• 방사선산업학회지
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• 제17권1호
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• pp.119-125
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• 2023

Burnup of spent nuclear fuel should be determined accurately for the safety storage of spent nuclear fuel. In this study, a gamma detection system was developed as a part of basic research to measure the burnup of spent nuclear fuel, and its performance was evaluated using a calibration source. The prototype of the gamma detection system was based on a semiconductor sensor using a CZT (Cadmium Zinc Telluride). For quantitative evaluation, tests were conducted using ¹³⁷Cs, ¹³⁴Cs and ²⁵²Cf calibration source. In the performance evaluation, Its field applicability was verified by assessing the energy resolution, the detection linearity and the shielding attenuation according to the nuclide.

• 핵의학기술
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• 제22권2호
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• pp.105-111
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• 2018

Purpose Quality control of instrument takes up a large part in the Radioimmunoassays. The gamma-ray instrument, which is one of the important instruments in the laboratory, observes the condition and performance of instrument and performs quality control of the instrument by measuring the Normalization, Calibration, Background and etc. However, there are some automation instruments which can't measure the counting efficiency of gamma-ray meters, resulting in insufficient management in terms of performance evaluation of gamma-ray meters. Therefore, the purpose of this paper is to manage the quality control continuously and regularly by suggesting how to measure the counting efficiency of gamma-ray instruments. Materials and Methods In case of a comparative measurement method to a gamma-ray instrument dedicated to nuclear medical examination, the CPM and counting efficiency can be obtained after the measurement of normalization by inserting the I-125 $200{\mu}L$(CPM 50,000~500,000) into the test tube. With this CPM and counting efficiency values, it's possible to calculate the measurement of the DPM value and count the CPM from the automation instrument from the same source, and enter the DPM to calculate the counting efficiency using a comparative measurement method. Another method is to calculate the counting efficiency by estimating the half life using the radiation source information of the tracer in B test reagents of company A. Results According to the calculation formula using the DPM obtained by counting the normalization of gamma-ray meters, the detection efficiency was 75.16% for Detector 1, 76.88% for Detector 2, 77.13% for Detector 3, 75.36% for Detector 4 and 73.2% for Detector 5 respectively. Using another calculation formula estimated from the shelf life, the data of the detection efficiency from Detector 1 to Detector 5 were 74.9%, 75.1%, 76.5%, 74.9% and 73.2% respectively. Conclusion Although the accuracy of counting efficiencies of both methods are insufficient, this is considered to be useful for ongoing management of quality control if counting efficiency is managed after setting the acceptable ranges. For example, if the measurement efficiency is set to 70% or higher, the allowed %difference between measurements is within 3% and the %difference with the detector wall is set within 5%.

• Nuclear Engineering and Technology
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• 제54권2호
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• pp.423-428
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• 2022

Very low contents (in the range of 10^-9 g/g) of Ir in mantle-derived rock samples (komatiites) were non-destructively determined by INAA coupled with coincidence gamma-ray spectrometry using 16 Ge detectors. Aliquots of the same samples were analyzed by NiS fire-assay ICP-MS for Ir and other platinum group elements. Because the INAA procedure used in this study is non-destructive and is almost free from spectral interference in gamma-ray spectrometry, the INAA values of Ir contents obtained in this study can be highly reliable. Iridium values obtained by ICP-MS were consistent with the INAA values, implying that the ICP-MS values of Ir obtained in this study are equally reliable. Under the present experimental conditions, detection limits were estimated to be 1 pg/g, which corresponds to 0.1 pg for a sample mass of 0.1 g. These levels can be even lowered by an order of magnitude, if necessary, which cannot be achieved by ICP-MS carried out in this study.

• 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.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(2)
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• pp.464-469
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• 1998

A coincidence gamma-ray spectroscopy method was applied to reduce the background radioactivity for measuring the activity of radioisotopes in a sample in the presence of environmental natural radioactivity. A HPGe detector was used for the coincident spectrum as a main detector and a NaI(Tl) scintillation detector for gating purposes as an associated detector. For coincidence spectroscopy the whole energy spectrum of associated detector was used instead of gate signals. The coincident events obtained from the gating spectrum was evaluated by a coincidence computer program in this study instead of timing circuit. In this work, the background of detection environment was reduced to factor 100 and peaks to be determined was reduced to factor 30 using the coincidence gamma-ray spectroscopy.

• 전자공학회논문지D
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• 제34D권4호
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• pp.47-53
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• 1997

We fabricated gamma radiation detector using high resistive p-Cd$_{80}$Zn$_{20}$Te grown by high pressure bridgman method and forming au thin film electrode by chemically electroless deposition method. The device of Au/Cd$_{80}$Zn$_{20}$Te/Au is a typical MIM structure. The characteristic of current-voltage showed good linearity to 3kV/cm but it depend on the square of electric field over 3kV/cm. As the results of rutherford backscattering spectroscope(RBS) and auger spectroscope on the Au/Cd$_{80}$Zn$_{20}$Te, Au penetrated to the surface of Cd$_{80}$Zn$_{20}$Te detector absorbed slightly high energy radiation like a few hundred keV and showed good performance to detect low energy gamma ray.mma ray.

• Journal of Radiation Protection and Research
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• 제16권2호
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• pp.1-6
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• 1991

상온에서 사용할 수 있는 감마선 검출 소자로서 $HgI_2$ 소자의 응용성을 판단하기 위하여 기상 성장법으로 $HgI_2$ 단결정을 성장시켰고 이를 이용하여 검출 소자를 제작한 후 감마선 검출 특성을 조사하였다 성장된 단결정의 비저항과 전하 운반자 포획 밀도는 상온에서 각각 $10^{11}{\Omega}\;cm$와 $1.8{\times}10^{14}/cm^3$였으며 단결정의 Photoluminescence를 측정한 결과 성장된 $HgI_2$ 단결정의 밴드갭의 온도계수는 20K부터 77K에서 $-1.53{\times}10^{-4}eV/K$였다. 감마선 검출실험 결과 제작된 $HgI_2$ 검출 소자는 상온에서 우수한 계수 특성과 시간에 대한 선형적 축적 계수 특성을 나타내었으나 온도변화에 따라 계수의 특성의 변화는 심하였다.

• Nuclear Engineering and Technology
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• 제53권10호
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• pp.3431-3437
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• 2021

In this study, one-dimensional gamma ray source positions are estimated using a plastic scintillating optical fiber, two photon counters and via data processing with a machine learning algorithm. A nonlinear regression algorithm is used to construct a machine learning model for the position estimation of radioactive sources. The position estimation results of radioactive sources using machine learning are compared with the theoretical position estimation results based on the same measured data. Various tests at the source positions are conducted to determine the improvement in the accuracy of source position estimation. In addition, an evaluation is performed to compare the change in accuracy when varying the number of training datasets. The proposed one-dimensional gamma ray source position estimation system with plastic scintillating fiber using machine learning algorithm can be used as radioactive leakage scanners at disposal sites.

• 한국축산식품학회지
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• 제30권1호
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• pp.124-132
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• 2010

육가공 산업에서 원료로 이용되고 있는 향신료의 위생화를 위하여 대표적인 살균 기술인 감마선과 전자선의 조사효과를 비교하였다. 미생물 오염도를 측정한 결과 대부분의 시료에서 1.5 to 3.8 Log CFU/g의 일반호기성 미생물이 나타났으나, 강황 및 로즈마리에서는 미생물이 검출되지 않았다. 검출된 시료에서는 조사에 의해 효과적인 것으로 미생물이 감소하였으며, 감마선이 전자선보다 효과적으로 미생물을 사멸하였다. 검출된 미생물을 동정한 결과 Bacillus spp. 및 Staphylococcus spp.으로 확인하였다. B. cereus 및 S. aureus에 대한 방사선 감수성 측정 결과 0.19-0.63 kGy로 확인되었으며, 전자선 보다 감마선에 대한 내성이 약한 것으로 확인되었다. Ames test를 이용하여 방사선 조사에 의한 향신료의 유전독성학적 안전성을 평가한 결과, 조사에 의한 돌연변이원성은 관찰되지 않았다. 이상의 결과를 종합하여 볼 때, 향신료의 위생화를 위한 살균방법으로 방사선 조사기술이 효과적으로 판단되며, 감마선(>4 kGy, <6 kGy)이 전자선보다 효과적으로 미생물을 제어하는 것으로 나타났다.

• 전기전자학회논문지
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• 제21권4호
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• pp.408-411
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• 2017

본 논문에서는 중성자, 감마선, 엑스선 등의 방사선을 측정하는 통합 제어 시스템을 제안한다. 제안하는 시스템은 원격 또는 네트워크상으로 측정 및 분석한 데이터를 디스플레이를 통해 모니터링 및 제어할 수 있는 장비로서, 현장에 가지 않고도 시스템 각 구성 부분의 상태를 보고 변경하여 원격으로 감시 및 관리할 수 있다. 제안하는 시스템은 감마선/엑스선 센서부, 중성자 센서부, 주제어 임베디드 시스템부, 전용 디스플레이 장치 및 GUI부, 원격 UI부 등으로 구성된다. 감마선/엑스선 센서부는 NaI(Tl) Scintillation Detector를 사용하여 저준위의 감마선 및 엑스선을 측정한다. 중성자 센서부는 Proportional Counter Detector(저준위 중성자)와 Ion Chamber Type Detector(고준위 중성자)를 사용하여 중성자를 측정한다. 주제어 임베디드 시스템부는 방사선을 검출하여 초단위로 샘플링하고 누적된 펄스 및 전류값에 대한 방사선량으로 변환한다. 전용 디스플레이 장치 및 GUI부는 방사선 측정 결과와 변환된 방사선량 및 방사능량 측정 수치를 출력하고, 사용자에게 제어 조건 설정 및 검출부에 대한 캘리브레이션 기능을 제공한다. 원격 UI부는 측정된 값들을 취합, 저장하여 원격 감시 시스템에 전달한다. 제안된 시스템의 성능을 평가하기 위하여 공인시험기관에서 실험한 결과는 중성자 검출부는 ${\pm}8.2%$ 이하의 측정 불확도가 측정되었고, 감마선, 엑스선 검출부는 7.5%이하의 불확도가 측정되어 국제 표준인 ${\pm}15%$ 이하에서 정상동작 됨이 확인되었다.