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Study on dryout point in vertical narrow annuli 被引量:1

Study on dryout point in vertical narrow annuli
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摘要 Prediction of dryout point is experimentally investigated with deionized water upflowing through narrow annular channel with 1.0 mm and 1.5 mm gap respectively. The annulus with narrow gap is bilaterally heated by AC current power supply. The experimental conditions covered a range of pressure from 0.8 to 3.5 MPa, mass flux of 26.6 to 68.8 kg?m-2?s-1 and wall heat flux of 5 to 50 kW?m-2. The location of dryout is obtained by observing a sudden rise in surface temperature. Kutateladze correlation is cited and modified to predict the location of dryout and proved to be not a proper one. Considering in detail the effects of geometry of annuli, pressure, mass flux and heat flux on dryout, an empirical correction is finally developed to predict dryout point in narrow annular gap under low flow condition, which has a good agreement with experimental data. Prediction of dryout point is experimentally investigated with deionized water upflowing through narrow annular channel with 1.0 mm and 1.5 mm gap respectively. The annulus with narrow gap is bilaterally heated by AC current power supply. The experimental conditions covered a range of pressure from 0.8 to 3.5 MPa, mass flux of 26.6 to 68.8 kg?m-2?s-1 and wall heat flux of 5 to 50 kW?m-2. The location of dryout is obtained by observing a sudden rise in surface temperature. Kutateladze correlation is cited and modified to predict the location of dryout and proved to be not a proper one. Considering in detail the effects of geometry of annuli, pressure, mass flux and heat flux on dryout, an empirical correction is finally developed to predict dryout point in narrow annular gap under low flow condition, which has a good agreement with experimental data.
出处 《Nuclear Science and Techniques》 SCIE CAS CSCD 2005年第1期53-58,共6页 核技术(英文)
关键词 窄环轨道 双侧加热 烘干点 临界质量 环流 Narrow annular channel, Bilaterally heating, Dryout point, Critical quality, Annular flow
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  • 1Tomio Okawa. Akio Kotani. Isao Kataoka. Prediction of dryout heat flux in vertical round tubes with uniform and non-uniform heating, The 10th international topic meeting on nuclear reactor thermal hydraulics. October, 2003,Seoul, Korea.
  • 2Cheng J C, Ozkaynak F T; Sundaram R K. Nuclear Engineering and Design, 1979, 51: 143-155.
  • 3Chen Zhihang, Cao Bolin. Two phase flow and heat transfer (in Chinese). Beijing: Mechanical Industry Press,1983.
  • 4Knudsen J G, Katz D L. Fluid dynamics and heat transfer.New York: McGraw-Hill, 1958: 186-195.
  • 5Lee Kwang-Won, Balk Se-Jin, Ro Tae-Sun. Nucl Eng Design, 2000. 200: 69-81.
  • 6Levy S, Healzer J M, Abdollahian D. Nucl Eng Design,1981, 65: 131-140.
  • 7Doerffer S, Groeneveld D C, Cheng S C. Nucl Eng Design, 1997, 177: 105-120.
  • 8Katto Y. International Journal of Heat Mass Transfer.1984, 27:83-891.
  • 9Venkateswararao P, Semiat R, Dukler A E, International Journal of Multiphase Flow, 1982, 8: 509-524.
  • 10David D H, Issam M. International Journal of Heat Mass Transfer, 2000. 43: 2573-2604.

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