• 센서학회지
• /
• 제4권4호
• /
• pp.1-9
• /
• 1995

반지름이 1.25 cm인 구형 BGO 섬광 검출기의 감마선 검출 특성을 결정하기 위하여 감마선 에너지 deposition 스펙트럼을 Monte Calro법으로 계산하였다. 이때 계산에 이용된 감마선 에너지 deposition 스펙트럼 계산 code는 personal computer 에서 사용할 수 있도록 qbasic을 이용하여 작성하였다. 또한 직접 제작된 구형 BGO 섬광 검출기를 이용하여 방사성 선원 $^{22}Na$, $^{137}Cs$ 및 $^{207}Bi$ 의 감마선 에너지 스펙트럼도 측정하였다. 이 측정 감마선 에너지 스펙트럼의 광전 peak을 Gauss함수로 fitting하여, 광전 peak의 표준편차를 구하고, 이를 Nardi의 경험식을 이용하여 $X^{2}$ fitting하므로서 2000 keV이하의 감마선 에너지에서 구형 BGO 섬광 검출기의 분해능에 대한 에너지 의존성도 조사하였다. 이를 이용하여 에너지 deposition 계산 스펙트럼을 펼치므로서 $^{22}Na$ 및 $^{137}Cs$의 측정 에너지 스펙트럼과 비교하였다. 또한 감마선 에너지 deposition 스펙트럼 계산 code를 이용하여 반지름이 1.25 cm인 구형 BGO 검출기에 대한 절대효율과 고유 peak 효율도 계산하였다.

• Nuclear Engineering and Technology
• /
• 제54권11호
• /
• pp.4215-4219
• /
• 2022

The Cd_0.95Mn_0.05Te_0.98Se_0.02 (CMTS) ingot was grown by the vertical Bridgman technique at low pressure. All wafers showed high resistivity, which suggests potential as a room-temperature semiconductor detector. The resistivity of the CMTS planar detector was 1.47 × 10¹⁰ Ω·cm and mobility lifetime product of electrons was 1.29 × 10^-3 cm²/V. The spectroscopic property with Am-241 and Co-57 was evaluated. The energy resolution about 59.5 keV gamma-ray of Am-241 was 11% and the photo-peak of 122 keV gamma-ray from Co-57 was clearly distinguished. The result shows the first detector-grade CMTS in the world and proves CMTS's potential as a radiation detector operating at room temperature.

• Journal of Radiation Protection and Research
• /
• 제43권4호
• /
• pp.137-142
• /
• 2018

Background: Gamma-ray detectors having a thin window of a material with low atomic number can increase the true coincidence summing effects for radionuclides emitting X-rays or gamma-rays. This effect can make efficiency calibration or spectrum analysis more complicated. In this study, a Cu shield was tested as an X-ray filter to neglect the true coincidence summing effect by X-rays and gamma-rays in gamma-ray spectrometry, in order to simplify gamma-ray energy spectrum analysis. Materials and Methods: A Cu shield was designed and applied to an n-type high-purity germanium detector having an $X-{\gamma}$ summing effect during efficiency calibration. This was tested using a commercial, certified mixed gamma-ray source. The feasibility of a Cu shield was evaluated by comparing efficiency calibration results with and without the shield. Results and Discussion: In this study, the thickness of a Cu shield needed to avoid true coincidence summing effects due to $X-{\gamma}$ was tested and determined to be 1 mm, considering the detection efficiency desired for higher energy. As a result, the accuracy of the detection efficiency calibration was improved by more than 13% by reducing $X-{\gamma}$ summing. Conclusion: The $X-{\gamma}$ summing effect should be considered, along with ${\gamma}-{\gamma}$ summing, when a detection efficiency calibration is implemented and appropriate shielding material can be useful for simplifying analysis of the gamma-ray energy spectra.

• Nuclear Engineering and Technology
• /
• 제51권1호
• /
• pp.263-268
• /
• 2019

The $^3He$ proportional chamber is widely used for neutron measurement owing to its high neutron detection efficiency and simplicity for gamma-ray rejection. In general, the neutron and gamma-ray signals obtained from the $^3He$ proportional chamber can be easily separated by the difference in the pulse heights. However, for a high gamma-ray field, the gamma-ray signal cannot be precisely eliminated by the pulse height due to gamma-ray pulse pileup which causes the pulse height of gamma-ray pulse to increase and making the pulses due to neutrons and gamma rays indistinguishable. In this study, an improved algorithm for $n/{\gamma}$ discrimination using a parameter, which is the ratio of the rise time to the pulse height, is proposed. The $n/{\gamma}$ discrimination performance of the algorithm is evaluated by applying it to $^{252}Cf$ neutron signal separation from various gamma-ray exposure rate levels ranging 0.1-5 R/h. The performance is compared to that of the conventional pulse-height analysis method in terms of the gamma elimination ratio. The suggested algorithm shows better performance than the conventional one by 1.7% (at 0.1 R/h) to 70% (at 5 R/h) for gamma elimination.

• 한국정보통신학회:학술대회논문집
• /
• 한국정보통신학회 2014년도 추계학술대회
• /
• pp.835-836
• /
• 2014

감마선원의 정확한 위치탐지를 위해서 스테레오 감마선 탐지장치는 두 대의 탐지기를 이용하여 방사선 신호를 측정하고, 획득된 신호를 영상화 하여 선원에 대한 거리정보를 추출을 수행한다. 영상획득 시 영상의 분해능을 개선하기 위해서는 스테레오 탐지장치를 구성하는 Collimator에 대한 구조분석이 필요하다. 본 논문에서는 Collimator와 차폐체에 대한 연구자료를 바탕으로 입사구가 다른 Collimator를 제작하여 입사각도에 따른 선량별 영향을 분석하고 감마선 조사시험을 통한 결과 데이터를 이용하여 Collimator의 최적 구조에 대한 연구를 진행하였다. 수행 결과 입사각도를 약 $2^{\circ}$영역에서 최적의 결과를 나타내었다. 논문의 결과는 방사선 탐지를 위한 효율적인 검출기 구조를 설계를 위한 기초자료로 활용될 것이다.

• Nuclear Engineering and Technology
• /
• 제50권3호
• /
• pp.462-469
• /
• 2018

The background spectrum of a $3^{{\prime}{\prime}}{\times}3^{{\prime}{\prime}}$ NaI(Tl) well-type scintillation SILENA detector was measured without shielding, in 6 cm thick lead shielding, and with 2 mm thick electrolytic copper covering the detector inside the lead shielding. The relative remaining background of the lead shield lined with copper was found to be ideal for low-level environmental radioactive spectroscopy. The background total count rate in the (20-2160 KeV) was reduced 28.7 times by the lead and 29 times by the Cu + Pb shielding. The effective reduction of background (1.04) by the copper mainly appeared in the energy range from X-ray up to 500 KeV, while for the total energy range the ratio is 1.01 relative to the lead only. In addition, a strong relation between the full-energy peak absolute efficiency and the detector well height was found using gamma-ray isotropic radiation point sources placed inside the detector well. The full-energy peak efficiency at a midpoint of the well (at 2.5 cm) is three times greater than that on the detector surface. The energy calibrations and the resolution of any single energy line are independent of the locations of the gamma source inside or outside of the well.

• 방사성폐기물학회지
• /
• 제2권2호
• /
• pp.97-104
• /
• 2004

NIPS 시스템은 중성자 핵반응 결과 방출되는 즉발 감마선을 정량적으로 측정하는 장치이며 고체 및 액체 폐기물 중 존재하는 다양한 원소를 비파괴적으로 분석할 수 있는 장점이 있다. 본 연구에서는 NIPS 시스템에 이용된 고순도반도체 검출기의 계측효율을 $^{l33}$Ba 및 $^{152}$Eu 방사성 동위원소 선원과 $^{35}$ Cl(n, ${\gamma}$)$^{36}$ Cl 핵반응 시 발생되는 즉발감마선을 이용하여 80 keV에서 8 MeV까지 넓은 영역에 대하여 구하였다. $^{35}$ Cl(n, ${\gamma}$)$^{36}$ Cl 핵반응을 이용한 고에너지 감마선의 계측효율은 즉발감마선의 방사능 값을 정확히 알 수 없기 때문에 저 에너지 영역에서 정확히 알고 있는 검출기 효율곡선에 규격화시켜 전 에너지 영역에서의 효율보정곡선을 구하였다. 또한 KCl 표준용액에 $^{252}$ Cf 중성자 선원을 조사시켜 표준용액으로부터 방출되는 즉발 감마선을 고순도반도체 검출기로 측정하고 광대역 계측효율 곡선을 이용하여 수용액 시료에서의 평균 열중성자 속을 예측하였다. NIPS 측정시스템은 주변 재료 물질의 핵반응으로 방출되는 감마선 background를 줄이기 위해 두 개의 고순도반도체 검출기를 이용한 동시계수 장치가 고안되었으며, 동시계수 모드에서의 계측효율도 함께 고려되었으며, 표준선원을 이용하여 전 계수 또는 동시계수모드에서의 background에 대한 측정감도를 비교하였다.다.

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

• Nuclear Engineering and Technology
• /
• 제52권6호
• /
• pp.1271-1276
• /
• 2020

The geometrical efficiency of a source-to-detector configuration is considered to be necessary in the calculation of the full energy peak efficiency, especially for NaI(Tl) and HPGe gamma-ray spectroscopy detectors. The geometrical efficiency depends on the solid angle subtended by the radioactive sources and the detector surfaces. The present work is basically concerned to establish a new mathematical approach for calculating the solid angle and geometrical efficiency, based on conversion of the geometrical solid angle of a non-axial radioactive point source with respect to a circular surface of the detector to a new equivalent geometry. The equivalent geometry consists of an axial radioactive point source with respect to an arbitrary elliptical surface that lies between the radioactive point source and the circular surface of the detector. This expression was extended to include coaxial radioactive circular disk source. The results were compared with a number of published data to explain how significant this work is in the efficiency calibration procedure for the γ-ray detection systems, especially in case of using isotropic radiating γ-ray sources in the form of point and disk shapes.

• 한국환경과학회지
• /
• 제13권2호
• /
• pp.175-180
• /
• 2004

A prompt gamma-ray neutron activation (PGNA) system was simulated by the Monte Carlo N-Particle transport code (MCNP-4A) to estimate the level at which the scattered photon fluence rate, the absolute efficiency of the HPGe-detector, the volume of the concrete sample and the $^{35}$ /Cl(n, ${\gamma}$) reaction rate in this sample contribute to the count rate in the NaCl concentration measurement. The n- ${\gamma}$ fluence rates at the ST-2 beam tube exit of the HANARO reactor were used as input data, and the GAMMA-X type HPGe detector was modeled to tally 1.1649 MeV ${\gamma}$ -rays emitted from the $^{35}$ Cl(n, ${\gamma}$) reaction in the concrete sample. For three cylindrical concrete samples of 13.8, 46.8 and 157.1 ㎤ volumes, respectively, the relations between the NaCl weight fractions of 0.1, 1, 2 and 5 % in each of the concrete samples and the 1.1 649 MeV pulses created in the HPGe detector model were studied. As a result, it was found that the count rate at the same NaCl concentration nearly depends on the volume of the samples in a simulated condition of the same NaCl concentration samples, and that the linearities of the NaCl concentration calibration curves were reasonable in the narrow range of the NaCl weight fraction.