• Journal of Ocean Engineering and Technology
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• v.19 no.2 s.63
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• pp.40-46
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• 2005

In order to consider the statistical properties of probability variables which are used in structural analysis, the conventional approach of using safety factors based on past experience, are usually used to estimate the safety of a structure. The real structures could only be analyzed with the error in estimation of loads, materials and dimensional characteristics. Errors should be considered systematically in the structural analysis. In this paper, we estimated the probability of failure of two pressure vessels, simultaneously, using computational analysis. One pressure vessel, theoretically, had no stiffener whereas the other had. This paper also discusses sensitivity values of random variables in the rounded parts of the pressure vessel which had ring-style stiffener in the center of the external area which had ring-style stiffener. Finally, we show that the reliability index, and the probability of failure, can be calculated to particular tolerance limits.

• Proceedings of the Korean Vacuum Society Conference
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• 2011.02a
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• pp.278-278
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• 2011

LCD 생산에 적용할 수 있는 대형 마그네트론 스퍼터 장비에서 공간적으로 불균일한 타겟 침식은 타겟의 사용 효율을 떨어뜨린다. 특히 직사각형의 외부 자석과 직선형태의 내부 자석 구조를 가진 마그네트론 스퍼터에서는 cross-corner 효과로 인해 국부적으로 일정 부분에 대한 상대적으로 높은 침식률이 문제가 된다. 이러한 문제를 해결하기 위해 국부적으로 자기장 세기를 바꾸는 시행착오를 통하여 실험적으로 문제를 해결하려는 방법이 있지만 비용 및 시간이 매우 많이 들어 전산모사를 통한 문제 해결 방법이 훨씬 유리하다. 우리는 몬테 카를로 방법에 기반한 3차원 입자 시뮬레이션을 통하여 마그네트론 스퍼터 장비를 모델링을 하였다. 직사각형의 외부와 직선형의 내부 자석 구조가 만들어 내는 정적인 공간 자기장의 분포는 OPERA3D를 이용하여 계산하였고, 플라즈마 입자들이 만들어내는 자기장에 의해 섭동영향을 받지 않는다고 가정하였다. 플라즈마 전기장 및 전하의 운동은 상호작용의 일관성이 유지되도록 계산하였다. 이온밀도의 공간분포는 내부 자석과 외부 자석 사이의 직선 부분 보다 cross-corner 효과가 일어나는 부분에서 상대적으로 더 높은 밀도분포를 보였다. 플라즈마 시뮬레이션을 통하여 얻은 타겟에 입사한 이온의 개수 및 속도에 대한 정보를 이용하여 타겟의 침식률을 계산하였다. 이러한 침식률을 계산하기 위한 시뮬레이션 기술은 산업용 대형 스퍼터 장비 연구 및 개발에 매우 효율적인 방법이 될 것이다.

• Progress in Medical Physics
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• v.24 no.4
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• pp.253-258
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• 2013

The purpose of this study is to evaluate and analyze the relationship between the external radiation dose reconstruction which is transmitted from the patient who receives radiation treatment through electronic portal imaging device (EPID) and the internal dose derived from the Monte Carlo simulation. As a comparative analysis of the two cases, it is performed to provide a basic indicator for similar studies. The geometric information of the experiment and that of the radiation source were entered into Monte Carlo n-particle (MCNPX) which is the computer simulation tool and to derive the EPID images, a tally card in MCNPX was used for visualizing and the imaging of the dose information. We set to source to surface distance (SSD) 100 cm for internal measurement and EPID. And the water phantom was set to be 100 cm of the source to surface distance (SSD) for the internal measurement and EPID was set to 90 cm of SSD which is 10 cm below. The internal dose was collected from the water phantom by using mesh tally function in MCNPX, accumulated dose data was acquired by four-portal beam exposures. At the same time, after getting the dose which had been passed through water phantom, dose reconstruction was performed using back-projection method. In order to analyze about two cases, we compared the penetrated dose by calibration of itself with the absorbed one. We also evaluated the reconstructed dose using EPID and partially accumulated (overlapped) dose in water phantom by four-portal beam exposures. The sum dose data of two cases were calculated as each 3.4580 MeV/g (absorbed dose in water) and 3.4354 MeV/g (EPID reconstruction). The result of sum dose match from two cases shows good agreement with 0.6536% dose error.

• Journal of the Korean Society of Radiology
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• v.15 no.5
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• pp.741-748
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• 2021

In this study, we evaluated image quality by changing collimator length and detector thickness using the Geant4 Application for Tomographic Emission (GATE) simulation tool. The gamma camera based on the Cadimium Zinc Telluride (CZT) and NaI detectors is modeled. In addition the images were acquired by setting 1, 2, 3, 4, 5, and 6 cm collimator length and 1, 3, 5, and 7 mm detector thickness using point source and phantom, which is designed by each diameter (4.45, 3.80, 3.15, 2.55 mm) with 447, 382, 317, and 256 Bq. The sensitivity (cps/MBq) for point source, and signal to noise ratio (SNR) and profile for phantom at the 4.45 mm by drwan the region of interests were used for quantitative analysis. Based on the results, the sensitivity according to collimator length is 2.3 ~ 48.6 cps/MBq for CZT detector, and 1.8 ~ 43.9 cps/MBq for NaI detector. The SNR using phantom is 3.6~9.8 for CZT detector, and 2.9~9.5 for NaI detector. As the collimator length is increased, the image resolution is also improved according to profile results based on the CZT and NaI detector. In addition, the senistivity for detector thickness is 0.04 ~ 0.12 cps/MBq for CZT detector, and 0.03 ~ 0.11 cps/MBq. The SNR using phnatom is 7.3~9.8 count for CZT detector, and 5.9~9.5 for NaI detector. As the detector thickness is increased, the image resolution is decreased according to profile results based on the CZT and NaI detector due to scatter ray. In conclusion, we need to set the geometric material such as detector and collimator to acuquire suitable image quality in nuclear medicine.