• Title/Summary/Keyword: Thermal fluid analysis

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A Study on the Characteristic of Heat Transfer of PCM(Phase Change Material) at the Simultaneous Charging and Discharging Condition (동시 축·방열 조건에서 PCM의 열전달 특성에 관한 연구)

  • Lee, Donggyu;Park, Sechang;Chung, Dong-yeol;Kang, Cheadong
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.28 no.8
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    • pp.305-310
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    • 2016
  • A thermal storage systems was designed to correspond to the temporal or quantitative variation in the thermal energy demand, and most of its heat is stored using the latent and sensible heat of the heat storage material. The heat storage method using latent heat has a very complex phenomenon for heat transfer and thermal behavior because it is accompanied by a phase change in the course of heating/cooling of the heat storage material. Therefore, many studies have been conducted to produce an experimentally accessible as well as numerical approach to confirm the heat transfer and thermal behavior of phase change materials. The purpose of this study was to investigate the problems encountered during the actual heat transfer from an internal storage tank through simulation of the process of storing and utilizing thermal energy from the thermal storage tank containing charged PCM. This study used analysis methods to investigate the heat transfer characteristics of the PCM with simultaneous heating/cooling conditions in the rectangular space simulating the thermal storage tank. A numerical analysis was carried out in a state considering natural convection using the ANSYS FLUENT(R) program. The result indicates that the slope of the liquid-solid interface in the analysis field changed according to the temperature difference between the heating surface and cooling surface.

Basic Investigation into the Validity of Thermal Analysis of 18650 Li-ion Battery Pack Using CFD Simulation (CFD 해석을 적용한 18650 리튬-이온 배터리 팩의 열 해석 신뢰도 기초 분석)

  • SIM, CHANG-HWI;KIM, HAN-SANG
    • Journal of Hydrogen and New Energy
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    • v.31 no.5
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    • pp.489-497
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    • 2020
  • The Li-ion battery is considered to be one of the potential power sources for electric vehicles. In fact, the efficiency, reliability, and cycle life of Li-ion batteries are highly influenced by their thermal conditions. Therefore, a novel thermal management system is highly required to simultaneously achieve high performance and long life of the battery pack. Basically, thermal modeling is a key issue for the novel thermal management of Li-ion battery systems. In this paper, as a basic study for battery thermal modeling, temperature distributions inside the simple Li-ion battery pack (comprises of nine 18650 Li-ion batteries) under a 1C discharging condition were investigated using measurement and computational fluid dynamics (CFD) simulation approaches. The heat flux boundary conditions of battery cells for the CFD thermal analysis of battery pack were provided by the measurement of single battery cell temperature. The temperature distribution inside the battery pack were compared at six monitoring locations. Results show that the accurate estimation of heat flux at the surface of single cylindrical battery is paramount to the prediction of temperature distributions inside the Li-ion battery under various discharging conditions (C-rates). It is considered that the research approach for the estimation of temperature distribution used in this study can be used as a basic tool to understand the thermal behavior of Li-ion battery pack for the construction of effective battery thermal management systems.

Thermal-Mixing Analyses for Safety Injection at Partial Loop Stagnation of a Nuclear Power Plant

  • Hwang, Kyung-Mo;Kim, Kyung-Hoon
    • Journal of Mechanical Science and Technology
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    • v.17 no.9
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    • pp.1380-1387
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    • 2003
  • When a cold HPSI (High pressure Safety Injection) fluid associated with an overcooling transient, such as SGTR (Steam Generator Tube Rupture), MSLB (Main Steam Line Break) etc., enters the cold legs of a stagnated primary coolant loop, thermal stratification phenomena will arise due to incomplete mixing. If the stratified flow enters the downcomer of the reactor pressure vessel, severe thermal stresses are created in a radiation embrittled vessel wall by local overcooling. As general thermal-hydraulic system analysis codes cannot properly predict the thermal stratification phenomena, RG 1.154 requires that a detailed thermal-mixing analysis of PTS (pressurized Thermal Shock) evaluation be performed. Also. previous PTS studies have assumed that the thermal stratification phenomena generated in the stagnated loop side of a partially stagnated primary coolant loop are neutralized in the vessel downcomer by the strong flow from the unstagnated loop. On the basis of these reasons, this paper focuses on the development of a 3-dimensional thermal-mixing analysis model using PHOENICS code which can be applied to both partial and total loop stagnated cases. In addition, this paper verifies the fact that, for partial loop stagnated cases, the cold plume generated in the vessel downcomer due to the thermal stratification phenomena of the stagnated loop is almost neutralized by the strong flow of the unstagnated loop but is not fully eliminated.

Selection of Working fluid for the Organic Rankine Cycle to Utilize Low-Temperature Waste Heat (저온 폐열을 이용하기 위한 유기랭킨 사이클의 작동유체 선정에 관한 연구)

  • Cho, Soo-Yong;Cho, Chong-Hyun
    • New & Renewable Energy
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    • v.10 no.4
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    • pp.36-46
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    • 2014
  • Low-grade heats are wasted even though an amount of their energy is huge. In the small and medium industrial complex sites, large amount of low-grade thermal energy generated during the manufacturing process is wasted if it is not used directly for building heating or air-conditioning. In order to utilize this waste thermal energy more efficiently, organic Rankine cycle (ORC) was adopted. The range of operating temperature of ORC was set to $60^{\circ}C$ from $30^{\circ}C$ applicable low-temperature waste heat. A study was conducted to select an appropriate organic working fluid based on these operating conditions. More than 60 working fluids were screened. Eleven working fluids were selected based on the requirements as working fluid for ORC such as environmentally friendly, safety, and good operation on the expander. Finally, six working fluids were selected by considering the operating temperature ranges. Then, a cycle analysis was conducted with these six working fluids. As a results, R-245fa and R-134a appeared as appropriate working fluids for ORC operating at low-temperature condition based on the system efficiency and the turbine output power.

Influences of Body Fluid on Crossed Thermal Effects (체수분이 교차성 열효과에 미치는 영향)

  • Lee, Sang-Un;Kanazawa, Yoshinori;Kim, Yong-Kwon
    • Journal of Korean Physical Therapy Science
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    • v.9 no.2
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    • pp.151-157
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    • 2002
  • This study examined the changes in body temperature through conductive heat applied to the body and clarified the influences of body fluid on the thermal effects. Body fluid was measured using the Segmental Bioelectrical Impedance Analysis method. The subjects consisted of 13 men and 14 women. TBW was 37.56 (4.35 L for men and 29.93 (3.12 L for women, with the former being significantly (p<0.01) higher. The amount of body fluid in the right and left legs was 6.46 (0.83 L and 6.39 (0.86 L for men and 4.78 (0.49 L and 4.78 (0.49 L for women, respectively, with men's values being significantly (p<0.01) higher than women's on both the right and left sides. The maximal change in the surface temperature was 33.93 (0.61(C at the start of a warm bath to 3407 (0.61(C after 14 min for men. In contrast, the maximal change was 33.38 (0.99(C at the start to 33.73 (0.86(C after 18 min for women. For the other sites, the maximal temperature in Depths 1 and 2 was attained earlier for men than for women. The decrease in body temperature after the end of warming was more remarkable for men. Men had fluid with a higher conductivity than women, indicating influences of body fluid on the changes in body temperature. There were few changes in body composition with a partial bath having a crossed effect, indicating that this is a safe therapeutic method for elderly people.

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Evaluation of Ground Thermal Conductivity by Performing In-Situ Thermal Response test (TRT) and CFD Back-Analysis (현장 열응답 시험(TRT)과 CFD 역해석을 통한 지반의 열전도도 평가)

  • Park, Moonseo;Lee, Chulho;Park, Sangwoo;Sohn, Byonghu;Choi, Hangseok
    • Journal of the Korean Geotechnical Society
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    • v.28 no.12
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    • pp.5-15
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    • 2012
  • In this study, a series of CFD (Computational Fluid Dynamics) numerical analyses were performed in order to evaluate the thermal performance of six full-scale closed-loop vertical ground heat exchangers constructed in a test bed located in Wonju. The circulation HDPE pipe, borehole and surrounding ground formation were modeled using FLUENT, a finite-volume method (FVM) program, for analyzing the heat transfer process of the system. Two user-defined functions (UDFs) accounting for the difference in the temperatures of the circulating inflow and outflow fluid and the variation of the surrounding ground temperature with depth were adopted in the FLUENT model. The relevant thermal properties of materials measured in laboratory were used in the numerical analyses to compare the thermal efficiency of various types of the heat exchangers installed in the test bed. The simulation results provide a verification for the in-situ thermal response test (TRT) data. The CFD numerical back-analysis with the ground thermal conductivity of 4 W/mK yielded better agreement with the in-situ thermal response tests than with the ground thermal conductivity of 3 W/mK.

Thermal-fluid-structure coupling analysis on plate-type fuel assembly under irradiation. Part-II Mechanical deformation and thermal-hydraulic characteristics

  • Li, Yuanming;Ren, Quan-yao;Yuan, Pan;Su, Guanghui;Yu, Hongxing;Zheng, Meiyin;Wang, Haoyu;Wu, Yingwei;Ding, Shurong
    • Nuclear Engineering and Technology
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    • v.53 no.5
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    • pp.1556-1568
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    • 2021
  • The plate-type fuel assembly adopted in nuclear research reactor suffers from complicated effect induced by non-uniform irradiation, which might affect stress conditions, mechanical behaviors and thermal-hydraulic performance of the fuel assembly. This paper is the Part II work of a two-part study devoted to analyzing the complex unique mechanical deformation and thermal-hydraulic characteristics for the typical plate-type fuel assembly under irradiation effect, which is on the basis of developed and verified numerical thermal-fluid-structure coupling methodology under irradiation in Part I of this work. The mechanical deformation, thermal-hydraulic performance and Mises stress have been analyzed for the typical plate-type fuel assembly consisting of support plates under non-uniform irradiation. It was interesting to observe that: the plate-type fuel assembly including the fuel plates and support plates tended to bend towards the location with maximum fission rate; the hot spots in the fuel foil appeared at the location with maximum thickness increment; the maximum Mises stress of fuel foil was located at the adjacent location with the maximum plate thickness increment et al.

Analysis of heat-loss mechanisms with various gases associated with the surface emissivity of a metal containment vessel in a water-cooled small modular reactor

  • Geon Hyeong Lee;Jae Hyung Park;Beomjin Jeong;Sung Joong Kim
    • Nuclear Engineering and Technology
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    • v.56 no.8
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    • pp.3043-3066
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    • 2024
  • In various small modular reactor (SMR) designs currently under development, the conventional concrete containment building has been replaced by a metal containment vessel (MCV). In these systems, the gap between the MCV and the reactor pressure vessel is filled with gas or vacuumed weakly, effectively suppressing conduction and convection heat transfer. However, thermal radiation remains the major mode of heat transfer during normal operation. The objective of this study was to investigate the heat-transfer mechanisms in integral pressurized water reactor (IPWR)-type SMRs under various gas-filled conditions using computational fluid dynamics. The use of thermal radiation shielding (TRS) with a much lower emissivity material than the MCV surface was also evaluated. The results showed that thermal radiation was always the dominant contributor to heat loss (48-97%), while the conjugated effects of the gas candidates on natural convection and thermal radiation varied depending on their thermal and radiative properties, including absorption coefficient. The TRS showed an excellent insulation performance, with a reduction in the total heat loss of 56-70% under the relatively low temperatures of the IPWR system, except for carbon dioxide (13%). Consequently, TRS can be utilized to enhance the thermal efficiency of SMR designs by suppressing the heat loss through the MCV.

CFD Analysis for Thermal Mixing in a Subcooled Water during Steam Jet Discharge (증기제트 방출시 과냉각수조 내의 열혼합 현상 CFD 해석)

  • Kang, Hyung-Seok;Song, Chul-Hwa
    • 유체기계공업학회:학술대회논문집
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    • 2006.08a
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    • pp.513-514
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    • 2006
  • A CFD analysis for a thermal mixing experiment during steam jet discharge was performed to develop the analysis methodology for the thermal mixing between steam and subcooled water and to find the optimized numerical method. In the CFD analysis, the steam condensation phenomena by a direct contact was modelled by the so-called condensation region model. The comparison of the CFD results with the test data showed a good agreement as a whole, but a small temperature difference was locally found at some locations. However, the commercial CFD code of CFX4.4 together with the condensation region model can simulate the thermal mixing behaviour reasonably well when a sufficient number of mesh distribution and a proper numerical method are adopted

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Finite Element Analysis of Thermal Fatigue Safety for a Heavy-Duty Diesel Engine (대형디젤엔진의 열적 피로안전도 분석을 위한 유한요소해석)

  • 조남효;이상업;이상규;이상헌
    • Transactions of the Korean Society of Automotive Engineers
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    • v.12 no.1
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    • pp.122-129
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    • 2004
  • Finite element analysis was performed to analyze structural safety of a new heavy-duty direct injection diesel engine. A half section of the in-line 6-cylinder engine was selected as a computational domain. A mapping method was used to project heat transfer coefficients from CFD results of engine coolant flow onto the FE model. The accurate setting of thermal boundary condition on the FE model was expected to result in improved prediction of temperature, cylinder bore distortion, and stresses. Characteristics of high cycle fatigue were investigated by assuming the engine was operated under the following five loading conditions repeatedly; assembly force, assembly force with thermal loading, alternating maximum gas pressure loading at each cylinder combined with assembly force and thermal loading. Distribution of fatigue safety factor was calculated by using it Haigh diagram in which the maximum and the minimum stresses were selected from the five loading cases.