• Title/Summary/Keyword: 김상백

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On the influence survey to building by the cable Tunnel blasting works. (통신구 터널발파작업으로 인한 진동.소음이 지상주택에 미치는 영향 평가)

  • Huh Ginn;Cheon Sang Back
    • Explosives and Blasting
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    • v.11 no.1
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    • pp.5-33
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    • 1993
  • On the cable Tunnel works. Cautious blasting works were so effective and carried out. The vibration record were under 0.4cm / sec and blasting noise are under 75dB Which it was measured at the ground of Tailor House. As a result cautious blasting works under above allowable value, are not Influenced the structure of house and living. On the architechtural survey, there were some hair crack on the wall but this was not crack from recently blasting work.

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반구형 간극에서 CHF 가 발생했을 때 히터표면의 온도변화와 CHF 측정

  • 정지환;박래준;조영로;김상백;김희동
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.10a
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    • pp.675-680
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    • 1997
  • 반구형 간극에서 히터 출력이 임계열유속(CHF)에 이르렀을 때 히터표면의 온도 변화와 CHF 값을 측정하였다. 반구형 히터의 직경은 498mm 이고 간극은 1, 2mm 에서 실험을 수행하였다. 히터표면의 온도는 항상 간극상단의 특정 부분에서부터 증가하기 시작하였다. 즉, 이곳에서 국부적인 dryout이 발생한 것으로 판단된다. 히터의 열속이 증가함에 따라 dryout 부분은 원주방향과 아래방향으로 확장되었다. 한편 임계열유속보다 작은 열속에서는 dryout 영역이 변하지 않는 정상상태가 존재하였으나 임계열유속에서는 열속이 고정되어 있어도 dryout 영역이 스스로 확장되어 나갔다. 이 실험은 계속 진행중이며 현재까지 측정된 CHF 값을 제시하였다. CHF 값은 간극을 대상으로 개발된 기존의 실험식보다 낮게 측정되었다.

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A Comparative Study of k-ε Algebraic Stress Model and Mellor-Yamada Model Applied to Atmospheric Dispersion Simulation Using Lagrangian Particle Dispersion Model (라그랑지 입자 모델을 이용한 k-ε Algebraic Stress Model과 Mellor-Yamada Model의 비교 연구)

  • 김상백;오성남
    • Journal of Korean Society for Atmospheric Environment
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    • v.20 no.1
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    • pp.47-58
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    • 2004
  • The $textsc{k}$-$\varepsilon$ algebraic stress model (KEASM) was applied to atmospheric dispersion simulation using the Lagrangian particle dispersion model and was compared with the most popular turbulence closure model in the field of atmospheric simulation, the Mellor-Yamada (MY) model. KEASM has been rarely applied to atmospheric simulation, but it includes the pressure redistribution effect of buoyancy due to heat and momentum fluxes. On the other hand, such effect is excluded from MY model. In the simulation study, the difference in the two turbulence models was reflected to both the turbulent velocity and the Lagrangian time scale. There was little difference in the vertical diffusion coefficient $\sigma$$_{z}$. However, the horizontal diffusion coefficient or calculated by KEASM was larger than that by MY model, coincided with the Pasquill-Gifford (PG) chart. The applicability of KEASM to atmospheric simulations was demonstrated by the simulations.s.

An Experimental Study on the Quenching Phenomena of Hemispherical Downward Facing Convex Surfaces with Narrow Gaps (반구형 소형 간극 내에서의 냉각과정에 관한 실험적 연구)

  • Ha, Kwang-Soon;Park, Rae-Joon;Kim, Sang-Baik;Cho, Young-Ro;Kim, Hee-Dong
    • Proceedings of the KSME Conference
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    • 2001.06d
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    • pp.447-452
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    • 2001
  • Quenching phenomena of hemispherical downward facing convex surfaces with narrow gaps have been investigated experimentally. Experiments employed test sections having 1 and 2 mm in gap thickness and 1 atm in system pressure. From interpretations of the temperature and the heat flux history, it was found that the flooding inside the gap was restricted by CCFL phenomena and quenching process was propagated from lower to upper region of the internal copper shell. The ratio of the maximum heat fluxes at 1 mm to 2mm in gap thickness was the almost same that obtained by steady state experiments. The quenching scenario of the hemispherical downward facing surface with narrow gap has been suggested.

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Correlation Development on Critical Power in a Spherical Narrow Gap (구형 간극에서의 임계 출력에 대한 상관식 개발)

  • Park, Rae-Joon;Ha, Kwang-Soon;Kim, Sang-Baik;Kim, Hee-Dong;Jeong, Ji-Hwan
    • Proceedings of the KSME Conference
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    • 2001.06e
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    • pp.235-240
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    • 2001
  • The CHFG (Critical Heat Flux in Gap) test results have been evaluated to quantify the critical power in hemispherical narrow gaps and a new correlation has been developed. The CHFG test results have shown that increases in the gap thickness and pressure lead to an increase in critical power. The pressure effect on the critical power was found to be much milder than predictions by CHF correlations of other researches. From the CHFG test results, a new correlation on critical power in the hemispherical gap has been developed using the non-dimensional parameters as follows: $$\frac{qCHF}{{\rho}g^hfg}{\cdot}4\sqrt{\frac{{\rho}_g^2}{g{\sigma}{\Delta}{\rho}}=\frac{0.1042}{1+0.1375({\rho}g/{\rho}l)^{0.21}(D/s)}$$ The developed correlation has been expanded to apply the spherical geometry using the Siemens/KWU's correlation.

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An Experimental visualization of the Pool Boiling Heat Transfer on the Inclined square surface (경사진 가열면에서의 수조비등에 대한 가시화 연구)

  • Kim, J.K.;Song, J.H.;Kim, S.B.;Kim, H.D.
    • Proceedings of the KSME Conference
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    • 2001.06e
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    • pp.63-68
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    • 2001
  • An experimental study was carried out to identify the various regimes of natural convective boiling and to determine the Critical Heat Flux(CHF) on a 70mm square surface which is inclined at $180^{\circ}$(upward), $90^{\circ}, \;45^{\circ}$. The heater block made of copper with cartridge heaters is submerged in a water tank with windows for visualization. As the heat flux increases from $100kW/m^2$ to $1.1MW/m^2$, the heat transfer regime migrates from the nucleate boiling to film boiling and results in a rapid heat up of the heater block. An explosive vapor generation on the heated surface, whose size and frequency are characterized by the heat flux, is visualized by using a digital camcorder with $512{\times}512$ pixel size at 30fps.

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TEMPERATURE-EXPLICIT FORMULATION OF ENERGY EQUATION FOR A HEAT TRANSFER ANALYSIS (열유동 해석을 위한 에너지 방정식의 온도에 현시적인 이산화 기법)

  • Kim, Jong-Tae;Kim, Sang-Baik
    • 한국전산유체공학회:학술대회논문집
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    • 2009.04a
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    • pp.277-282
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    • 2009
  • A temperature equation which is derived from an enthalpy transport equation by using an assumption of a constant specific heat is very attractive for analyses of heat and fluid flows. It can be used for an analysis of a solid-fluid conjugate heat transfer, and it does not need a numerical method to find temperature from a temperature-enthalpy relation. But its application is limited because of the assumption. A new method is derived in this study, which is a temperature-explicit formulation of the energy equation. The enthalpy form of the energy equation is used in the method. But the final discrete form of the equation is expressed with temperature. It can be used for a solid-fluid conjugate heat transfer and multiphase flows. It is found by numerical tests that it is very efficient and as accurate as the standard enthalpy formulation.

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3D FE Analysis of Cast-in-situ Concrete Pile embedded in Weathered Rock (풍화암에 지지된 현장타설말뚝의 3차원 해석)

  • Kim, Sang-Baek;Lee, Whaol;Kwon, Oh-Kyun;Choi, Yong-Kyu
    • Proceedings of the Korean Geotechical Society Conference
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    • 2000.03b
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    • pp.167-172
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    • 2000
  • In this study, the behaviors of a cast-in-situ concrete pile embedded in the weathered rock were analysed by a 3D numerical analysis using PENTAGON 3D and the results were compared with those of the field load test. The load-settlement relation and the load transfer relationship were evaluated from the numerical analysis. As a result, the load-settlement relation at the pile top and the axial load distribution with depth were predicted reasonably. And those results were similar with those of the field load test.

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PHEBUS FPT0실험 PIE결과를 통한 노심 손상 후기 과정 분석

  • 박래준;김상백;김희동
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.11a
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    • pp.435-440
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    • 1996
  • PHEBUS FPT0 노내실험의 핵연료 다발에 대한 실험후 비파괴 검사 및 파괴 검사 결과를 분석하여 노심손상 후기과정을 정alf 분석하였다. 분석한 비파괴 검사결과는 gamma scanning, radiography, tomographies 였으며 파괴 검사 결과는 정밀사진, metallography, Electron Probe Micro Analysis(EPMA)였다. 그 결과, PHEBUS-FPT0 실험에 사용한 핵연료다발은 기존에 수행된 어떤 다른 노내실험의 핵연료다발보다 많이 용융되었으며 용융 pool 및 피막충의 형성, 용융물 내부의 자연대류 열전달과 이에 따른 shroud 물질 손상, 핵연료다발 물질들간의 eutectic 형성 등을 보여주었다. 특히 Ag-In-Cd 제어봉 물질과 stainless-steel이 핵연료봉 물질과 반응하여 이들의 용융온도를 낮게하여 실험 예측값보다 많이 핵연료다발이 손상되어 기존 중대사고 해석 전산코드의 개선이 요구되었다.

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