• 제목/요약/키워드: Thermal Flow Analysis

검색결과 1,503건 처리시간 0.029초

Slip flow 영역에서의 미소채널 내 열전달 및 유동에 관한 수치적 연구 (A Numerical Study of Heat transfer and Flow Analysis for a Micro-channel in The Slip Flow Regime)

  • 정수인;김귀순;강범수
    • 유체기계공업학회:학술대회논문집
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    • 유체기계공업학회 2006년 제4회 한국유체공학학술대회 논문집
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    • pp.391-394
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    • 2006
  • In this paper, the thermal lattice Boltzmann method(TLBM) proposed by Guo et al.(2002) is applied to analyze the forced convective flow and heat transfer of 2-D micro channel. Nonequilibrium extrapolation boundary condition is adopted to simulate the velocity and temperature behavior at wall boundaries. Numerical results obtained by the present study give a good prediction of the micro fluidic characteristics with thermal effects.

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핵연료 집합체에서의 열유동 특성에 관한 연구 (A Study on Thermal-hydraulic Characteristics for Nuclear Fuel Rod Bundle)

  • 유성연;정민호;김만웅;최영준;김현군
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 추계학술대회논문집B
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    • pp.3-8
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    • 2001
  • For the successful design of nuclear reactor, it is very important to investigate thermal-hydraulic characteristics of fuel rod bundle. Fluid flow and heat transfer in the non-circular cross-section of nuclear fuel rod bundle are different from those found in common circular tube. And complex three dimensional flow including secondary and vortex flow, is formed around the bundles. The purpose of this research is to examine how geometries and flow conditions affect heat transfer in fuel rod bundle. Design data for nuclear fuel rod bundle and structure are surveyed, and $3{\times}3$ sub-channel model is adopted in this study. Computational results are compared with the heat transfer data measured by naphthalene sublimation method, and numerical analysis and evaluation are performed at various design conditions and flow conditions.

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Thermal analysis of certain accident conditions of dry spent nuclear fuel storage

  • Alyokhina, Svitlana
    • Nuclear Engineering and Technology
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    • 제50권5호
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    • pp.717-723
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    • 2018
  • Thermal analysis of accident conditions is an important problem during safety assessment of the dry spent nuclear fuel storage facilities. Thermal aspects of accident conditions with channel blockage of ventilated storage containers are considered in this article. Analysis of flow structure inside ventilated containers is carried out by numerical simulation. The main mechanisms of heat and mass transfer, which take part in spent nuclear fuel cooling, were detected. Classification of accidents on the basis of their influence on the maximum temperatures inside storage casks is proposed.

용탕유동과 응고를 고려한 주조공정의 유한요소해석 (Finite element analysis of casting processes considering molten-metal flow and solidification)

  • 윤석일;김용환
    • 한국정밀공학회지
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    • 제13권3호
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    • pp.110-122
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    • 1996
  • Finite element analysis tool was developed to analyze the casting process. Generally, casting process consists of mold filling and solidification. Both filling and solidication process were simulated simultaneously to investigate the effects of process variables and to predict the defect. At filling process, thermal coupling was especially considered to investigate thermal history of material during the filling stage. And thermal condition at the final stage of filling is used as the initial conditions in a solidification process for the exact simullation of the actual casting processes. At mold filling process, Lagragian-type finite element method with automatic remeshing scheme was used to find the material flow. A perturbation method with artificial viscosity is adopted to avoid numerical instability in low viscous fluid. At solidification process, enthalpy-based finite element method was used to solove the heat transfer problem with phase change. And elastic stress analysis has been performed to predict the thermal residual stress. Through the FE analysis, solidification time, position of solidus line, liquidus line and thermal residual stress are found. Through the study, the importance of combined analysis has been emphasized. Finite element tools developed in this study will be used process design of casting process and may be basic structure for total CAE system of castings which will be constructed afterward.

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채널 유동장 내에 배열된 전자부품의 강제대류 냉각 특성에 관한 연구(I) -채널과 발열부품의 높이 비(H/B)의 영향(히트싱크가 부착되지 않은 경우)- (Cooling Characteristics on the Forced Convection of an Array of Electronic Components in Channel Flow (I) - The Effect of H/B (without the Heat Sink) -)

  • 김광수;양장식
    • 설비공학논문집
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    • 제18권1호
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    • pp.73-80
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    • 2006
  • Present study is concerned with an experimental study on the cooling characteristics of heat-generating components arranged in channels which are made by printed circuit boards. To assess the thermal performance of the heat-generating components arranged by $5\times11$ in flow channel, three variables are used: the velocity of the fluid at the entrance, the height of channel, and row number of the component. The cooling characteristics of the heat-generating components such as the surface temperature rise, the adiabatic temperature rise, the adiabatic heat transfer coefficient, and the effect of thermal wake are compared with the result of the experiment and the numerical analysis. Based on the experiment analysis, some conclusions can be drawn: First of all, the experiment and numerical analysis are identical comparatively; the heat transfer coefficient increases as H/B decreases. Howeve., when H/B is over 7.2, the effect of H/B is rather trivial. The effect is the biggest at the first component from the entrance, and it decreases until the fully developed flow, where it becomes very consistent. The thermal wake function calculated for each row decreases as H/B increases.

CUPID 코드와 MARS 코드를 이용한 기기/계통 다중스케일 연계 해석 코드 구현 (COMPONENT AND SYSTEM MULTI-SCALE DIRECT-COUPLED CODE IMPLEMENTATION USING CUPID AND MARS CODES)

  • 박익규
    • 한국전산유체공학회지
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    • 제21권3호
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    • pp.89-97
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    • 2016
  • In this study, direct code coupling, in which two codes share a single flow field, was conducted using 3-dimensional high resolution thermal hydraulics code, CUPID and 1-dimensional system analysis code, MARS. This approach provide the merit to use versatile capability of MARS for nuclear power plants and 3-dimensional T/H analysis capability of CUPID. Numerical Method to directly couple CUPID and MARS was described in this paper. The straight flow and manometer flow oscillation were calculated to verify conservation of coupled CUPID/MARS code in mass, momentum, and energy. This verification calculations indicates that the CUPID/MARS is coupled appropriately in numerical aspect and the coupled code can be applied to nuclear reactor thermal hydraulics after validation against integral transient experiments.

최적의 램프뱅크형태를 결정하기 위한 열유동 해석 (A Thermal Flow Analysis for an Optimal shape of Solar Lamp Bank)

  • 백상화
    • 한국태양에너지학회 논문집
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    • 제32권4호
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    • pp.82-89
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    • 2012
  • This study is on the thermal flow analysis to select an optimal shape of solar lamp bank. Solar Lamp bank is designed by the lamp bank design program based on point light source theory. The reliability of the program for lamp bank design is verified through irradiance variation experiments of a kind of lamp according to horizontal distance. Solar lamp bank facilitates heat distribution and satisfies the irradiance in the three wave length which test guidelines require. Among the 4 kinds of lamp bank, since lamp bank type D satisfies uniformity ${\pm}10%$ and also doesn't exceed total irradiance 1,232 $W/m^2$, type D is finally selected.

유기랭킨사이클과 암모니아-물 랭킨사이클의 열역학적 성능의 비교 해석 (Comparative Thermodynamic Analysis of Organic Rankine Cycle and Ammonia-Water Rankine Cycle)

  • 김경훈;김만회
    • 한국수소및신에너지학회논문집
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    • 제27권5호
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    • pp.597-603
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    • 2016
  • In this paper a comparative thermodynamics analysis is carried out for organic Rankine cycle (ORC) and ammonia-water Rankine cycle (AWRC) utilizing low-grade heat sources. Effects of the working fluid, ammonia concentration, and turbine inlet pressure are systematically investigated on the system performance such as mass flow rate, pressure ratio, turbine-exit volume flow, and net power production as well as the thermal efficiency. Results show that ORC with a proper working fluid shows higher thermal efficiency than AWRC, however, AWRC shows lower mass flow rate of working fluid and lower pressure ratio of expander than ORC.

초저온 볼밸브의 열 응력 및 유동해석 (Thermal stress and Flow Analysis of a Cryogenic Ball Valve)

  • 배상규;이원희;김현섭;김동수
    • 유공압시스템학회논문집
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    • 제3권4호
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    • pp.8-13
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    • 2006
  • The high pressure cryogenic ball valve is used to transfer the liquefied natural gas which temperature is $-196^{\circ}C$, supplied pressure is $168kgf/cm^2$. In the present work, the temperature distribution and thermal deformation is calculated numerically. The CAR and CFD methods are useful to predict the thermal matter and the inner flow field of high pressure cryogenic ball valve. For this reason, to optimum design of the cryogenic ball valve, the theological behavior of the supplied LNG in a cryogenic valve has been studied. The governing equations are discredited and solved numerically by the finite-volume method and finite-element method. In this study, we designed the high pressure cryogenic ball valve that accomplishes zero leakage by elastic seal at normal temperature and metal seal at high temperature.

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열 유동해석을 통한 무선충전기 발열 성능 향상에 관한 연구 (A Study on the Thermal Flow Analysis for Heat Performance Improvement of a Wireless Power Charger)

  • 김평준;박동규
    • 한국산학기술학회논문지
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    • 제20권7호
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    • pp.310-316
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    • 2019
  • 자동차 편의 장치에 대하여 고객들은 높은 효율과 많은 기능을 요구하고 있으며, 이러한 자동차 어플리케이션에 대한 수요가 지속적으로 증가하고 있다. 본 연구에서는 최근 자동차 편의 사양으로 개발된 무선충전기의 PCB(printed circuit board) 발열 성능 향상을 위한 열 유동해석에 관한 연구를 진행하였다. 무선충전기는 PCB의 전력 손실 및 열 저항의 특성 발열에 따라 충전의 성능이 급격히 저하된다. 따라서 열 유동해석 시뮬레이션을 통해 최적의 PCB 설계 및 부품의 실장 위치를 제안하고, 각 설계 단계에서 해석을 통해 디자인을 결정한다. 이후, 실제 환경 조건에서 해석결과 정합성 검증을 위해 시험을 수행하고 결과를 비교 분석한다. 본 논문에서는 HyperLynx Thermal와 FloTHERM 프로그램을 사용하여 PCB 모델링 및 과도 응답 열 유동해석을 수행하였다. 또한, 해석 및 측정 결과의 정합성 검증을 위해 적외선 열화상 카메라를 사용하여 시험을 진행하였다. 최종 결과 비교에서 해석과 시험의 오차는 10 % 이내로 확인되었고, PCB의 발열 성능도 향상되었다.