• 제목/요약/키워드: radiation detector

검색결과 842건 처리시간 0.028초

NaI(T1) 섬광검출기를 이용한 공기 및 수중에서의 감마선 에너지스펙트럼 분석 (An Analysis of ${\gamma}-ray$ Energy Spectra Using the NaI(T1) Scintillation Detector in the Air and Water)

  • 김은숙;박재우
    • Journal of Radiation Protection and Research
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    • 제21권4호
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    • pp.285-296
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    • 1996
  • NaI(T1) 섬광검출기를 이용하여 감마선원인 Cr-51, Cs-137, Mn-54, Zn-65에 대하여 공기와 깊이가 다른 수중에서 에너지스펙트럼을 조사하였다. 측정한 스펙트럼의 차이와 변화를 정량적으로 비교분석하기 위해서 측정 스펙트럼을 곡선근사할 수 있는 응답함수를 구성하였다. 본 연구에서 밝혀진 바에 의하면 구성된 응답함수는 공기 중 뿐만 아니라 수중에서 측정된 스펙트럼을 거의 완전하게 나타낼 수 있었다. 또한 응답함수에 사용된 계수들을 비교함으로써 공기와 수중에서-물의 깊이에 따른-스펙트럼의 특성 면화를 정량적으로 규정할 수 있었다. 응답함수의 계수 가운데 전에너지 봉우리의 높이 및 비율이 물의 깊이에 가장 민감하게 영향을 받았으며, 그 외에도 전에너지 봉우리의 퍼진 정도, flat continuum의 높이, 1차 콤프턴산란 연속의 높이, Compton edge의 모양을 나타내는 응답함수계수 등에서 미약하나마 물의 깊이에 따라 변화를 보였다.

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중성자 방사화법을 이용한 감마선원 제조 및 HPGe 검출기 효율 결정 (Manufacture of a Gamma-ray Source using the Neutron Activation and Determination of a HPGe Detector Efficiency)

  • 서범경;이길용;윤윤열;이근우
    • Journal of Radiation Protection and Research
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    • 제29권1호
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    • pp.17-23
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    • 2004
  • HPGe 검출기를 이용한 방사능 분석 시 효율교정을 위하여 통상적으로 사용하는 상용의 감마선 표준선원을 구입하는데 따르는 금전적인 문제와 장기간의 소요시간 등의 문제를 해결하기 위하여 본 연구에서는 표준선원을 직접 제작하였다. 측정하고자 하는 에너지 영역의 감마선을 방출하는 핵종이 포함된 시약을 원자로에서 조사시켜 방사화된 시약을 수용액 상태로 만들어 표준선원을 제조하였다. 제조한 방사선원을 상용의 표준선원과 비교하였으며 효율교정용 선원으로 사용할 수 있다는 것을 확인하였다. 또한 일상적인 방사능 분석과정에서 발생할 수 있는 표준선원과 측정 시료의 부피 차이에 따른 측정 효율의 변화정도를 조사하기 위하여 방사능 분석에서 사용되고 있는 다양한 측정용기에 대하여 표준선원의 부피 변화에 따른 효율의 변화 정도를 조사하였다.

FRAM을 이용한 우라늄 농축도 분석의 신뢰성 평가 연구 (Uranium Enrichment Analysis with Gamma-ray Spectroscopy)

  • 엄성호;정혜균;박준식;박세환;신희성
    • Journal of Radiation Protection and Research
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    • 제36권1호
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    • pp.16-23
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    • 2011
  • 보다 정확한 우라늄 농축도 분석은 핵물질 관리를 위하여 중요하다. 본 연구에서는 감마선을 이용한 우라늄 농축도 분석에서 시료와 검출기 사이에 차폐체가 있는 경우와 측정시간 변화에 따른 분석결과에 대한 정확성 평가 및 오차분석을 수행하였다. 우라늄 농축도를 분석하기 위하여 FRAM (Fixed energy Response function Analysis with Multiple efficiencies)을 이용하였다. FRAM에 의한 분석결과의 정확성은 화학 분석 결과와의 비교를 통해 평가되었다. 연구결과 선원과 검출기사이에 차폐체가 존재할 경우 차폐체의 두께변화에 따른 감마선의 세기는 지수함수 형태로 감소하며 감마선에너지 피이크의 반치폭 (FWHM : Full Width at Half Maximum)은 차폐체의 두께에 영향을 거의 받지 않는 것을 보였다. 따라서 시료와 검출기 사이에 차폐체가 있는 경우의 우라늄 농축도 분석에서 FRAM을 이용한 감마선분광 분석은 유용하게 활용될 수 있다. 본 연구 결과는 차폐체 안에 우라늄이 있는 경우 핵물질 분석에 기여할 수 있을 것이 기대된다.

a-Se에 첨가된 Iodine의 조성비 변화에 따른 X선 검출특성 연구 (The Study on X-ray Detection Characteristics of Radiation Detective Sensor with Changing Composition Ratio of Iodine in a-Se)

  • 차병열;강상식;이규홍;김재형;남상희
    • 한국전기전자재료학회:학술대회논문집
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    • 한국전기전자재료학회 2002년도 추계학술대회 논문집 Vol.15
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    • pp.399-402
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    • 2002
  • This paper is researched that electric characteristic of Digital x-ray radiography technique with changing composition ratio of Iodine. Dopant material, Iodine is evaporated with amorphous selenium. Thorugh the old papers say, doponted Iodine will be down the created trap level because of Arsenic dopant material in amorphous selenium. Arsenic material of Composition ratio in amorphous selenium is fixed with 0.3% and test sample is deposited composition of 30, 100, 300, 500, 700ppm with thermal evaporate system. Experimental measurement is performed by dark current and x-ray sensitivity in amorphous selenium based radition detector sensor. Fabricated test sample thickness is $30{\mu}m$ and injected voltage is $3{\mu}m$$6{\mu}m$$9{\mu}m$ to both electrode. Experimental results showed that the net charge of composition rate of 30ppm is 398.88 pc/mR/$cm^2$ very high. And increase of the Iodine composition ratio is tendency to the decrease of net charge. Doping changing composition of Iodine in amorphous selenium detector offered to basical information of amorphous selenium material.

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전 에너지 흡수 피크 분석용 GUI 기반 교육용 프로그램 개발 (A Development of GUI Full-Energy Absorption Peak Analysis Program for Educational Purpose)

  • 손종완;신명석;이혜정;정경수;정민수;김상년
    • Journal of Radiation Protection and Research
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    • 제34권2호
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    • pp.69-75
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    • 2009
  • 교육적 목적으로 감마선 검출기 계통의 특성에 대한 정보를 세밀하게 얻기 위하여, Delphi코드를 이용하여 전 에너지 흡수 피크 스펙트럼을 편리하게 분석할 수 있는 그래픽 사용자 인터페이스 방식의 컴퓨터 프로그램을 개발하였다. 피크는 4개의 비선형 모양함수를 사용하여 최소제곱법으로 적합하였다. 이들 4개의 비선형함수 속에 들어있는 12개의 계수값들을 사용자 인터페이스 화면에서 결정하는 과정을 상세히 서술하였다. 개발된 프로그램을 HPGe 검출기에서 측정된 1 $\mu$Ci 밀봉 점선원 $^{137)Cs$ 661KeV 감마선의 피크분석에 적용하여 계수값 탐색의 예를 예시하였다.

PET-MR 시스템에 적용을 위한 실리콘 광증배센서의 온도 변화에 따른 성능 열화 분석 (An Analysis on Performance Degradation of Silicon Photomultipliers over Temperatures Variation for PET-MR Application)

  • 박경진;김형택;임경택;조민식;김기윤;조규성
    • 방사선산업학회지
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    • 제9권3호
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    • pp.143-151
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    • 2015
  • A PET-MR system is particularly useful in diagnosing brain diseases. We have developed a prototype positron emission tomography (PET) system which can be inserted into the bore of a whole-body magnetic resonance imaging (MRI) system that enables us to obtain PET and MRI images simultaneously with a reduced cost. Silicon photomultipliers (SiPM) are appropriated as a PET detector at PET/MR system because detectors have a high gain and are insensitive to magnetic fields. Despite of its improved performance compared to that of PMT-based detectors, there is a problem of the photo-peak channel shift which is due to the increase of the temperature inside the ring detector. This problem will occur decreasing sensitivity of the PET and image distortion. In this paper, I quantitative analyze parameters of the KAIST SiPM depending on temperature by experiments. And I designed cooling methods in consideration of the degradation of sensors for correction of the temperature in the PET gantry. According to this research, we expect that distortive images and degradation of the sensitivity will not be occurred with using the above idea to reduce heat even if the PET system operates for a long time.

Pulse pileup correction method for gamma-ray spectroscopy in high radiation fields

  • Lee, Minju;Lee, Daehee;Ko, Eunbie;Park, Kyeongjin;Kim, Junhyuk;Ko, Kilyoung;Sharma, Manish;Cho, Gyuseong
    • Nuclear Engineering and Technology
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    • 제52권5호
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    • pp.1029-1035
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    • 2020
  • The detector suffers from pulse pileup by overlapping of the signals when it was used in high radiation fields. The pulse pileup deteriorates the energy spectrum and causes count losses due to random co-incidences, which might not resolve within the resolving time of the detection system. In this study, it is aimed to propose a new pulse pileup correction method. The proposed method is to correct the start point of the pileup pulse. The parameters are obtained from the fitted exponential curve using the peak point of the previous pulse and the start point of the pileup pulse. The amplitude at the corrected start point of the pileup pulse can be estimated by the peak time of the pileup pulse. The system is composed of a NaI (Tl) scintillation crystal, a photomultiplier tube, and an oscilloscope. A 61 μCi 137Cs check-source was placed at a distance of 3 cm, 5 cm, and 10 cm, respectively. The gamma energy spectra for the radioisotope of 137Cs were obtained to verify the proposed method. As a result, the correction of the pulse pileup through the proposed method shows a remarkable improvement of FWHM at 662 keV by 29, 39, and 7%, respectively.

Comparison of Machine Learning-Based Radioisotope Identifiers for Plastic Scintillation Detector

  • Jeon, Byoungil;Kim, Jongyul;Yu, Yonggyun;Moon, Myungkook
    • Journal of Radiation Protection and Research
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    • 제46권4호
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    • pp.204-212
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    • 2021
  • Background: Identification of radioisotopes for plastic scintillation detectors is challenging because their spectra have poor energy resolutions and lack photo peaks. To overcome this weakness, many researchers have conducted radioisotope identification studies using machine learning algorithms; however, the effect of data normalization on radioisotope identification has not been addressed yet. Furthermore, studies on machine learning-based radioisotope identifiers for plastic scintillation detectors are limited. Materials and Methods: In this study, machine learning-based radioisotope identifiers were implemented, and their performances according to data normalization methods were compared. Eight classes of radioisotopes consisting of combinations of 22Na, 60Co, and 137Cs, and the background, were defined. The training set was generated by the random sampling technique based on probabilistic density functions acquired by experiments and simulations, and test set was acquired by experiments. Support vector machine (SVM), artificial neural network (ANN), and convolutional neural network (CNN) were implemented as radioisotope identifiers with six data normalization methods, and trained using the generated training set. Results and Discussion: The implemented identifiers were evaluated by test sets acquired by experiments with and without gain shifts to confirm the robustness of the identifiers against the gain shift effect. Among the three machine learning-based radioisotope identifiers, prediction accuracy followed the order SVM > ANN > CNN, while the training time followed the order SVM > ANN > CNN. Conclusion: The prediction accuracy for the combined test sets was highest with the SVM. The CNN exhibited a minimum variation in prediction accuracy for each class, even though it had the lowest prediction accuracy for the combined test sets among three identifiers. The SVM exhibited the highest prediction accuracy for the combined test sets, and its training time was the shortest among three identifiers.

Radioisotope identification using sparse representation with dictionary learning approach for an environmental radiation monitoring system

  • Kim, Junhyeok;Lee, Daehee;Kim, Jinhwan;Kim, Giyoon;Hwang, Jisung;Kim, Wonku;Cho, Gyuseong
    • Nuclear Engineering and Technology
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    • 제54권3호
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    • pp.1037-1048
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    • 2022
  • A radioactive isotope identification algorithm is a prerequisite for a low-resolution scintillation detector applied to an unmanned radiation monitoring system. In this paper, a sparse representation with dictionary learning approach is proposed and applied to plastic gamma-ray spectra. Label-consistent K-SVD was used to learn a discriminative dictionary for the spectra corresponding to a mixture of four isotopes (133Ba, 22Na, 137Cs, and 60Co). A Monte Carlo simulation was employed to produce the simulated data as learning samples. Experimental measurement was conducted to obtain practical spectra. After determining the hyper parameters, two dictionaries tailored to the learning samples were tested by varying with the source position and the measurement time. They achieved average accuracies of 97.6% and 98.0% for all testing spectra. The average accuracy of each dictionary was above 96% for spectra measured over 2 s. They also showed acceptable performance when the spectra were artificially shifted. Thus, the proposed method could be useful for identifying radioisotopes in gamma-ray spectra from a plastic scintillation detector even when a dictionary is adapted to only simulated data. Furthermore, owing to the outstanding properties of sparse representation, the proposed approach can easily be built into an insitu monitoring system.

Gamma/neutron classification with SiPM CLYC detectors using frequency-domain analysis for embedded real-time applications

  • Ivan Rene Morales;Maria Liz Crespo;Mladen Bogovac;Andres Cicuttin;Kalliopi Kanaki;Sergio Carrato
    • Nuclear Engineering and Technology
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    • 제56권2호
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    • pp.745-752
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    • 2024
  • A method for gamma/neutron event classification based on frequency-domain analysis for mixed radiation environments is proposed. In contrast to the traditional charge comparison method for pulse-shape discrimination, which requires baseline removal and pulse alignment, our method does not need any preprocessing of the digitized data, apart from removing saturated traces in sporadic pile-up scenarios. It also features the identification of neutron events in the detector's full energy range with a single device, from thermal neutrons to fast neutrons, including low-energy pulses, and still provides a superior figure-of-merit for classification. The proposed frequency-domain analysis consists of computing the fast Fourier transform of a triggered trace and integrating it through a simplified version of the transform magnitude components that distinguish the neutron features from those of the gamma photons. Owing to this simplification, the proposed method may be easily ported to a real-time embedded deployment based on Field-Programmable Gate Arrays or Digital Signal Processors. We target an off-the-shelf detector based on a small CLYC (Cs2LiYCl6:Ce) crystal coupled to a silicon photomultiplier with an integrated bias and preamplifier, aiming at lightweight embedded mixed radiation monitors and dosimeter applications.