• Journal of Radiation Protection and Research
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• 제44권2호
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• pp.53-63
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• 2019

Background: As neutron fields are always accompanied by gamma rays, it is essential to distinguish neutrons from gamma rays in the detection of neutrons. Neutrons and gamma rays can be separated by pulse shape discrimination (PSD) methods. Recently, we performed characterization of a stilbene scintillator detector and an EJ-301 liquid scintillator detector with a high-speed digitizer DT5730 and investigated optimized PSD variables for both detectors. This study is for providing a basis for developing fast neutron/gamma-ray dual-particle imager. Materials and Methods: We conducted PSD experiments using stilbene scintillator and EJ-301 liquid scintillator and evaluated neutron and gamma ray discriminability of each PSD method with a $^{137}Cs$ gamma source and a $^{252}Cf$ neutron source. We implemented digital signal processing techniques to apply two PSD methods - the charge comparison (CC) method and the constant time discrimination (CTD) method - to distinguish neutrons from gamma rays. We tried to find optimized PSD variables giving the best discriminability in a given experimental condition. Results and Discussion: For the stilbene scintillator detector, the charge comparison method and the constant time discrimination method both delivered the PSD FOM values of 1.7. For the EJ-301 liquid scintillator detector, both PSD methods delivered the PSD FOM values of 1.79. With the same PSD variables, PSD performance was excellent in $300{\pm}100keVee$, $500{\pm}100keVee$, and $700{\pm}100keVee$ energy regions. This result shows that we can achieve an effective discrimination of neutrons from gamma rays using these scintillator detector systems. Conclusion: We applied both PSD methods to a stilbene and a liquid scintillator and optimized the PSD performance represented by FOM values. We observed a good separation performance of both scintillators combined with a high-speed digitizer and digital PSD. These results will provide reference values for the dual-particle imager we are developing, which can image both fast neutrons and gamma rays simultaneously.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.203-206
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• 2001

The mathematical processing (unfolding) of pulse height spectra from a scintillation detector helps to calculate the photon fluence rate energy distribution in a measured photon field. The data processing is based on the knowledge of detection system response function and directional dependence respectively. The experimental results of the photon fields measurements in the vicinity of the spent fuel temporary storage and inside the storage hall are presented. The containers Castor 440 are used for temporary storing of the burnt up fuel assemblies in the Czech nuclear power plant Dukovany. A set of periodical measurements was performed in order to get basic information on the time dependence of the photon fields spatial distributions and spectral characteristics in the temporary storage hall and its vicinity. The photon fields were measured by the scintillation system. The obtained photon fields spatial distributions and spectral characteristics present the information on the radiation hazard in the storage.

• Nuclear Engineering and Technology
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• 제50권5호
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• pp.690-697
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• 2018

Criticality alarm systems (CASs) are mandatory in nuclear plants for prompt alarm in the event of any criticality incident. False criticality alarms are not desirable as they create a panic environment for radiation workers. The present article describes the design enhancement of the CAS at each stage and provides maximum availability, preventing false criticality alarms. The failure mode and effect analysis are carried out on each element of a CAS. Based on the analysis, additional hardware circuits are developed for early fault detection. Two different methods are developed, one method for channel loop functionality test and another method for dose alarm test using electronic transient pulse. The design enhancement made for the external systems that are integrated with a CAS includes the power supply, criticality evacuation hooter circuit, radiation data acquisition system along with selection of different soft alarm set points, and centralized electronic test facility. The CAS incorporating all improvements are assembled, installed, tested, and validated along with rigorous surveillance procedures in a nuclear plant for a period of 18,000 h.

• 한국광학회지
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• 제16권6호
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• pp.553-559
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• 2005

(110) ZnTe 결정을 사용한 광정류(Optical Rectification)법에 의한 테라헤르츠파의 발생과 자유공간 전광 샘플링(Free-Space Electro-Optic Sampling; FS-EOS)법에 의한 테라헤르츠파의 검출특성에 대해서 보고한다. ZnTe 결정에 펌프용 레이저광에 대한 반사방지막 코팅을 실시함으로서 테라헤르츠파 신호크기가 $27\%$ 증가함을 알 수 있었다. ZnTe 결정의 두께가 얇을수록 테라헤르츠파의 신호의 크기는 작으나 광대역의 주파수를 가진 스펙트럼이 얻어졌다. 또한 레이저광의 편광방향과 ZnTe 결정의 (001)축사이의 각도에 따른 테라헤르츠파의 신호 변화, 펌프광 출력에 따른 테라헤르츠파의 신호크기 변화 등에 대한 특성이 조사되었다.

• Nuclear Engineering and Technology
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• 제41권5호
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• pp.723-728
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• 2009

The response property of the CZT detector ($5{\times}5{\times}5\;mm^3$), widely used in photon spectroscopy, was evaluated by considering the charge collection efficiency, which depends on the interaction position of incident radiation, A quantitative analysis of the energy spectra obtained from the CZT detector was also performed to investigate the tail effect at the low energy side of the full energy peak. The collection efficiency of electrons and holes to the two electrodes (i.e., cathode and anode) was calculated from the Hecht equation, and radiation transport analysis was performed by two Monte Carlo codes, Geant4 and MCNPX. The radiation source was assumed to be 59.5 keV gamma rays emitted from a $^{241}Am$ source into the cathode surface of this detector, and the detector was assumed to be biased to 500 V between the two electrodes. Through the comparison of the results between the Geant4 calculation considering the charge collection efficiency and the ideal case from MCNPX, an pronounced difference of 4 keV was found in the full energy peak position. The tail effect at the low energy side of the full energy peak was confirmed to be caused by the collection efficiency of electrons and holes. In more detail, it was shown that the tail height caused by the charge collection efficiency went up to 1000 times the pulse height in the same energy bin at the calculation without considering the charge collection efficiency. It is, therefore, apparent that research considering the charge collection efficiency is necessary in order to properly analyze the characteristics of CZT detectors.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2004년도 추계학술대회
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• pp.1140-1145
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• 2004

Laser-induced incandescence (LII) is introduced as a valuable tool for the characterization of nanoparticles in flame environments. This technique is based on the heating of the particles by a short laser pulse and the subsequent detection of the thermal radiation. It has been applied successfully for the investigation of soot in different fields of application. The evaluation of the temporal decay of the laser-induced incandescence (LII) signal from soot particles is introduced as a technique to obtain two-dimensional distributions of particle sizes and is applied to a laminar diffusion flame. This novel approach to soot sizing exhibits several theoretical and technical advantages compared with the established combination of elastic scattering and LII, especially as it yields absolute sizes of primary particles without requiring calibration. With this technique a spatially resolved 2-D measurement of soot primary particle sizes is feasible in a combination process form the ratio of emission signals obtained at two delay times after a laser pulse, as the cooling behavior is characteristic of particle size.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1999년도 하계학술대회 논문집 E
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• pp.2063-2065
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• 1999

PD pulses have about one nanosecond rise time in the $SF_6$ gas insulation. These pulses propagate through GIS chamber to PD sensors in the form of the electromagnetic radiation. In this paper, we investigated the characteristics of disc sensors and monopole antenna, by putting high frequency signals into the test cell in $SF_6$ gas by means of a Ins rise time pulse generator and 60Hz power supply respectively. Also, we measured PD quantity from the needle electrode and the location effect of output terminal beneath the disk sensors.

• 한국방사선학회논문지
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• 제13권6호
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• pp.847-856
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• 2019

오늘날 경제의 발전과 함께 여러 가지 환경 문제가 발생했다. 자연스레 사람들은 환경에 대한 관심이 높아졌으며 특히 식수에 대한 안전성과 오염도 조사에 대한 중요성이 부각되고 있다. 우리나라 국민들이 식수로 이용하는 지하수에서 우라늄 및 ²²²Rn 이 다수 지역에서 검출되고 있다. 따라서 이 연구는 지하수 내포함된 ²²²Rn 농도를 측정하는데 보다 정확한 측정을 위한 방법을 알아보고자 한다. 실험은 알파, 베타 펄스의 분석이 용이한 펄스파형분석 기능을 가진 저 준위 액체섬광계수기를 이용하여 실험하였다. 지하수 시료와 혼합하는 섬광체의 조제, 유효기간은 시간이 지날수록 검출값은 낮아지고, 에너지 스펙트럼도 낮은 쪽으로 channel 이동이 있었다. 섬광체의 구입시기가 오래 될수록, 개봉한 후 방치시간이 지날수록 검출값이 낮아짐을 확인했다. 사용목적이 다른 섬광체를 사용했을 경우 channel 이동으로 에너지를 확인할 수 있다.

• Nuclear Engineering and Technology
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• 제55권8호
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• pp.2797-2801
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• 2023

CdZnTeSe (CZTS) has attracted attention for applications in X- and gamma-ray detectors owing to its improved properties compared to those of CdZnTe (CZT). In this study, we grew and processed single crystals of CZT and CZTS using the Bridgeman method to confirm the feasibility of using a dosimeter for high-energy X-rays in radiotherapy. We evaluated their linearity and precision using the coefficient of determination (R²) and relative standard deviation (RSD). CZTS showed sufficient RSD values lower than 1.5% of the standard for X-ray dosimetry, whereas CZT's RSD values increased dramatically under some conditions. CZTS exhibited an R² value of 0.9968 at 500 V/cm, whereas CZT has an R² value of 0.9373 under the same conditions. The X-ray response of CZTS maintains its pulse shape at various dose rates, and its properties are improved by adding selenium to the CdTe matrix to lower the defect density and sub-grain boundaries. Thus, we validated that CZTS shows a better response than CZT to high-energy X-rays used for radiotherapy. Further, the applicability of an onboard imager, a high-energy X-ray (>6 MV) image, is presented. The proposed methodology and results can guide future advances in X-ray dose detection.

• 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.