• Journal of Radiation Protection and Research
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• 제25권1호
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• pp.3-9
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• 2000

한국원자력연구소에서는 사람의 폐에 침착된 방사성핵종의 in vivo 측정을 위해 사용되고 있는 Ge 검출기의 교정을 위해 LLNL 팬텀을 구입하였다. 제작사는 팬팀 위에서 phoswich 검출기의 위치설정을 돕기 위해 팬텀의 몸통덮개판과 이의 오버레이판 위에 동심원을 그려 놓았으며, 그리고 동심원내에서 측정된 팬텀의 가습벽유효두께를 제공하였다. 그러나 Ge 검출기의 면적이 phoswich 검출기보다 작기때문에 phoswich 검출기를 위한 동심원은 한국원자력연구소에서 사용중인 Ge 검출기에는 적합하지 않는 것으로 나타났다. 따라서 본 연구에서는 제작사에 의해 제공된 팬텀의 가슴벽 유효두께가 Ge 점출기에 적합한지, 새로운 자료가 교정에 사용되어야 하는지를 결정하기 위해 팬텀의 가슴벽유효두께를 재평가하였다 그결과 한국원자력연구소에서 새로 설정한 Ge 검출기영역과 phoswich 검출기영역에서의 가습벽유효두께는 다소 차이가 있는 것으로 나타났다.

• Nuclear Engineering and Technology
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• 제7권2호
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• pp.85-94
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• 1975

n형 Ge 결정체를 보상하기 위해 상온에서 $^{60}$Co 감마선으로 647 Mrad 조사하였다. 감마선으로 조사된 Ge 결정체로 Ge(${\gamma}$) 검출기를 제작하였다. Ge(${\gamma}$) 검출기의 검출기 특성은 얇은 Ge(Li) 검출기나 고순도 Ge 검출기와 비슷하였다. Ge(${\gamma}$) 검출기의 온도에 대한 안정도는 상온에서의 저장이 가능함을 보여 주었다.

• 방사성폐기물학회지
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• 제13권4호
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• pp.295-300
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• 2015

HPGe 검출기를 이용하여 밀도가 다양한 환경시료에 대한 정밀 분석시 정확한 분석을 위해서는 밀도보정인자가 필요하다. 밀도에 대한 보정인자를 구하기 위해서 본 연구에서는 몬테카를로 코드인 MCNPX 코드를 사용하여 크리스털의 높이, 지름 및 코어의 크기와 같은 특성이 다른 세 대의 p-type HPGe 검출기를 모사하고 밀도 $1g/m^3$의 교정용 표준시료를 이용하여 모델링을 검증하였다. 검증을 통하여 모델링을 확정한 후 0.3, 0.6, 0.9, 1.0, 1.2, $1.5g/m^3$ 밀도를 가진 샘플에 대한 효율을 시뮬레이션하고 밀도보정인자를 도출하였다. 도출된 각 검출기에 대한 밀도보정인자를 비교하였을 때 전 에너지 범위에서 그 차이가 거의 없음을 확인하였으며 이는 검출기의 크리스털과 같은 주요 특성에 대해 밀도보정인자가 독립적임을 의미한다.

• Nuclear Engineering and Technology
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• 제52권6호
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• pp.1282-1288
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• 2020

In the first study, the Radon emanation and radiological hazards associated with radionuclides in soil samples, collected from 9 various date palm farms located in 3 different districts in Saudi Arabia were determined through a high purity Germanium (HPGe) gamma-ray spectrometer. The estimated average values of Radon emanation coefficient and Radon mass exhalation rate for soil samples were 0.535 ± 0.016 and 50.063 ± 7.901 mBqkg^-1h^-1, respectively. The annual effective dose of radionuclides in all sampling locations was found to be lower than UNSCEAR's recommended level of 0.07 mSvy^-1 for soil in an outdoor environment. In the secondary study, gross α and gross β activities in soil and date palm pits samples were measured by a low background α/β counting system. Average values of gross α and gross β activities in soil and date palm pits samples were 5.761 ± 0.360 Bqkg^-1, 38.219 ± 8.619 Bqkg^-1 and 0.556 ± 0.142 Bqkg^-1, 24.266 ± 1.711 Bqkg^-1, respectively.

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

• Journal of Astronomy and Space Sciences
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• 제31권4호
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• pp.317-323
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• 2014

Odyssey, one of the NASA's Mars exploration program and SELENE (Kaguya), a Japanese lunar orbiting spacecraft have a payload of Gamma-Ray Spectrometer (GRS) for analyzing radioactive chemical elements of the atmosphere and the surface. In these days, gamma-ray spectroscopy with a High-Purity Germanium (HPGe) detector has been widely used for the activity measurements of natural radionuclides contained in the soil of the Earth. The energy spectra obtained by the HPGe detectors have been generally analyzed by means of the Window Analysis (WA) method. In this method, activity concentrations are determined by using the net counts of energy window around individual peaks. Meanwhile, an alternative method, the so-called Full Spectrum Analysis (FSA) method uses count numbers not only from full-absorption peaks but from the contributions of Compton scattering due to gamma-rays. Consequently, while it takes a substantial time to obtain a statistically significant result in the WA method, the FSA method requires a much shorter time to reach the same level of the statistical significance. This study shows the validation results of FSA method. We have compared the concentration of radioactivity of $^{40}K$, $^{232}Th$ and $^{238}U$ in the soil measured by the WA method and the FSA method, respectively. The gamma-ray spectrum of reference materials (RGU and RGTh, KCl) and soil samples were measured by the 120% HPGe detector with cosmic muon veto detector. According to the comparison result of activity concentrations between the FSA and the WA, we could conclude that FSA method is validated against the WA method. This study implies that the FSA method can be used in a harsh measurement environment, such as the gamma-ray measurement in the Moon, in which the level of statistical significance is usually required in a much shorter data acquisition time than the WA method.

• Journal of Radiation Protection and Research
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• 제42권2호
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• pp.83-90
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• 2017

Background: Different cases exist in the measurement of thyroid radiobioassays owing to the individual characteristics of the subjects, especially the potential variation in the counting efficiency. An In situ Object Counting System (ISOCS) was developed to perform an efficiency calibration based on the Monte Carlo calculation, as an alternative to conventional calibration methods. The purpose of this study is to evaluate the applicability of ISOCS to thyroid radiobioassays by comparison with a conventional thyroid monitoring system. Materials and Methods: The efficiency calibration of a portable high-purity germanium (HPGe) detector was performed using ISOCS software. In contrast, the conventional efficiency calibration, which needed a radioactive material, was applied to a scintillator-based thyroid monitor. Four radioiodine samples that contained $^{125}I$ and $^{131}I$ in both aqueous solution and gel forms were measured to evaluate radioactivity in the thyroid. ANSI/HPS N13.30 performance criteria, which included the relative bias, relative precision, and root-mean-squared error, were applied to evaluate the performance of the measurement system. Results and Discussion: The portable HPGe detector could measure both radioiodines with ISOCS but the thyroid monitor could not measure $^{125}I$ because of the limited energy resolution of the NaI(Tl) scintillator. The $^{131}I$ results from both detectors agreed to within 5% with the certified results. Moreover, the $^{125}I$ results from the portable HPGe detector agreed to within 10% with the certified results. All measurement results complied with the ANSI/HPS N13.30 performance criteria. Conclusion: The results of the intercomparison program indicated the feasibility of applying ISOCS software to direct thyroid radiobioassays. The portable HPGe detector with ISOCS software can provide the convenience of efficiency calibration and higher energy resolution for identifying photopeaks, compared with a conventional thyroid monitor with a NaI(Tl) scintillator. The application of ISOCS software in a radiation emergency can improve the response in terms of internal contamination monitoring.

• 한국방사선학회논문지
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• 제17권2호
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• pp.175-184
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• 2023

검출기의 실제 모양과 제조사에서 제공한 데이터를 기준으로 Penelope simulation을 통해 검출기 모양을 구현하며 측정치에서 얻은 효율을 기준으로 하여 적합한 사층 두께에 적용하였다. 검출기의 simulation 된 전체에너지피크 효율 채널수와 crystal의 Outside contact layer가 전체에너지피크 효율에 미치는 영향을 결정 하기위한 효율 계산은 Penelope Code를 사용하여 0.3, 0.5, 0.7, 1.0, 1.2 ,1.4 mm의 다양한 사층 두께에 대해 수행하였다. 외부 접촉 사층 두께가 5배 증가하였을 때, 59.50 keV의 경우 전체에너지피크 효율이 약 36% 감소하였으며, 1836.01 keV 경우 10% 감소하였다. 또한 10배 증가할수록 59.54 keV의 경우 FEP 효율이 약 20% 감소하였으며, 1836.01 keV 경우 7% 감소하였음을 확인하였다. Penelope simulation된 전체에너지피크 효율 채널은 사층 증가에 따라 기하급수적으로 감소한다. 또한, 총 효과 곡선은 0.3 - 1.4 mm 사층 두께 영역에서 3.5% 미만의 상대적 차이로 잘 일치함을 확인하였다. 그러나 비균질 사층이 몬테카를로 모델에서 여전히 매개변수라는 것을 알 수 있었다.