• 제목/요약/키워드: Fluid-heat Interaction

검색결과 78건 처리시간 0.023초

Influence of Blade Row Distance on Performance and Flow Condition of Contra-Rotating Small-Sized Axial Fan

  • Shigemitsu, Toru;Fukutomi, Junichiro;Shimizu, Hiroki
    • International Journal of Fluid Machinery and Systems
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    • 제5권4호
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    • pp.161-167
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    • 2012
  • Small-sized axial fans are used as air coolers for electric equipment. There is a strong demand for higher power of fans according to the increase of quantity of heat from electric devices. Therefore, higher rotational speed design is conducted, although, it causes the deterioration of the efficiency and the increase of noise. Then, the adoption of contra-rotating rotors for small-sized fans is proposed for the improvement of the performance. In the case of contra-rotating rotors, blade row distance between the front and the rear rotors influences on the performance and the noise. Therefore, it is important to clarify the optimum blade row distance between front and rear rotors. The performance curves of the contra-rotating small-sized axial fan under the condition of different blade row distances are shown and the blade row interaction between the front and the rear rotors are discussed by the numerical results. Furthermore, the optimum blade row distance of the contra-rotating small-sized axial fan is considered.

측추력기 Shutter의 단방향 유체-구조 연성해석에 관한 연구 (A Study on the 1-Way FSI Analysis for Shutter of Side Jet Thruster)

  • 고준복;서민교;이경호;백기봉;조승환
    • 대한기계학회논문집A
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    • 제38권12호
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    • pp.1359-1365
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    • 2014
  • 본 연구에서는 측추력기 구성품인 Shutter의 열구조 안전성을 평가하기 위해 단방향 유체-구조 연성해석을 수행하였다. Shutter는 측추력기에서 노즐을 개방시키기 위한 구동 토크와 연소가스의 고온, 고압 열하중을 받는 부품으로 연소가 진행되는 동안 열구조 안전성을 확보하여야만 한다. 유체-구조 연성해석을 위해 측추력기의 연소시간동안 내부 유동장에서 발생하는 연소가스의 압력 및 온도 분포, 대류 열전달계수값을 유동해석을 통해 도출하였고, 이 결과 값을 맵핑 방식을 이용하여 열구조 해석의 하중조건으로 부가하였다. 연소시간동안 Shutter에서 발생되는 최대 응력 및 취약위치, 온도분포를 단위 시간 단위로 분석하여 온도에 따른 소재의 인장강도 값과 비교하여 열구조 안전성을 평가 하였다. 또한 반경 방향 변형량을 분석하여 셔터와 노즐목 간의 적정 간극을 설정하는 근거로 활용하였다.

NEUTRON-INDUCED CAVITATION TENSION METASTABLE PRESSURE THRESHOLDS OF LIQUID MIXTURES

  • Xu, Y.;Webster, J.A.;Lapinskas, J.;Taleyarkhan, R.P.
    • Nuclear Engineering and Technology
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    • 제41권7호
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    • pp.979-988
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    • 2009
  • Tensioned metastable fluids provide a powerful means for low-cost, efficient detection of a wide range of nuclear particles with spectroscopic capabilities. Past work in this field has relied on one-component liquids. Pure liquids may provide very good detection capability in some aspects, such as low thresholds or large radiation interaction cross sections, but it is rare to find a liquid that is a perfect candidate on both counts. It was hypothesized that liquid mixtures could offer optimal benefits and present more options for advancement. However, not much is known about radiation-induced thermal-hydraulics involving destabilization of mixtures of tensioned metastable fluids. This paper presents results of experiments that assess key thermophysical properties of liquid mixtures governing fast neutron radiation-induced cavitation in liquid mixtures. Experiments were conducted by placing liquid mixtures of various proportions in tension metastable states using Purdue's centrifugally-tensioned metastable fluid detector (CTMFD) apparatus. Liquids chosen for this study covered a good representation of both thermal and fast neutron interaction cross sections, a range of cavitation onset thresholds and a range of thermophysical properties. Experiments were devised to measure the effective liquid mixture viscosity and surface tension. Neutron-induced tension metastability thresholds were found to vary non-linearly with mixture concentration; these thresholds varied linearly with surface tension and inversely with mixture vapor pressure (on a semi-log scale), and no visible trend with mixture viscosity nor with latent heat of vaporization.

냉난방 가동 모사에 따른 콘크리트 에너지파일의 열응력 해석에 대한 연구 (Study on Thermal Stress Occurred in Concrete Energy Pile During Heating and Cooling Buildings)

  • 성치훈;박상우;김병연;정경식;최항석
    • 한국지열·수열에너지학회논문집
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    • 제11권2호
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    • pp.12-18
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    • 2015
  • The energy pile, used for both structural foundations and heat exchangers, brings about heat exchange with the ground formation by circulating a working fluid for heating and cooling buildings. As heat exchange occurs in the energy pile, thermal stress and strain is generated in the pile body and surrounding ground formation. In order to investigate the thermo-mechanical behavior of an energy pile, a comprehensive experimental program was conducted, monitoring the thermal stress of a cast-in place energy pile equipped with five pairs of U-type heat exchanger pipes. The heating and cooling simulation both continued for 30 days. The thermal strain in the longitudinal direction of the energy pile was monitored for a 15 operation days and another 15 days monitoring followed, without the application of heat exchange. In addition, a finite element model was developed to simulate the thermo-mechanical behavior of the energy pile. A non-linear contact model was adopted to interpret the interaction at the pile-soil interface, and thermal-induced structure mechanics was considered to handle the thermo-mechanical coupled multi-field problem.

동심축 이중관 구조에서 유동기인진동 특성 고찰 (Investigation of FIV Characteristics on a Coaxial Double-tube Structure)

  • 송기남;김용완;박상철
    • 대한기계학회논문집A
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    • 제33권10호
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    • pp.1108-1118
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    • 2009
  • A Very High Temperature Gas Cooled Reactor (VHTR) has been selected as a high energy heat source of the order of $950^{\circ}C$ for nuclear hydrogen generation, which can produce hydrogen from water or natural gas. A primary hot gas duct (HGD) as a coaxial double-tube type cross vessel is a key component connecting a reactor pressure vessel and an intermediate heat exchanger in the VHTR. In this study, a structural sizing methodology for the primary HGD of the VHTR is suggested in order to modulate a flow-induced vibration (FIV). And as an example, a structural sizing of the horizontal HGD with a coaxial double-tube structure was carried out using the suggested method. These activities include a decision of the geometric dimensions, a selection of the material, and an evaluation of the strength of the coaxial double-tube type cross vessel components. Also in order to compare the FIV characteristics of the proposed design cases, a fluid-structure interaction (FSI) analysis was carried out using the ADINA code.

에탄 열분해 반응이 동반된 관형 반응기에서의 열전달 및 화학반응 특성 연구 (THE CHARACTERISTICS OF HEAT TRANSFER AND CHEMICAL REACTION FOR THERMAL CRACKING OF ETHANE IN TUBULAR REACTOR)

  • 신찬영;안준
    • 한국전산유체공학회지
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    • 제21권1호
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    • pp.43-49
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    • 2016
  • Thermal cracking is commonly modeled as plug flow reaction, neglecting the lateral gradients present. In this paper, 2-dimensional computational fluid dynamics including turbulence model and molecular reaction scheme are carried out. This simulation is solved by means of coupled implicit scheme for stable convergence of solution. The reactor is modeled as an isothermal tube, whose length is 1.2 m and radius is 0.01 m, respectively. At first, The radial profile of velocity and temperature at each point are predicted in its condition. Then the bulk temperature and conversion curve along the axial direction are compared with other published data to identify the reason why discussed variations of properties are important to product yield. Finally, defining a new non-dimensional number, Effect of interaction with turbulence, heat transfer and chemical reaction are discussed for design of thermal cracking furnace.

직사각형 밀폐공간내에서의 복사 및 자연대류 열전달 (Combined Radiation-Natural Convection Heat Transfer in a Rectangular Enclosure)

  • 김기훈;이택식;이준식
    • 대한기계학회논문집
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    • 제11권2호
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    • pp.331-344
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    • 1987
  • 본 연구에서는 직사각형 밀폐공간내에서 자연대류와 복사의 상호 영향에 대해 서 P-1 근사를 이용하여 수치적으로 해석하였다.밀폐공간내에서의 온도분포, 속도 분포 및 열전달계수를 구하였으며 열경계층내에서의 전도와 복사의 상호 영향에 대하 여 고찰하였다. 표면 복사만이 존재하는 경우에 대해서도 고찰함으로써 P-1 근사의 적용한계를 규명하였다. 벽면을 산광 방사 및 반사체(diffuse emitter and reflec- tor)로, 기체는 회색체(gray body)로 가정하였다. 이는 복사 물성치의 파장에 따른 변화를 고려할 때의 대단히 복잡한 계산 과정을 피할 수 있고, 현재의 이론적 수준에 비추어 복사 열전달의 열향을 정성적으로 규명하는데 타당한 가정이다.

Large-eddy simulation on gas mixing induced by the high-buoyancy flow in the CIGMAfacility

  • Satoshi Abe;Yasuteru Sibamoto
    • Nuclear Engineering and Technology
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    • 제55권5호
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    • pp.1742-1756
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    • 2023
  • The hydrogen behavior in a nuclear containment vessel is a significant issue when discussing the potential of hydrogen combustion during a severe accident. After the Fukushima-Daiichi accident in Japan, we have investigated in-depth the hydrogen transport mechanisms by utilizing experimental and numerical approaches. Computational fluid dynamics is a powerful tool for better understanding the transport behavior of gas mixtures, including hydrogen. This paper describes a Large-eddy simulation of gas mixing driven by a high-buoyancy flow. We focused on the interaction behavior of heat and mass transfers driven by the horizontal high-buoyant flow during density stratification. For validation, the experimental data of the Containment InteGral effects Measurement Apparatus (CIGMA) facility were used. With a high-power heater for the gas-injection line in the CIGMA facility, a high-temperature flow of approximately 390 ℃ was injected into the test vessel. By using the CIGMA facility, we can extend the experimental data to the high-temperature region. The phenomenological discussion in this paper helps understand the heat and mass transfer induced by the high-buoyancy flow in the containment vessel during a severe accident.

고체 위의 박막에서의 분리압력 및 안정특성에 관한 연구 (Disjoining pressure of nanoscale thin film on solid substrate)

  • 한민섭
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2007년도 춘계학술대회B
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    • pp.1912-1915
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    • 2007
  • The disjoining pressure is critical in modeling the transport phenomena in small scales. They are very useful in characterizing the non-continuum effects that are not negligible in heat and mass transports in the film of less than submicro-scales. We present he disjoining pressure of thin film absorbed on solid substrate using Molecular Dynamics Simulation (MD). The disjoining pressure with respect to the film thickness is accurately calculated in the resolution of a molecular scale. The characteristics of the pressure are discussed regarding the molecular nature of the fluid system like molecular diameter and intermolecular interaction. Also, the MD results are compared with those based on the macroscopic approximation of the slab-like density profile. Significant discrepancy is observed when the effective film thickness is less than several molecular diameter

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원전 가압경수로 증기발생기 열유동 해석법 (Thermal Hydraulic Analysis Methodology for PWR Nuclear Power Plant Steam Generators)

  • 최석기;남호윤;김의광;김형남;장기상;홍승열
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 춘계학술대회논문집E
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    • pp.463-468
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    • 2001
  • This paper presents the methodology for thermal hydraulic analysis of Pressurized Water Reactor (PWR) steam generators. Topics include porous media approach, governing equations, physical models and correlations for solid-to-fluid interaction and heat transfer and numerical solution scheme. Some details about the ATHOS3 code currently used widely for thermal hydraulic analysis of PWR steam generators in the industry are presented. The ATHOS3 code is applied to the thermal hydraulic analysis of steam generator in the Korea YGN 3&4 nuclear power plant and the computed results are presented.

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