta}^{(E)}$, the ${\eta}^{(E)}$ can be calculated by the experimental data (the amounts of lights) divided by absorbed dose. Results and Discussion: The deviation of simulation results compared with theoretical calculation results were less than 5%, so the absorbed dose in elements was calculated by simulation results in here. The change range of ${\eta}^{(E)}$ value, relative to 662 keV $^{137}Cs$ gamma rays, is about 30% in the energy range of 33 keV to 662 keV, is in accordance by the comparison with relevant foreign literatures. Conclusion: The ${\eta}^{(E)}$ values can be used for updating the amounts of lights that are got by the direct ratio assumed relations with deposition energy in TL elements, which can largely reduce the error of calculation results of the amounts of lights. These data can be used for the design of individual dosimeter which used TLD-2000 thermo-luminescence elements, also have a certain reference value for manufacturer to improve the energy-response performance of TL elements by formulation adjustment.

• 전기전자학회논문지
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• 제20권2호
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• pp.123-127
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• 2016

본 연구에서는 $3mm{\times}3mm{\times}2mm$, $3mm(Dia){\times}15mm$, $3mm(Dia){\times}20mm$, $10mm(Dia){\times}20mm$. YSO 섬광체와 광전자증배관을 결합하여 검출기를 제작하였다. 또한 10mm의 지름을 가진 섬광체는 LightTools를 이용하여 최적화한 광가이드와 결합하였다. 광가이드의 두께는 2mm이며 입사부는 섬광체 크기와 같은 10mm이고 출사부는 다른 섬광체와 같은 3mm이다. 제작된 검출기는 표준 감마선원인 $^{137}Cs$를 이용하여 분광 특성을 분석하였다. 그 결과 662keV에서 각각의 에너지 분해능이 14.46%, 21.10%, 10.71%, 나왔으며 10mm의 지름과 20mm의 길이를 가진 섬광체에 광가이를 결합한 섬광체가 7.48%로 분해능이 가장 좋게 나왔다.

• 센서학회지
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• 제19권6호
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• pp.443-448
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• 2010

In this work, the scintillation properties of CsI:Na crystal were investigated as radiation detection sensor. This scintillation material was grown by a 2-zone vertical Bridgman method. Under X-ray excitation the crystal shows a broad emission band between 280 nm and 690 nm wavelength range, peaking at 413 nm. Energy resolution for $^{137}Cs$ 662 keV $\gamma$-rays of the crystal was measured to be 6.9 %(FWHM). At room temperature, the crystal exhibits three exponential decay time components. The fast and major component of scintillation time profile of the crystal emission decays with a 457 ns time constant. Absolute light yield of the crystal was estimated to be 53,000 ph/MeV using LAAPD. The sample crystal shows proportionality of 30 % in the measured energy range from 31 to 1,333 keV. And the $\alpha/\beta$ ratio of the crystal was 0.14.

• Journal of Radiation Protection and Research
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• 제43권3호
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• pp.85-96
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• 2018

Background: A variety of inorganic scintillators have been developed and improved for use in radiation detection and measurement, and in situ gamma-ray spectrometry in the environment remains an important area in nuclear safety. In order to verify the feasibility of promising scintillators in an actual environment, a performance test is necessary to identify gamma-ray peaks and calculate the radioactivity from their net count rates in peaks. Materials and Methods: Among commercially available scintillators, $LaBr_3(Ce)$ scintillators have so far shown the highest energy resolution when detecting and identifying gamma-rays. However, the intrinsic background of this scintillator type affects efficient application to the environment with a relatively low count rate. An algorithm to subtract the intrinsic background was consequently developed, and the in situ calibration factor at 1 m above ground level was calculated from Monte Carlo simulation in order to determine the radioactivity from the measured net count rate. Results and Discussion: The radioactivity of six natural radionuclides in the environment was evaluated from in situ gamma-ray spectrometry using an $LaBr_3(Ce)$ detector. The results were then compared with those of a portable high purity Ge (HPGe) detector with in situ object counting system (ISOCS) software at the same sites. In addition, the radioactive cesium in the ground of Jeju Island, South Korea, was determined with the same assumption of the source distribution between measurements using two detectors. Conclusion: Good agreement between both detectors was achieved in the in situ gamma-ray spectrometry of natural as well as artificial radionuclides in the ground. This means that an $LaBr_3(Ce)$ detector can produce reliable and stable results of radioactivity in the ground from the measured energy spectrum of incident gamma-rays at 1 m above the ground.

• Nuclear Engineering and Technology
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• 제56권5호
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• pp.1667-1671
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• 2024

This paper presents a neutron/gamma detector based on a micropixel avalanche photodiode and a plastic scintillator that monitors the status of the accelerator-driven intense resonance neutron source (IREN) facility by measuring the neutron/gamma intensity in the target hall. The electronics of the neutron/gamma detector has been designed and developed. The size of the plastic scintillator was selected to be 3.7 × 3.7 × 30 mm³ due to the sensitive area of the MAPD. The experimental results demonstrated a dependence between the count rate of the detector and the frequency of the accelerator. The detector is sensitive to intermediate and fast neutrons. The minimum detectable energy was determined to be 200 keV using Cs-137 point gamma source. The maximum counting rate of the detector from TTL out is about 2.2⋅10⁶ counts/sec, but for analogue output it is about 2⋅10⁷ counts/sec. The detector can not allow discriminating neutrons and gamma rays by charge integration method.