• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.11a
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• pp.153-162
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• 2005

In this Paper, sets of engineering analyses were conducted to renew the overall dimensions and configurations of a disposal container proposed as a prototype in the previous study. Such efforts and calculation results can provide new design variables such as the inner basket array type and thickness of the outer shell and the lid & bottom of a spent nuclear fuel disposal container. These efforts include radiation shielding and nuclear criticality analyses to check to see whether the dimensions of the container proposed from the mechanical structural analyses can provide a nuclear safety or not. According to the results of the structural analysis of a PWR disposal container by varying the diameter of the container insert, the Maximum Von Mises stress from the 102 cm container meets the safety factor of 2.0 for both extreme and normal load conditions. This container also satisfies the nuclear criticality and radiation safety limits. This decrease in the diameter results in a weight loss of a container by ${\~}$20 tons.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.25 no.1
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• pp.37-49
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• 2012

A structural model of the SNF(spent nuclear fuel) disposal canister for the PWR(pressurized water reactor) for about 10,000 years long term deposition at a 500m deep granitic bedrock repository has been developed through various structural safety evaluations. The SNF disposal baskets of this canister model have the array type whose four square cross section baskets stand parallel to each other and symmetrically with respect to the center of the canister section. However, whether this developed structural model of the SNF disposal canister is optimal is not determinable yet. Especially, there is still a problem in weight-reduction of the canister. The cross section shape of the SNF basket should be changed to solve this problem. There are two ways in changing the cross section shape of the SNF basket; the one is to rotate the cross section itself and the other is to change the cross section shape as other shape different from the square cross section. The previous study shows that the canister with $30{\sim}35^{\circ}$ rotated basket array is structurally more stable than the canister with un-rotated parallel basket array. However, whether this canister with rotated basket array is optimal is not either determinable as yet, because it is not revealed that the canister with other cross section different from the square cross section is structurally more stable than other canisters. Therefore, the structural analysis of the SNF disposal canister with other cross section shape which is also symmetric with respect to the canister center planes is very necessary. The structural analysis of the canister with various cross section shape basket array in which each basket is arrayed symmetrically with respect to the center planes is carried out in this paper. The structural analysis result shows that the SNF disposal canister with circular cross section shape baskets located symmetrically with respect to the center of the canister section is structurally more stable than the previously developed SNF disposal canister with the parallel basket array.

• Proceedings of the Korean Vacuum Society Conference
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• 2016.02a
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• pp.425.1-425.1
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• 2016

고온의 플라즈마를 긴 펄스 및 장시간 연속운전 유지기술 개발 및 연구를 위해서는 플라즈마는 더욱 가열되어야 하고, 고온 고밀도의 플즈마 상태를 유지시켜야 한다. 이러한 고성능 플라즈마 개발은 향후 핵융합 에너지의 상용화를 위한 절대필수적 기반기술이다. 현재 KSTAR 토카막에서는 플라즈마를 가열하기 위한 장치들 중 하나로서, 출력 6 MW 급의 중성입자빔을 입사하는 NBI (Neutral Beam Injection) 가열장치가 설치 운영 중에 있다. 이 NBI 가열장치는 진공환경에서 고온, 고압, 고전압 방전 및 수냉 등이 작동 및 운전되고 있기 때문에, 구성 부품 들의 미세한 구조적 결함에도 장치의 치명적 failed로 이어질 수 있다. 이번 연구에서는 NBI 가열장치의 특성상 극한 운전 환경에 있는 진공용기 부품 중 하나 인 빔인출을 위한 가속 그리드 (accelerating grid)의 구조적 손상및 결함 여부를 고속중성자 이미지 기법을 적용하여 내부를 투시 진단하였다. 가속 그리드는 copper로 제작되었고, 빔인출을 위한 원형의 구멍과 냉각관을 가진 평면판 형태로 되었다. 본 연구에서 내부투시 및 진단할 수 있는 고속중성자 이미징 기법의 적용으로 진공용기 부품 및 장치의 구조적 결함 및 손상 여부를 판단 가능하다는 연구 결과를 얻었다.

• Journal of radiological science and technology
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• v.40 no.1
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• pp.19-25
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• 2017

The aim of this study was to evaluate Magnetic Resonance Imaging safety by measuring the translational attraction, torque and susceptibility artifact for Bone-Anchored Hearing Aid (BAHA) implant at 1.5 T and 3.0 T MRI by standard criteria. In vitro assessment tools were made of acrylic-resin by American Society for Testing and Materials (ASTM) F2052-06 and F2119-07 standard. Translational attraction of BAHA implant was measured by the maximum deflection angle at 96 cm position, where the magnetically induced deflection was the greatest. The torque was assessed by the qualitative criteria of evaluating the alignment and rotation pattern, when the BAHA implant was positioned on a line with $45^{\circ}$ intervals inside the circular container in the center of the bore. The susceptibility artifact images were obtained using the hanged test tool, which was filled with $CuSO_4$ solution. And then the artifact size was measured using Susceptibility A rtifact Measurement (SA M) software. In results, the translational attraction was 0 mm at both 1.5 T and 3.0 T and the torque was 0(no torque) at 1.5 T, and +1(mild torque) at 3.0 T. The size of susceptibility artifacts was between 13.20 mm and 38.91 mm. Therefore, The BAHA implant was safe for the patient in clinical MR environment.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.20 no.5
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• pp.551-556
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• 2007

High pressure storage of the agent gas in fire suppression system was composed of tank, main valve and safety valve, which prevents the fracture of the high pressure storage. The safety valve has circular thin plate as fracture plate that was destroyed over fracture pressure. When inner pressure of the storage is reached the fracture pressure, the safety valve discharges gas and degrades simultaneously the inner pressure of the storage. There are design variables such as flow path diameter, inner diameter of the plastic packing ring, thickness of plate and fillet radius. In this variables, thickness of plate is set to be a value of 0.2mm. The main effect of variables on the inner pressure, has been decided using factorial design and statistical analysis. Therefore, the relation of variables are expressed by regression equation. It is disclosed results that the difference of fracture pressures between the equation and experiment has $2{\sim}5%$. Finally, using response surface method, the optimal design of the safety valve could be decided with safety pressure of 25MPa, where the fracture occurs on circular thin plate.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.36 no.3
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• pp.269-276
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• 2012

An air core is generated during draining through an axisymmetrically placed circular orifice after rotating a cylindrical tank filled with a liquid. If an air core is generated, the draining flow rate decreases and the draining time increases. In this study, the process of the formation of the air core and internal flow characteristics in a cylindrical tank are studied by numerical methods. Several methods are used in the analysis, and the results are compared with experimental results to obtain the appropriate scheme. Axial, radial, and swirl velocity profiles on a variety of heights are shown graphically, and the internal flow structure is analyzed from the velocity profiles, the vector plot, and the stream function distribution.

• Journal of IKEEE
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• v.25 no.3
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• pp.493-500
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• 2021

In this paper, we propose the development of deep learning structure to improve quality of polygonal containers. The deep learning structure consists of a convolution layer, a bottleneck layer, a fully connect layer, and a softmax layer. The convolution layer is a layer that obtains a feature image by performing a convolution 3x3 operation on the input image or the feature image of the previous layer with several feature filters. The bottleneck layer selects only the optimal features among the features on the feature image extracted through the convolution layer, reduces the channel to a convolution 1x1 ReLU, and performs a convolution 3x3 ReLU. The global average pooling operation performed after going through the bottleneck layer reduces the size of the feature image by selecting only the optimal features among the features of the feature image extracted through the convolution layer. The fully connect layer outputs the output data through 6 fully connect layers. The softmax layer multiplies and multiplies the value between the value of the input layer node and the target node to be calculated, and converts it into a value between 0 and 1 through an activation function. After the learning is completed, the recognition process classifies non-circular glass bottles by performing image acquisition using a camera, measuring position detection, and non-circular glass bottle classification using deep learning as in the learning process. In order to evaluate the performance of the deep learning structure to improve quality of polygonal containers, as a result of an experiment at an authorized testing institute, it was calculated to be at the same level as the world's highest level with 99% good/defective discrimination accuracy. Inspection time averaged 1.7 seconds, which was calculated within the operating time standards of production processes using non-circular machine vision systems. Therefore, the effectiveness of the performance of the deep learning structure to improve quality of polygonal containers proposed in this paper was proven.

• Journal of the Korean Institute of Gas
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• v.25 no.6
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• pp.53-65
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• 2021

While the hydrogen refueling station is rapidly expanded and installed, the safety inspection of the hydrogen pressure vessel in the station should be very important. Of these, according to ASME, hydrogen embrittlement tests must be performed for hydrogen vessel that store hydrogen above a certain pressure. The main test method for hydrogen embrittlement inspection is to carry out fracture tests and fatigue fracture tests in a high pressure hydrogen atmosphere, which allows the durability limit of the pressure vessel to be measured and the endurable limit to be determined in the hydrogen atmosphere. In detail, the critical crack depth can be calculated by the stress intensity factor(K), and the service life can be determined by da/dN (fatigue growth rate). API579-1/ ASME FFS-1 part 9 exemplifies the calculation method according to the mode of crack-like flaws, but for various shapes such as plates and cylinders, there are about 55 modes according to the shape and location of the crack. Due to the fairly complex formula, it is not easily accessible. In this study, we will show you how to calculate fracture mechanics numerically via Excel and VBA. In addition, this was applied to analyze the effects of the thickness and inner diameter of the pressure vessel on the service life.

• Journal of Energy Engineering
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• v.8 no.1
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• pp.59-66
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• 1999

원자력발전의 고유한 문제점을 해결할 수 있는 새로운 집적폐회로형 AMBIDEXTER 원자력시스템 개념을 제안하였다. 이 복합시스템은 일체형 원자로를 중심으로 열/에너지 변환회로와 방사선/물질 수송회로를 서로 독립적으로 구성하므로 최소 방사선 위험부담 아래서 원자력에너지의 잇점을 극대화하는 설계이다. 특히 방사선/물질 수송회로로부터 분리된 고준위 방사성 폐기물에서 고부가가치 동위원소나 방사선원을 선별적으로 용이하게 추출, 활용할 수 있다. 원자로 계통은 얇고 큰 Hastelloy 합금 원자로용기 내부를 노심, 침니, 열교환기, 다운캄어 및 입구플레넘 콤파트먼트로 분할하여 배관이나 벨브관이 없으므로 기기파손으로 인한 방사성물질의 대량 외부 누출은 불가능하다. Th/233U 용융염핵연료의 핵물리 및 열수력학적 특성을 살려 AMBIDEXTER 노심의 핵적 자활성 설계에 융통성을 부여하는 변성핵연료주기를 도입하면 핵연료자원의 공급 안정화나 핵확산방지의 투명성 제고에 큰 효과가 있다. AMBIDEXTER 설계연구에 관련된 핵심기술들은 일찍이 미국 ORNL에서 시작한 MSR 프로그램을 통해 개발되어 이미 대부분 상용화하고 있기 때문에 현재 추진 중인 250 MWth급 원형로 모듈의 개념개발에서는 주로 시스템 통합에 관한 문제들이 중점적으로 다루어진다.

• Proceedings of the KSME Conference
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• 2003.04a
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• pp.1765-1770
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• 2003

This paper describes a study of the spin-up of a free-surface fluid in a rectangular container in which an internal cylindrical obstacle is mounted. Experiments and numerical analysis have been carried out for a variety of obstacle position. Increase in the speed of background rotation and near wall position of cylindrical obstacle results in the complex flow structures. Numerical and experimental results agree well with each other and the Ekman-pumping model is also applied to this flow.