• 제목/요약/키워드: Compton edge

검색결과 10건 처리시간 0.033초

저준위 토양시료를 이용한 콤프턴 연속체 억제의 측정 및 몬테카롤로 시뮬레이션 평가 (Measurement and Monte Carlo Simulation evaluation of a Compton Continuum Suppression with low level soil Sample)

  • 장은성;이효영
    • 한국방사선학회논문지
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    • 제12권2호
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    • pp.123-131
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    • 2018
  • 본 연구는 점 선원인 $^{60}Co$, $^{137}Cs$ 및 혼합부피선원을 이용하여 피크 대 컴프턴 비율, 연속체 배경 스펙트럼을 감소시키기 위해 저 에너지 peak부터 고 에너지 peak에서 측정된 측정치와 PENELOPE와 비교하였다. 또한, 저에너지 부근에서의 변화를 통해 후방산란, 컴프턴 단(compton edge)의 효율 변화를 PENELOPE와 비교하였다. 혼합부피 선원에서 나온 결과를 토양시료에 적용하여 억제와 비 억제(unsuppressed)모드에서 토양시료의 최소검출한계치가 얼마큼 감소하였는지 확인하고자 한다. $^{60}CO$(1,173 keV)의 저에너지 영역의 컴프턴 억제가 상당히 되었으며, $^{137}Cs$(661 keV) 피크에 대한 Compton edge의 RF는 2.8이다. 특히, $^{60}Co$ 선원은 1,173.2keV와 1,332.5 keV의 coincidence 감마선을 방출하므로 컴프턴 억제는 대략 21% 감소하였다. 60Co 선원에서 방출되는 1,173keV와 1,332keV의 compton edge의 RF는 3.2, 3.4였으며 피크대 컴프턴 edge비율은 8:1로 향상되었다. 그리고, PENELOPE와 비교했을 때 불확도는 2% 이내로 잘 일치하였다. Compton unsuppressed 모드에서 661 keV, 1,173 keV 및 1,332 keV의 MDA 값은 각각 0.535, 0.173 및 0.136Bq/kg이었으나, Compton suppressed 모드에서는 0.121, 0.00826 및 0.00728B/kg로 감소하였다. 따라서, Compton suppres sed는 배후방사능과 검출기 자체에 함유된 방사능을 줄일 수 있었다.

Characteristics of Plastic Scintillators Fabricated by a Polymerization Reaction

  • Lee, Cheol Ho;Son, Jaebum;Kim, Tae-Hoon;Kim, Yong Kyun
    • Nuclear Engineering and Technology
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    • 제49권3호
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    • pp.592-597
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    • 2017
  • Three plastic scintillators of 4.5 cm diameter and 2.5-cm length were fabricated for comparison with commercial plastic scintillators using polymerization of the styrene monomer 2.5-diphenyloxazole (PPO) and 1,4-bis benzene (POPOP). Their maximum emission wavelengths were determined at 426.06 nm, 426.06 nm, and 425.00 nm with a standard error of 0.2% using a Varian spectrophotometer (Agilent, Santa Clara, CA, USA). Compton edge spectra were measured using three gamma ray sources [i.e., cesium 137 ($^{137}Cs$), sodium 22 ($^{22}Na$), and cobalt 60 ($^{60}Co$)]. Energy was calibrated by analyzing the Compton edge spectra. The fabricated scintillators possessed more than 99.7% energy linearity. Light output was comparable to that of the BC-408 scintillator (Saint-Gobain, Paris, France). The fabricated scintillators showed a light output of approximately 59-64% of that of the BC-408 scintillator.

Development of an energy and efficiency calibration method for stilbene scintillators

  • Kim, Chanho;Kim, Jaehyo;Hong, Wooseong;Yeom, Jung-Yeol;Kim, Geehyun
    • Nuclear Engineering and Technology
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    • 제54권10호
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    • pp.3833-3840
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    • 2022
  • A method for calibrating the energy scale and detection efficiency of stilbene scintillators is presented herein. This method can be used to quantitatively analyze the Compton continuum of gamma-ray spectra obtained using such scintillators. First, channel-energy calibration was conducted by fitting a semi-empirical equation for the Compton continuum to the acquired energy spectrum and a new method to evaluate the intrinsic detection efficiency, called intrinsic Compton efficiency, of stilbene scintillators was proposed. The validity of this method was verified by changing experimental conditions such as the number of sources being measured simultaneously and the detector-source distance. According to the energy calibration, the standard error for the estimated Compton edge position was ±1.56 keV. The comparison of the intrinsic Compton efficiencies calculated from the single- and two-source spectra showed that the mean absolute difference and the mean absolute percentage difference are 0.031 %p and 0.557%, respectively, demonstrating reasonable accuracy of this method. The feasibility of the method was confirmed for an energy range of 0.5-1.5 MeV, showing that stilbene scintillators can be used to quantitatively analyze gamma rays in mixed-radiation fields.

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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이중 모드 컴프턴 카메라의 측면 흡수부 제작을 위한 신호처리회로 개발 (Development of Signal Processing Circuit for Side-absorber of Dual-mode Compton Camera)

  • 서희;박진형;박종훈;김영수;김찬형;이주한;이춘식
    • Journal of Radiation Protection and Research
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    • 제37권1호
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    • pp.16-24
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    • 2012
  • 본 연구에서는 이중 모드 컴프턴 카메라의 측면 흡수부 개발을 위해 CsI(Tl) 섬광체에 실리콘 광다이오드를 결합한 섬광 검출기를 제작하였고, 이를 위한 신호처리회로를 설계 및 제작하였다. 개발된 신호처리회로는 에너지를 결정하는 파트와 타이밍을 결정하는 파트로 구성되어 있으며, 트리거 신호를 발생시키기 위해 상승 에지 선별기 및 TTL-to-NIM 로직 변환기를 포함하도록 개발하였다. 검출기와 초단의 신호처리회로(front-end electronics, FEE)는 AC 커플링 구조로 구성하였다. FEE의 잡음 특성은 전체 시스템의 성능에 크게 기여하므로 설계 시 고려해야 할 몇 가지 조건들에 대해 논의하였다. 이후 제작된 감마선 검출 시스템의 에너지 분해능 및 시간 분해능을 결정하였다. 평가된 에너지 분해능은 662 keV 피크와 511 keV 피크에 대해서 각각 12.0% 및 15.6% FWHM이었다. 시간 분해능은 59.0 ns로 평가되었다. 본 연구를 통해 제작된 섬광 검출기 및 신호처리회로의 성능이 기대에 다소 미치지 못하므로 결론에서는 성능 향상을 위한 추가 연구 방향에 대해 논의하였다.

방사선 포털 모니터용 대용적 플라스틱 섬광체 내부 빛 수집 효율 평가 (Light Collection Efficiency of Large-volume Plastic Scintillator for Radiation Portal Monitor)

  • 이진형;김종범
    • 방사선산업학회지
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    • 제11권3호
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    • pp.157-165
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    • 2017
  • In this paper, we calculate the light photons collection efficiency of large-volume plastic scintillation detector mainly used for radiation portal monitor (RPM). A Monte Carlo light photon transport code, DETECT2000, were used to quantitatively evaluate light collection efficiency of plastic scintillation detector. DETECT2000 calculated the placement of light collection efficiency based on the energy spectrum. We calculated the light collection efficiency relative to the position of the energy spectrum that proportional to the placement of the source. The $850{\times}285{\times}65mm^3$ size of polyvinyl toluene (PVT) scintillator was used for measurements. Through DETECT2000 simulation, the light collection efficiency of $5{\times}5$ arrays were calculated and verification was performed by comparing with experimentally measured. And then, the corrected MCNP simulation by applying the light collection efficiency in $21{\times}13$ arrays was compared and analyzed. Comparing the Monte Carlo simulation with measured results, it shows an average difference of 10.1% in $5{\times}5$ arrays. Particularly, about twice of the difference was found in the edge of first column, which coupled with PMT. In whole $5{\times}5$ array, the overall ratio was the same except for the first column. And then comparing the energy spectra of the $21{\times}13$ array with and without the light collection efficiency, it shows a difference of 6.69% in Compton edge area. The DETECT2000 based light collection efficiency simulation showed well agreement with the point source experiment. And comparing with measured energy spectra, we could compare the differences according to whether or not the light collection efficiency was applied. As a results, it is possible to increase the accuracy and reliability of Monte Carlo simulation results by pre-calculating the light collection efficiency according to the PVT geometry by using the DETECT2000.

Explainable radionuclide identification algorithm based on the convolutional neural network and class activation mapping

  • Yu Wang;Qingxu Yao;Quanhu Zhang;He Zhang;Yunfeng Lu;Qimeng Fan;Nan Jiang;Wangtao Yu
    • Nuclear Engineering and Technology
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    • 제54권12호
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    • pp.4684-4692
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    • 2022
  • Radionuclide identification is an important part of the nuclear material identification system. The development of artificial intelligence and machine learning has made nuclide identification rapid and automatic. However, many methods directly use existing deep learning models to analyze the gamma-ray spectrum, which lacks interpretability for researchers. This study proposes an explainable radionuclide identification algorithm based on the convolutional neural network and class activation mapping. This method shows the area of interest of the neural network on the gamma-ray spectrum by generating a class activation map. We analyzed the class activation map of the gamma-ray spectrum of different types, different gross counts, and different signal-to-noise ratios. The results show that the convolutional neural network attempted to learn the relationship between the input gamma-ray spectrum and the nuclide type, and could identify the nuclide based on the photoelectric peak and Compton edge. Furthermore, the results explain why the neural network could identify gamma-ray spectra with low counts and low signal-to-noise ratios. Thus, the findings improve researchers' confidence in the ability of neural networks to identify nuclides and promote the application of artificial intelligence methods in the field of nuclide identification.

CdS/ZnS 양자점 기반 플라스틱 섬광체 제작 및 성능평가 (Fabrication and Evaluation of CdS/ZnS Quantum Dot Based Plastic Scintillator)

  • 민수정;강하라;이병채;서범경;정재학;노창현;홍상범
    • Korean Chemical Engineering Research
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    • 제59권3호
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    • pp.450-454
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    • 2021
  • 현재, 감마 핵종 분석은 주로 무기섬광체 또는 반도체 검출기를 활용하여 여러 분야에 사용되고 있다. 이러한 검출기는 분해능이 좋지만 크기가 제한적이며, 가공성이 낮고 경제성이 플라스틱 섬광체보다 낮다. 따라서, 나노물질인 양자점과 플라스틱섬광체의 장점을 이용하여 양자점 나노물질 기반 플라스틱 섬광체를 개발하였다. 가장 많이 활용되고 있는 Cd계열 물질인 CdS/ZnS 양자점을 플라스틱 매트릭스에 교반하여 제작하였으며, 이를 60Co핵종 대상 계측 실험을 하여 상용플라스틱 섬광체의 성능과 비교 분석하였다. 상용플라스틱 섬광체 대비 CdS/ZnS 양자점 기반 플라스틱 섬광체가 20~30% 높은 효율을 보였다. 이는 의료분야뿐만 아니라 원자력 해체분야에서도 방사능 분석기로 활용 가능할 것으로 판단된다.

Evaluation of Source Identification Method Based on Energy-Weighting Level with Portal Monitoring System Using Plastic Scintillator

  • Lee, Hyun Cheol;Koo, Bon Tack;Choi, Chang Il;Park, Chang Su;Kwon, Jeongwan;Kim, Hong-Suk;Chung, Heejun;Min, Chul Hee
    • Journal of Radiation Protection and Research
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    • 제45권3호
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    • pp.117-129
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    • 2020
  • Background: Radiation portal monitors (RPMs) involving plastic scintillators installed at the border inspection sites can detect illicit trafficking of radioactive sources in cargo containers within seconds. However, RPMs may generate false alarms because of the naturally occurring radioactive materials. To manage these false alarms, we previously suggested an energy-weighted algorithm that emphasizes the Compton-edge area as an outstanding peak. This study intends to evaluate the identification of radioactive sources using an improved energy-weighted algorithm. Materials and Methods: The algorithm was modified by increasing the energy weighting factor, and different peak combinations of the energy-weighted spectra were tested for source identification. A commercialized RPM system was used to measure the energy-weighted spectra. The RPM comprised two large plastic scintillators with dimensions of 174 × 29 × 7 ㎤ facing each other at a distance of 4.6 m. In addition, the in-house-fabricated signal processing boards were connected to collect the signal converted into a spectrum. Further, the spectra from eight radioactive sources, including special nuclear materials (SNMs), which were set in motion using a linear motion system (LMS) and a cargo truck, were estimated to identify the source identification rate. Results and Discussion: Each energy-weighted spectrum exhibited a specific peak location, although high statistical fluctuation errors could be observed in the spectrum with the increasing source speed. In particular, 137Cs and 60Co in motion were identified completely (100%) at speeds of 5 and 10 km/hr. Further, SNMs, which trigger the RPM alarm, were identified approximately 80% of the time at both the aforementioned speeds. Conclusion: Using the modified energy-weighted algorithm, several characteristics of the energy weighted spectra could be observed when the used sources were in motion and when the geometric efficiency was low. In particular, the discrimination between 60Co and 40K, which triggers false alarms at the primary inspection sites, can be improved using the proposed algorithm.