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Experimental and numerical investigation of heat transfer and pressure drop in staggered arrangement helically finned-tube bundle

  • Xi'an Jiaotong University

科研成果: 书/报告/会议事项章节会议稿件同行评审

2 引用 (Scopus)

摘要

In a new pressurized water reactor nuclear power plant, the heat exchange tube bundle of the Moisture Separator Reheater (MSR) is a new designed staggered arrangement low helically finned-tube bundle. To investigation the thermal hydraulic characteristics of the Reheater part of MSR, the tube bundle test section was designed by using prototype tube and prototype arrangement of the new designed MSR. The experiment was carried out on the test section with steam cross-flowing outside the horizontal tube bundle, same conditions as MSR' operation designing, and electrical heating in the tubes simulating the condensation heat release of the two phase-flow inside. A lot of experimental data on heat transfer and pressure drop were obtained in a broad experiment parameters range of wall heat flux density and steam temperature, pressure and Reynolds number. Based on the present data, empirical average heat transfer correlation and friction factor correlation were proposed for the outside average heat transfer and pressure drop. Comparisons and analysis between these experimental results and some of other investigations were made. The conclusions of this experimental investigation were given. The results are very useful to the design of the heat exchange tube bundle in the MSR, and the validations of the new design. However, experimental studies cannot adequately reveal the detail of flow characteristics, and suitable correlations for this fin geometry are very rare. Thus, numerical simulations should be performed to make up for the deficiency. To perform a detail understanding of the heat transfer and pressure drop characteristics, a three-dimensional geometry was carefully constructed and a fine mesh was generated. The flow across the tubes was assumed to be a steady, incompressible turbulent flow. RNG based k-ϵ turbulence model was chosen in the simulation. Nusselt number and Euler number of a wide range of Reynolds numbers (based on the steam velocity through the minimum flow area) from 1 × 104 to 8 × 104 were calculated by the CFD software ANSYS Fluent. The numerical results were compared with experiment results of the same fin geometry and tube configuration. Also, local flow behavior and local temperature distribution were obtained to show the detail flow features and heat transfer. The velocity and temperature distribution near the fin surface were discussed.

源语言英语
主期刊名International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
出版商American Nuclear Society
8643-8656
页数14
ISBN(电子版)9781510811843
出版状态已出版 - 2015
活动16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, 美国
期限: 30 8月 20154 9月 2015

丛书

姓名International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
10

会议

会议16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
国家/地区美国
Chicago
时期30/08/154/09/15

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