• Journal of Radiation Protection and Research
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• 제41권2호
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• pp.93-99
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• 2016

Background: Industrial X-ray CT system is normally applied to non-destructive testing (NDT) for industrial product made from metal. Furthermore there are some special CT systems, which have an ability to inspect nuclear fuel assemblies or rocket motors, using high power and high energy (more than 6 MeV) pulsed X-ray source. In these case, pulsed X-ray are produced by the electron linear accelerator, and a huge number of photons with a wide energy spectrum are produced within a very short period. Consequently, it is difficult to measure the X-ray energy spectrum for such accelerator-based X-ray sources using simple spectrometry. Due to this difficulty, unexpected images and artifacts which lead to incorrect density information and dimensions of specimens cannot be avoided in CT images. For getting highly precise CT images, it is important to know the precise energy spectrum of emitted X-rays. Materials and Methods: In order to realize it we investigated a new approach utilizing the Bayesian estimation method combined with an attenuation curve measurement using step shaped attenuation material. This method was validated by precise measurement of energy spectrum from a 1 MeV electron accelerator. In this study, to extend the applicable X-ray energy range we tried to measure energy spectra of X-ray sources from 6 and 9 MeV linear accelerators by using the recently developed method. Results and Discussion: In this study, an attenuation curves are measured by using a step-shaped attenuation materials of aluminum and steel individually, and the each X-ray spectrum is reconstructed from the measured attenuation curve by the spectrum type Bayesian estimation method. Conclusion: The obtained result shows good agreement with simulated spectra, and the presently developed technique is adaptable for high energy X-ray source more than 6 MeV.

• 한국진공학회지
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• 제17권3호
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• pp.234-239
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• 2008

휴대용 XRF (X-Ray Fluorescence) 장치에 적용할 수 있는 40 kV용 투과 양극형 W-Target tube와 Rh-Target tube를 개발하고 특성을 조사하였다. 특성 x-ray의 에너지와 연속 x-ray의 선량특성은 알려진 결과와 잘 일치함을 확인하였고, 최대 선량을 추출하기 위한 양극금속 박막의 최적 두께는 W-target tube의 경우 약 $2.6{\mu}m$, Rh-target tube의 경우 약 $2.7{\mu}m$ 임을 밝혀내었다. 또한 관전압 40 kV, 관전류 $60{\mu}A$로 30분 동안 연속적으로 작동시켰을 때 양극에서의 온도는 $50^{\circ}C$를 넘지 않아 휴대용 XRF장치에 적용할 수 있음을 확인하였다.

• 한국의학물리학회지:의학물리
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• 제27권4호
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• pp.272-276
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• 2016

To investigate the optimum x-ray tube design for the dental radiology, factors affecting x-ray beam characteristics such as tungsten target thickness and anode angle were evaluated. Another goal of the study was to addresses the anode heel effect and off-axis spectra for different target angles. MCNPX has been utilized to simulate the diagnostic x-ray tube with the aim of predicting optimum target angle and angular distribution of x-ray intensity around the x-ray target. For simulation of x-ray spectra, MCNPX was run in photon and electron using default values for PHYS:P and PHYS:E cards to enable full electron and photon transport. The x-ray tube consists of an evacuated 1 mm alumina envelope containing a tungsten anode embedded in a copper part. The envelope is encased in lead shield with an opening window. MCNPX simulations were run for x-ray tube potentials of 70 kV. A monoenergetic electron source at the distance of 2 cm from the anode surface was considered. The electron beam diameter was 0.3 mm striking on the focal spot. In this work, the optimum thickness of tungsten target was $3{\mu}m$ for the 70 kV electron potential. To determine the angle with the highest photon intensity per initial electron striking on the target, the x-ray intensity per initial electron was calculated for different tungsten target angles. The optimum anode angle based only on x-ray beam flatness was 35 degree. It should be mentioned that there is a considerable trade-off between anode angle which determines the focal spot size and geometric penumbra. The optimized thickness of a target material was calculated to maximize the x-ray intensity produced from a tungsten target materials for a 70 keV electron energy. Our results also showed that the anode angle has an influencing effect on heel effect and beam intensity across the beam.

• Nuclear Engineering and Technology
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• 제52권11호
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• pp.2572-2580
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• 2020

Emerging gamma ray detection applications that utilize neutron-based interrogation result in the prompt emission of high-energy (>2 MeV) gamma-rays. Rapid imaging is enabled by scintillators that possess high density, high atomic number, and excellent energy resolution. In this paper, we evaluate the bright (50,000 photons/MeV) oxide scintillator, cerium-doped Gd₂Al₂Ga₃O₁₂ (GAGG(Ce)). A silicon photomultiplier (SiPM) array is coupled to a GAGG(Ce) scintillator array (12 × 12 pixels) and integrated into a coded-aperture based gamma-ray imaging system. A resistor-based symmetric charge division circuit was used reduce the multiplicity of the analog outputs from 144 to 4. The developed system exhibits 9.1%, 8.3%, and 8.0% FWHM energy resolutions at 511 keV, 662 keV, and 1173.2 keV, respectively. In addition, a pixel-identification resolution of 602 ㎛ FWHM was obtained from the GAGG(Ce) scintillator array.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2003년도 학술회의 논문집 정보 및 제어부문 B
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• pp.600-603
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• 2003

Energy spectrum modulation of X-ray source in digital mammography has been studied. In this study, we calculated various filtered spectra using the scattering data. Primary spectra were generated by Molybdenum (Mo) and Tungsten (W) targets. The materials of added filters are Molybdenum and Rhodium (Rh) for 40 kVp Mo. primary spectrum, the amounts of photons over whole energy ranges are attenuated to 0.43 with 0.03 mm Mo filter and 0.38 with 0.06 mm Mo filter while the photons of energy ranged from 17 keV to 20 keV. The photons of low energy ranged below 17 keV are considerably attenuated. This effect brings out reducing the scattered radiation and dose to the patient, and enhancing subject contrast in the image. The results show that filtered spectra are not seriously affected by X-ray tube loadability. Because the energy range from 17 keV to 20 keV is directly transmitted although low and high energies are mainly filtered.

• 방사성폐기물학회지
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• 제6권3호
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• pp.189-203
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• 2008

원전 부지에 저장중인 방사성폐기물을 처분장에 인도하기 전에 폐기물의 물리 화학적 특성이 인수기준에 적합한지를 검사해야 한다. 검사하는 방법 중 비파괴 검사방법에 대해 조사하였는데, 조사결과 X-ray를 이용한 비파괴 방법을 적용하면 인수검사 항목 중 '드럼내 내용물 검사', '유리수 및 채움율 정량검사'를 할 수 있는 것으로 나타났다. 본 논문에서는 먼저 X-ray 장비의 원리와 시스템 선정 시 고려해야 할 사항들에 대해 간략하게 살펴 본 후 X-ray 장비를 이용하여 검사해야 할 드럼들의 특성을 분석하였다. 분석한 특성들은 드럼의 종류, 드럼의 규격, 드럼내 내용물의 종류 등이었고 이들 특성자료를 이용하여 검사에 필요한 X-ray 소요에너지를 계산하였다. 계산 결과 드럼 크기가 320 l 이하인 드럼을 검사하기 위한 소요에너지는 3 MeV 이하로 나타났으며 경제성 및 실현가능성 측면에서 450 keV 장비와 3 MeV 장비를 조합하거나 단독으로 사용하는 것이 바람직하고 이 때 450 keV 장비를 이용하여 검사가 가능한 저밀도 드럼 수는 2006년 12월 저장기준으로 42,327 드럼, 3 MeV 장비를 이용하여 검사가 가능한 드럼 수는 18,105 드럼으로 나타났다. 검사를 수행하는 주체, 장비 구매 방안 등에 따라 4가지 검사 시나리오를 수립하고 이에 대해 경제성 및 적용 가능성을 분석한 결과 최적의 검사시나리오는 인수기준, 처리 및 처분장 인도에 대한 폐기물 발생자의 정책 등에 영향을 받는 것으로 나타났다. 예를 들어, '유리수', '채움율'에 대한 정량분석과 ‘내용물 확인’을 모두 해야 할 경우에는 밀도가 상대적으로 낮은 폐기물이 담겨있는 ‘저밀도 드럼’의 검사를 위해 450 keV 이동형 장비 2대를 구입하여 자체 검사하고 ‘고밀도 드럼’은 외주로 검사하는 것이 바람직할 수 있다. 반면‘내용물 확인’만을 비파괴 검사항목으로 할 경우에는 450 keV 급 이동형 장비 1대면 연간 13,000 드럼을 검사할 수 있는 것으로 나타났다.

• 한국안광학회지
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• 제11권4호
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• pp.311-315
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• 2006

플라스마 포커스장치에서 방사되는 전자기파 중에서 X선에 대한 특성을 조사하였다. X선 측정은 pin 포토다이오드와 0.5mm 핀홀카메라로 이루어졌으며, X선 이외의 전자기파를 차폐하기 위해 $25{\mu}m$ 베리륨박막을 사용하였다. X선 발생조건은 방전전압이 15kV이었고, 아르곤 기체압력은 0.12torr 이었다. X선 발생의 재현성이 조사되었고, 방사되는 X선의 온도는 3keV 이상이었다.

• 한국재료학회지
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• 제14권5호
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• pp.348-352
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• 2004

The mechanical alloying (MA) effect in immiscible V-Cu system with positive heat of mixing was studied by not only the neutron and X-ray diffraction but also the analysis of DSC spectra. The total energy, ΔHt accumulated during MA for the mixture of $V_{50}$ $Cu_{50}$ / powders increased with milling time and approached the saturation value of 14 kJ/mol after 120 h of milling. It can be seen that the free energy difference between the amorphous phase and the pure V and Cu powders with an atomic ratio 5:5 is estimated to be 11 kJ/mol by Miedema et al. This is thermodynamically taken as one of the evidences for the amorphization. The structural changes of V-Cu MA powders were characterized by the X-ray diffraction and neutron diffraction. We take a full advantage of a negligibly small scattering length of the V atom in the neutron diffraction measurement. The neutron diffraction data definitely indicate that the amorphization proceeds gradually but incompletely even after 120 h of MA and bcc-Cu Bragg peaks appears after 60 h of MA.

• 전력전자학회:학술대회논문집
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• 전력전자학회 2020년도 전력전자학술대회
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• pp.265-266
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• 2020

X-ray 발생장치는 주로 열전자생성을 위한 저압 발생장치과 열전자가속을 위한 고압전원 및 X-ray 튜브 등으로 이루어져 있다. 따라서 X-ray 발생장치에는 저압전원과 고압전원의 설계가 필수적이다. 저압전원의 경우 전압, 전류의 정격이 비교적 작기 때문에 구현이 상대적으로 용이하나 고압전원은 40~200kV까지의 고전압을 생성해야하기 때문에 일반적으로 인버터, 고압 변압기, 배압회로 등 단계를 거쳐서 생성되도록 설계된다. 이들의 설계 방식에 따라 고압전원의 특성이 결정되게 된다. 본 논문에서는 55kV 11mA급 X-ray 발생장치를 설계, 제작하고 성능에 대해 검증하였다.

• Nuclear Engineering and Technology
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• 제56권5호
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• pp.1830-1835
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• 2024

The current study aims to study the impacts of the substitution of magnesium with nickel concentrations on physical and γ-ray shielding capacity of magnesium alloys. The density of the magnesium alloys under study is varied from 3.677 g/cm³ to 5.652 g/cm³, with raising the nickel content from 26.7 wt% to 54.8 wt% and reducing the magnesium concentration from 72.6 wt% to 44.2 wt%, respectively. Additionally, the examination of the γ-ray shielding capacity using the Monte Carlo simulation code shows that the substitution of magnesium by nickel content in the magnesium alloys was associated with an enhancement in the γ-ray shielding capacity, where the linear attenuation coefficient for the studied alloys was enhanced by 53.22 %, 52.45 %, and 52.52 % at γ-ray energies of 0.662 MeV, 1.252 MeV, and 1.408 MeV, respectively, with raising the nickel concentration from 26.7 wt% to 54.8 wt%. Simultaneously, the half-value thickness for magnesium alloys was reduced from 2.47 cm to 1.62 cm (at gamma ray energy of 0.662 MeV), from 3.39 cm to 2.22 cm (at gamma ray energy of 1.252 MeV), and from 3.60 cm to 2.36 cm (at gamma ray energy of 1.408 MeV), raising the nickel concentration from 26.7 wt % to 54.8 wt%, respectively. The study shows that the substitution of magnesium for nickel greatly enhanced the radiation shielding capacity of the magnesium alloys.