• Nuclear Engineering and Technology
• /
• 제39권4호
• /
• pp.349-358
• /
• 2007

A single-beam gamma densitometer is utilized to measure the average void fraction in a small diameter stainless steel pipe under critical flow conditions. A typical design of a single-beam gamma densitometer is composed of a sealed gammaray source, a collimator, a scintillation detector, and a data acquisition system that includes an amplifier and a single channel analyzer. It is operated in the count mode and can be calibrated with a test pipe and various types of phantoms made of polyethylene. A good average void fraction is obtained for a small diameter pipe with various flow regimes of the core, annular, stratified, and bubbly flows. Several factors influencing the performance of the gamma densitometer are examined, including the distance between the source and the detector, the measuring time, and the ambient temperature. The void fraction is measured during an adiabatic downward two-phase critical flow in a vertical pipe. The test pipe has an inner diameter of 10.9 mm and a thickness of 3.2 mm. The average void fraction was reasonably measured for a two-phase critical flow in the presence of nitrogen gas.

• 한국표면공학회지
• /
• 제56권1호
• /
• pp.84-93
• /
• 2023

The spent nuclear fuel is burned during the planned cycle in the plant and then generates elements such as actinide series, fission products, and plutonium with a long half-life. An 'interim storage' step is needed to manage the high radioactivity and heat emitted by nuclides until permanent-disposal. In the case of Korea, there is no space to dispose of high-level radioactive waste after use, so there is a need for a period of time using interim storage. Therefore, the intensity of neutrons and gamma-ray must be determined to ensure the integrity of spent nuclear fuel during interim storage. In particular, the most important thing in spent nuclear fuel is burnup evaluation, estimation of the source term of neutrons and gamma-ray is regarded as a reference measurement of the burnup evaluation. In this study, an analysis of spent nuclear fuel was conducted by setting up a virtual fuel burnup case based on CE16×16 fuel to check the total amount and spectrum of neutron, gamma radiation produced. The correlation between BU (burnup), IE (enrichment), and CT (cooling time) will be identified through spent nuclear fuel burnup calculation. In addition, the composition of nuclide inventory, actinide and fission products can be identified.

• 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.

• 한국방사선학회논문지
• /
• 제17권6호
• /
• pp.889-896
• /
• 2023

핵의학과에서 가장 많이 사용되는 ^99mTc를 점선원과 산란팬텀을 이용하여 에너지스펙트럼 변화를 분석하고 변화된 감마선 에너지에 따른 납 앞치마의 차폐효과를 평가하였다. 산란팬텀의 감마선 에너지 스펙트럼은 점선원보다 광전피크 영역은 감소하고 컴프턴 산란영역은 증가하였다. 감마선원 형태 변화에 따른 에너지 영역별 계수치는 점선원의 계수치보다 20 cm 거리에서 최대 66.1 %의 감소율을 보였으며 컴프턴 산란 영역에서는 산란팬텀의의 계수치가 점선원의 계수치보다 최대 40 cm 거리에서 122.2 % 증가하는 결과를 보였다. 감마카메라를 이용한 선원과 산란팬텀의 거리에 따른 차폐율 차이에서 광전피크 영역은 유사한 결과를 보였으나 컴프턴 산란영역에서는 20 cm거리에서 산란팬텀의 차폐율이 점선원의 차폐율보다 29.2% 증가하였으며 거리가 증가함에 따라 차폐율 차이는 감소하였다. 방사선 선량계를 이용한 납 앞치마 차폐율 측정에서 산란팬텀의 차폐율은 최대 15.3 %의 차이를 보였으며 거리가 증가할수록 두 선원의 차폐율 차이는 감소하였다. 산란팬텀의 납 앞치마 차폐율이 점선원보다 높고 선원과 가까운 거리일수록 납 앞치마의 효과는 증가하는 결과로 방사성의약품을 주입한 환자를 직접 대면할 때 납 앞치마의 착용은 방사선피폭 저감화에 도움이 될 것으로 판단된다.

• 한국정보통신학회:학술대회논문집
• /
• 한국정보통신학회 2017년도 추계학술대회
• /
• pp.705-707
• /
• 2017

스테레오기반의 공간방사선 탐지장치는 방사선원에 대한 공간분포정보 뿐만 아니라 탐지장치로부터 선원까지의 거리정보를 얻을 수 있어 기존 방사선 영상화 장치보다 선원에 대한 효율적인 정보를 제공한다. 또한 감마선원의 스펙트럼 및 종류에 대한 정보를 고속으로 제공하기 위해서는 감도가 높은 고감도 검출센서가 필요하며 고선량에서의 포화되는 현상을 해소할 수 있는 기법이 필요하다. 본 논문에서는 다종 감마선 공간분포 측정을 위해 고감도 센서를 구성하고, 검출모듈의 기능을 개선하여 고선량에서의 포화상태를 해소함으로써 단일센서로 탐지범위 증대를 위한 연구를 수행하였다. 본 논문의 결과는 향후 스테레오기반의 감마선 탐지장치의 성능개선을 위해 활용될 것이다.

• Nuclear Engineering and Technology
• /
• 제54권10호
• /
• pp.3795-3802
• /
• 2022

NaI(Tl) scintillation materials are considered to be one of many materials that are used exclusively for γ-ray detection and spectroscopy. The gamma-ray spectrometer is not an easy-to-use device, and the accuracy of the numerical values must be carefully checked based on the rules of the calibration technique. Therefore, accurate information about the detection system and its effectiveness is of greater importance. The purpose of this study is to estimate, using an analytical-numerical formula (ANF), the purely geometric solid angle, geometric efficiency, and total efficiency of a cylindrical NaI(Tl) γ-ray detector with a side-through hole. This type of detector is ideal for scanning fuel rods and pipelines, as well as for performing radio-immunoassays. The study included the calculation of the complex solid angle, in combination with the use of various points like gamma sources, located axially and non-axially inside the through detector side hole, which can be applied in a hypothetical method for calibrating the facility. An extended γ-ray energy range, the detector, source dimensions, "source-to-detector" geometry inside the side-through hole, path lengths of γ-quanta photons crossing the facility, besides the photon average path length inside the detector medium itself, were studied and considered. This study is very important for an expanded future article where the radioactive point source can be replaced by a volume source located inside the side-trough hole of the detector, or by a radioactive pipeline passing through the well. The results provide a good and useful approach to a new generation of detectors that can be used for low-level radiation that needs to be measured efficiently.

• 지질공학
• /
• 제25권2호
• /
• pp.281-290
• /
• 2015

남한 지역에서 수행된 검층밀도 자료를 수집하고 코어밀도 자료와 비교 분석하였다. 먼저 코어밀도와 검층밀도 자료의 비교로부터 검층밀도가 비이상적으로 낮은 현상이 얻어졌으며 이는 소선원 검층밀도 자료에서의 비이상적으로 낮은 밀도와 연관되어 있음이 밝혀졌다. 표준선원과 소선원 자료간의 큰 밀도 차이를 비롯하여 표준선원 검층밀도와 코어밀도 간의 상관성 비교에서 나타난 분포곡선의 형태, 평균값, 표준편차 등 모든 결과들이 소선원 밀도자료의 품질에 이상이 있음을 보였다. 소선원 밀도자료에서의 품질 이상은 검층밀도 결정에서 소선원 밀도검층기가 지니는 선원 특성과 연결되었으며 결론적으로 지금까지의 소선원 밀도자료는 정확성을 유지하기 위한 최소의 조건이 충족되지 못한 상태에서 얻어진 것으로 판단하였다. 끝으로 코어자료와 표준선원 자료를 사용하여 남한지역 주요 지층의 밀도 분포 특성이 결정되었다.

• 대한전기학회:학술대회논문집
• /
• 대한전기학회 1997년도 하계학술대회 논문집 E
• /
• pp.1752-1754
• /
• 1997

The Kaufman type ion beam source with focusing lens was prepared to measure $\gamma$-coefficient of MgO thin film. Initial discharge of the system was started with the discharge voltage of 25V, the cathode filament current of 5.5A at the constant magnetic field of 150G. The system shows the maximum ion current density of $120{\mu}A/cm^2$, energy dispersion of 200eV and beam divergence of $30^{\circ}$ under the condition of Ar gas pressure $2.5{\times}10^{-4}Torr$, the beam voltage of 500V, the discharge voltage of 90V, the accelerator voltage of -200V and the cathode filament current of 6.1A. When the focusing lens was installed onto the ion beam source, the spreadness diameter of ion beam was about 10mm.

• Nuclear Engineering and Technology
• /
• 제53권1호
• /
• pp.199-207
• /
• 2021

This paper deals with accurate image reconstruction of gamma camera using a coded-aperture mask based on pixel-type CsI(Tl) scintillator coupled with silicon photomultipliers (SiPMs) array. Coded-aperture imaging (CAI) system typically has a smaller effective viewing angle than Compton camera. Thus, if the position of the gamma source to be searched is out of the fully-coded field-of-view (FCFOV) region of the CAI system, artifacts can be generated when the image is reconstructed by using the conventional cross-correlation (CC) method. In this work, we propose an effective method for more accurate reconstruction in CAI considering the source distribution of partially-coded field-of-view (PCFOV) in the reconstruction in attempt to overcome this drawback. We employed an iterative algorithm based on compressed-sensing (CS) and compared the reconstruction quality with that of the CC algorithm. Both algorithms were implemented and performed a systematic Monte Carlo simulation to demonstrate the possiblilty of the proposed method. The reconstructed image qualities were quantitatively evaluated in sense of the root mean square error (RMSE) and the peak signal-to-noise ratio (PSNR). Our simulation results indicate that the proposed method provides more accurate location information of the simulated gamma source than the CC-based method.

• Nuclear Engineering and Technology
• /
• 제53권8호
• /
• pp.2640-2645
• /
• 2021

We report the development of a gamma-ray imaging device, named Large-Area Hybrid Gamma Imager (LAHGI), featuring high imaging sensitivity and good imaging resolution over a broad energy range. A hybrid collimation method, which combines mechanical and electronic collimation, is employed for a stable imaging performance based on large-area scintillation detectors for high imaging sensitivity. The system comprises two monolithic position-sensitive NaI(Tl) scintillation detectors with a crystal area of 27 × 27 cm² and a tungsten coded aperture mask with a modified uniformly redundant array (MURA) pattern. The performance of the system was evaluated under several source conditions. The system showed good imaging resolution (i.e., 6.0-8.9° FWHM) for the entire energy range of 59.5-1330 keV considered in the present study. It also showed very high imaging sensitivity, successfully imaging a 253 µCi ¹³⁷Cs source located 15 m away in 1 min; this performance is notable considering that the dose rate at the front surface of the system, due to the existence of the ¹³⁷Cs source, was only 0.003 µSv/h, which corresponds to ~3% of the background level.