• 대한전기학회:학술대회논문집
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• 대한전기학회 1999년도 추계학술대회 논문집 학회본부 A
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• pp.43-45
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• 1999

This paper is presented about the development of magnetic levitation conveyor with a transverse flux linear synchronous motor (TFLSM). The TFLSM is proposed as the new type linear motor for the conveyor driving system. The flux density distribution. the thrust and etc. of TFLSM are analyzed by the finite element method. To analyze the dynamic characteristics of TFLSM, the parameter of equivalent circuit is calculated by the analytical method.

• 전기학회논문지
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• 제60권12호
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• pp.2236-2245
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• 2011

This paper deals with the levitation force characteristics of electromagnet for MAGLEV vehicle application. The magnetic flux density distribution and levitation force characteristics of the electromagnet are investigated by means of equivalent magnetic circuit model. Firstly, we defined the aligned and unaligned electromagnet module for the full-electromagnet, and magnetic flux paths are represented for each model including leakage and fringing flux paths. Because of the analysis model contains both the permanent magnet and electromagnet coil, we calculated the airgap magnetic flux density and levitation forces using flux superposition in electromagnetic circuit. The results are validated extensively by comparison with finite element analysis. Moreover, the 1/4 scaled magnetic levitation and propulsion test vehicle has been manufactured and tested in order to verify these predictions. The experimental results confirms the validity of the analytical prediction with equivalent magnetic circuit model for the description of a electromagnet.

• Nuclear Engineering and Technology
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• 제33권4호
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• pp.409-422
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• 2001

The dynamic character of a system of the governing differential equations for the one- dimensional two-fluid model, where the momentum flux parameters are employed to consider the velocity and void fraction distribution in a flow channel, is investigated. In response to a perturbation in the form of a＇traveling wave, a linear stability analysis is peformed for the governing differential equations. The expression for the growth factor as a function of wave number and various flow parameters is analytically derived. It provides the necessary and sufficient conditions for the stability of the one-dimensional two-fluid model in terms of momentum flux parameters. It is demonstrated that the one-dimensional two-fluid model employing the physical momentum flux parameters for the whole range of dispersed flow regime, which are determined from the simplified velocity and void fraction profiles constructed from the available experimental data and $C_{o}$ correlation, is stable to the linear perturbations in all wave-lengths. As the basic form of the governing differential equations for the conventional one-dimensional two-fluid model is mathematically ill posed, it is suggested that the velocity and void distributions should be properly accounted for in the one-dimensional two-fluid model by use of momentum flux parameters.s.

• 대한설비공학회:학술대회논문집
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• 대한설비공학회 2007년도 동계학술발표대회 논문집
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• pp.176-181
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• 2007

This study aims to evaluate theoretically heat transfer characteristics and heat flux performance in ondol system of dried type is composed of panel of ceramics to improve of thermal conductivity and fin to expand heat. To this end, we analyzed effect of design factors(temperature of hot water, set temperature of room and thermal conductivity of finishing materials) in ondol system of dried type by heat transfer analysis. The main results of this study are summarized as follows; The deviation of heat flux and temperature was reduced by heat expansion from fin decreasing heat loss generated in air layer. The temperature and heat flux in upper finishing materials surface linearly increased according to temperature increment of hot water, but the temperature distribution in upper surface was assessed uneven. The greater heat resistance value of upper finishing materials, the deviation of maximum temperature and minimum temperature was decreased. Also, we suggested a basic design data about ondol system of dried type through an analysis of simulation results on heat transfer characteristics and heat flux performance.

• 한국추진공학회지
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• 제7권3호
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• pp.8-14
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• 2003

KSR-III 축소형 엔진을 원형으로 하는 8채널형 칼로리미터의 냉각성능해석을 수행하였다. 축대칭 압축성 해석을 통해서 연소실 벽으로의 열유속을 예측하였으며 이를 이용하여 3차원 냉각유로 내부의 열전달 해석을 수행하였다. 연소실 벽으로의 열유속은 문헌에서 제시하는 수준으로 확인되었으며 열전달 해석을 통하여 칼로리미터 개발과 운용에 필요한 냉각수의 압력강하, 온도상승 및 연소실벽의 최고온도를 제시하였다. 연소실 압력증가에 따른 냉각요구량을 결정하였으며 냉각수의 물성변화에 의한 냉각성능 변화를 예측하였다.

• 반도체디스플레이기술학회지
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• 제20권4호
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• pp.72-77
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• 2021

The radial distribution of etch rate was analyzed using the ion energy flux model in VHF-CCP. In order to exclude the effects of polymer passivation and F radical depletion on the etching. The experiment was performed in Ar/SF6 plasma with an SF6 molar ratio of 80% of operating pressure 10 and 20 mTorr. The radial distribution of Ar/SF6 plasma was diagnosed with RF compensated Langmuir Probe(cLP) and Retarding Field Energy Analyzer(RFEA). The radial distribution of ion energy flux was calculated with Bohm current times the sheath voltage which is determined by the potential difference between the plasma space potential (measured by cLP) and the surface floating potential (by RFEA). To analyze the etch rate uniformity, Si coupon samples were etched under the same condition. The ion energy flux and the etch rate show a close correlation of more than 0.94 of R² value. It means that the etch rate distribution is explained by the ion energy flux.

• Journal of Radiation Protection and Research
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• 제6권1호
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• pp.8-24
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• 1981

This paper presents flux-to-dose-rate conversion factors for neutrons and gamma rays based on the American National Standard Institute(ANSI) N666. These data are used to calculated the dose rate distribution of neutron and gamma ray in radiation fields. Neutron flux-to-dose-rate conversion factors for energies from $2.5{\times}10^{-8}$ to 20 MeV are presented; the corresponding energy range for gamma rays is 0.01 to 15 MeV. Flux-to-dose-rate conversion factors were calculated, under the assumption that radiation energy distribution has nonlinearity in the phantom, have different meaning from those values obtained by monoetiergetic radiation. Especially, these values were determined with the cross section library. The flux-to-dose-rate conversion factors obtained in this work were in a good agreement to the values presented by ANSI. Those data will be a useful for the radiation shielding analysis and the radiation dosimetry in the case of continuous energy distributions.

• 한국신재생에너지학회:학술대회논문집
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• 한국신재생에너지학회 2005년도 춘계학술대회
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• pp.422-426
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• 2005

This experimental study represents the results of an analysis on the characteristics of flux density distribution in the focal region of solar concentrator. The characteristics of flux density distributions are investigated to optimally design and position a cavity receiver. This was deemed very useful to find and correct various errors associated with a dish concentrator. We estimated the flux density distribution on the target placed along with focal lengths from the dish vertex to experimentally determine the focal length. It is observed that the actual focal point exists when the focal length is 2.17m. The total integrated power and percent power was 2467W and $85.8\%$, respectively, in the case of small dish, and also 2095W and $79\%$, respectively, in the case of KIERDISH II. As a result of the percent power within radius, approximately $90\%$ of the incident radiation is intercepted by about 0.06 m radius. The minimum radius of receiver in KIERDISH II is found to be 0.15m and approximately $90\%$ of the incident radiation is intercepted by receiver aperture.

• 대한조선학회논문집
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• 제35권1호
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• pp.98-106
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• 1998

멤브레인형 가스운반선의 경우 화물창들 사이에 cofferdam을 두어 격리시키고 있는데 이 경우 극 저온 액체 화물의 영향으로 cofferdam 실내 온도는 약 $-40^{\circ}C$내외로 떨어지게 된다. 그 결과 cofferdam 및 화물창을 구성하는 bulkhead는 구조 부재로서의 허용 강도를 만족하는 온도를 유지할 수 없게 된다. 결국 heating system을 사용하여 cofferdam 실내 온도를 최소한 $5^{\circ}C$까지 올려야 하는데, 소요 pipe의 길이 산정을 위한 heat flux 산출과 pipe의 배치가 우선적으로 요청된다. 본 연구에서는 다양한 설계 조건에서의 cofferdam 내 heat flux를 각 compartment들 간의 연성 효과를 고려하여 구하고 이를 기존 계산서들과 비교 검토하여 그 타당성을 검증하였고 이를 토대로 heating system에 필요한 pipe의 길이를 산정하였다. 아울러 현재의 heating system의 대안으로 fin을 부착한 pipe로 구성된 heating coil system을 제시하고 그 효율을 비교하였다.

• Nuclear Engineering and Technology
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• 제53권2호
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• pp.430-438
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• 2021

The spatial distribution of neutron flux or reaction rate was calculated by cell or mesh tally in traditional Monte Carlo simulation. However, either cell or mesh tally leads to the increase of memory consumption and simulation time. In this paper, the function expansion tally (FET) method was developed in Reactor Monte Carlo code RMC to solve this problem. The FET method was applied to the tallies of neutron flux distributions of uranium block and PWR fuel rod models. Legendre polynomials were used in the axial direction, while Zernike polynomials were used in the radial direction. The results of flux, calculation time and memory consumption of different expansion orders were investigated, and compared with the mesh tally. Results showed that the continuous distribution of flux can be obtained by FET method. The flux distributions were consistent with that of mesh tally, while the memory consumption and simulation time can be effectively reduced. Finally, the convergence analysis of coefficients of polynomials were performed, and the selection strategy of FET order was proposed based on the statistics uncertainty of the coefficients. The proposed method can help to determine the order of FET, which was meaningful for the efficiency and accuracy of FET method.