• 제목/요약/키워드: Thermal transport analysis

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Analysis of flow Field in a steam turbine LP/HP Bypass control Valve (증기터빈 Bypass Valve 의 유동장 해석)

  • Choi, Ji-Yong;Kim, Kwang-Yong
    • 유체기계공업학회:학술대회논문집
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    • 2005.12a
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    • pp.437-440
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    • 2005
  • In the present work, characteristics of the flow in CAGE of a steam turbine LP/HP Bypass control valve for thermal power plant are investigated. The flow field is analyzed numerically by solving steady three-dimensional Reynolds-averaged Navier-Stokes equations. Shear stress transport (SST) model is used as turbulence closure.

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Microstructural Characterization of Composite Electrode Materials in Solid Oxide Fuel Cells via Image Processing Analysis

  • Bae, Seung-Muk;Jung, Hwa-Young;Lee, Jong-Ho;Hwang, Jin-Ha
    • Journal of the Korean Ceramic Society
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    • v.47 no.1
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    • pp.86-91
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    • 2010
  • Among various fuel cells, solid oxide fuel cells (SOFCs) offer the highest energy efficiency, when taking into account the thermal recycling of waste heat at high temperature. However, the highest efficiency and lowest pollution for a SOFC can be achieved through the sophisticated control of its constituent components such as electrodes, electrolytes, interconnects and sealing materials. The electrochemical conversion efficiency of a SOFC is particularly dependent upon the performance of its electrode materials. The electrode materials should meet highly stringent requirements to optimize cell performance. In particular, both mass and charge transport should easily occur simultaneously through the electrode structure. Matter transport or charge transport is critically related to the configuration and spatial disposition of the three constituent phases of a composite electrode, which are the ionic conducting phase, electronic conducting phase, and the pores. The current work places special emphasis on the quantification of this complex microstructure of composite electrodes. Digitized images are exploited in order to obtain the quantitative microstructural information, i.e., the size distributions and interconnectivities of each constituent component. This work reports regarding zirconia-based composite electrodes.

Failure Analysis of Stress Reliever in Heat-Transport Pipe of District Heating System

  • Cho, Jeongmin;Chae, Hobyung;Kim, Heesan;Kim, Jung-Gu;Kim, Woo Cheol;Lee, Soo Yeol
    • Corrosion Science and Technology
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    • v.21 no.4
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    • pp.243-249
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    • 2022
  • The objective of the present study was to perform failure analysis of double-layered bellow (expansion joint), a core part of stress reliever, used to relieve axial stresses induced by thermal expansion of heat-transport pipes in a district heating system. The bellow underwent tensile or compressive stresses due to its structure in terms of position. A leaked position sufferred a fatigue with a tensile component for decades. A cracked bellow contained a higher fraction of martensitic phase because of manufacturing and usage histories, which induced more brittleness on the component. Inclusions in the inner layer of the bellow acted as a site of stress concentration, from which cracks initiated and then propagated along the hoop direction from the inner surface of the inner layer under fatigue loading conditions. As the crack reached critical thickness, the crack propagated to the outer surface at a higher rate, resulting in leakage of the stress reliever.

COMPUTATION OF NATURAL CONVECTION AND THERMAL STRATIFICATION USING THE ELLIPTIC BLENDING MODEL (Ellipting Blending Model에 의한 자연대류 및 열성층 해석)

  • Choi, Seok-Ki;Kim, Seong-O
    • 한국전산유체공학회:학술대회논문집
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    • 2006.10a
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    • pp.77-82
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    • 2006
  • Evaluation of the elliptic blending turbulence model (EBM) together with the two-layer model, shear stress transport (SST) model and elliptic relaxation model (V2-F) is performed for a better prediction of natural convection and thermal stratification. For a natural convection problem the models are applied to the prediction of a natural convection in a rectangular cavity and the computed results are compared with the experimental data. It is shown that the elliptic blending model predicts as good as or better than the existing second moment differential stress and flux model for the mean velocity and turbulent quantities. For thermal stratification problem the models are applied to the thermal stratification in the upper plenum of liquid metal reactor. In this analysis there exist much differences between the turbulence models in predicting the temporal variation of temperature. The V2-F model and EBM better predict the steep gradient of temperature at the interface of thermal stratification, and the V2-F model and EBM predict properly the oscillation of temperature. The two-layer model and SST model fail to predict the temporal oscillation of temperature.

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Prediction of Spectral Phonon Mean Free Path Contribution to Thermal Conduction in Silicon Using Phonon Kinetic Theory (포논 기체 운동론을 이용한 실리콘 내 포논 평균자유행로 스펙트럼 열전도율 기여도 예측)

  • Jin, Jae Sik
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.41 no.5
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    • pp.341-346
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    • 2017
  • Knowing the mean free paths (MFPs) of thermal phonons is an essential step in performing heat transfer analysis for nanomaterials, and in determining the optimum design for tailoring the heat transfer characteristics of nanomaterials. In this study, we present a method that can be used to calculate accurately the phonon MFP spectra of nanostructures based on simple phonon kinetic theory. Here, the kinetic theory may be employed by extracting only the diffusive-transport part of the phonon spectrum (i.e., the MFPs are less than a thermal length). By considering phonon dispersion and polarization effects, the phonon MFP distributions of silicon at room temperature are calculated from phonon transport properties and the spectral MFP. Our results are validated by comparison with those of the first principle and MFP spectroscopy data.

A Simple Condensation Model on the Vapor Jets in Subcooled Water (과냉각수로 방출되는 증기제트의 응축모델)

  • Kim, Hwan-Yeol;Ha, Kwang-Soon;Bae, Yoon-Yeong;Park, Jong-Kyun;Choi, Sang-Min
    • Proceedings of the KSME Conference
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    • 2001.06d
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    • pp.240-245
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    • 2001
  • Phenomena of direct contact condensation (DCC) heat transfer between steam and water are characterized by the transport of heat and mass through a moving steam/water interface. Application of the phenomena of DCC heat transfer to the engineering industries provides some advantageous features in the viewpoint of enhanced heat transfer. This study proposes a simple condensation model on the steam jets discharging into subcooled water from a single horizontal pipe for the prediction of the steam jet shapes. The analysis model was derived from the mass, momentum and energy equations as well as a thermal balance equation with condensing characteristics at the steam/water interface for the axi-symmetric coordinates. The extremely large heat transfer rate at the steam/water interface was reflected in the effective thermal conductivity estimated from the previous experimental results. The analysis results were compared with the experimental ones. The analysis model predicted that the steam jet shape (i. e. radius and length) was increasing as the steam mass flux and the pool temperature were increasing, which was similar in trend to that observed in the experiment.

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Neutron activation analysis: Modelling studies to improve the neutron flux of Americium-Beryllium source

  • Didi, Abdessamad;Dadouch, Ahmed;Jai, Otman;Tajmouati, Jaouad;Bekkouri, Hassane El
    • Nuclear Engineering and Technology
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    • v.49 no.4
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    • pp.787-791
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    • 2017
  • Americium-beryllium (Am-Be; n, ${\gamma}$) is a neutron emitting source used in various research fields such as chemistry, physics, geology, archaeology, medicine, and environmental monitoring, as well as in the forensic sciences. It is a mobile source of neutron activity (20 Ci), yielding a small thermal neutron flux that is water moderated. The aim of this study is to develop a model to increase the neutron thermal flux of a source such as Am-Be. This study achieved multiple advantageous results: primarily, it will help us perform neutron activation analysis. Next, it will give us the opportunity to produce radio-elements with short half-lives. Am-Be single and multisource (5 sources) experiments were performed within an irradiation facility with a paraffin moderator. The resulting models mainly increase the thermal neutron flux compared to the traditional method with water moderator.

Development of a Thermal Analysis Program for a Regenerative Cooling Passage of Liquid Rocket and Simulation of Turbulent Heat Transfer (액체로켓의 재생냉각채널에 대한 열해석 프로그램의 개발 및 난류열유동 해석)

  • Park T. S
    • Journal of computational fluids engineering
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    • v.8 no.3
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    • pp.56-65
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    • 2003
  • A numerical procedure for analyzing the heat transfer in a regenerative cooling passage of liquid rocket has been developed. The thermal analysis is based on the numerical model of Naraghi〔1〕. The thermodynamic and transport properties of the combustion gases are evaluated using the chemical equilibrium composition. The pressure and heat flux obtained by the isentropic relation are in good agreement with the result of Navier-Stokes equations. The effect of design parameters on heat transfer is addressed for the pressure loss and temperature variation. Also, their constraints in designing the cooling passage are recommended. Finally, in a heated rectangular duct, the effects of secondary flow on heat transfer are scrutinized by the nonlinear k- e -fu of Park et at.〔2〕.

Post Test Analysis of the Phebus FPT1 Experiment

  • Cho, Song-Won;Park, Jong-Hwa;Kim, Hee-Dong
    • Nuclear Engineering and Technology
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    • v.31 no.1
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    • pp.88-103
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    • 1999
  • The purposes of this study are to understand the severe accident phenomena, to establish the simulation method for the experimental test, and to assess the current models in MELCOR for future improvement. This paper presents the results of the PHEBUS FPT1 post test analysis using MELCOR computer code, version 1.8.4. The entire PHEBUS facility has been modeled; the core, the primary circuit including the steam generator, and the containment vessel. Both the thermal hydraulic and the fission product behavior have been investigated. The code simulation results of the thermal hydraulic behavior show good agreement with the experimental data, The fission product release and transport are calculated using the CORSOR models in MELCOR code and the results will be compared with the experiment when the experimental data are available.

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CANDU-6 Heat Transport System Stability Analysis With Canflex Fuel Bundle (CANFLEX 핵연료를 사용한 CANDU-6의 열수송계통 안정성 분석)

  • Shin, Jung-Cheol;Park, Ju-Hwan;Kim, Tae-Han;Suk, Ho-Chun
    • Nuclear Engineering and Technology
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    • v.27 no.3
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    • pp.358-373
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    • 1995
  • The Heat Transport system loop stability of CANDU-6 reactor using the CANFLEX fuel bundle was studied. The Thermal-hydraulic behavior of CANFLEX fuel bundle is similar to the conventional 37-element fuel bundle since the reactor power and the frictional pressure drop through the fuel channel is almost the same each other, Mounter the CANFLEX fuel bundle gives higher critical channel power and more homogeneous enthalpy distributions in the subchannels than 37-element fuel bundle. The SOPHT modelling or the CANFLEX fuel bundle and the Reactor outlet Header(ROH) interconnection line was made and the stability analysis response of Wolsong-1 reactor with CANFLEX fuel bundle was obtained. Without the ROH interconnection line the Heat Transport system loop using 43-element fuel bundle is unstable like the current 37-element fuel bundle. With the ROH interconnection line, however, the Heat Transport system is stable within $\pm$1% of nominal flow. In the Heat Transport system loop stability point of view for Wolsong-1 plant therefore, the CANFLEX fuel loading is considered to be acceptable.

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