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 annular 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 from 26.6 to 68.8 kg/m2 s and wall heat flux from 5.0 to 50.0 kW/m2. The location of dryout is obtained by observing a sudden rise in surface temperature, Kutateladze correlations is cited, however proved to be not a proper one for annuli gap and modified to predict the location of dryout. Considering in detail the effects of the 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.
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12th International Conference on Nuclear Engineering
April 25–29, 2004
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4689-X
PROCEEDINGS PAPER
Experimental Study on Dryout Point in Vertical Narrow Annulus Under Low Flow Conditions
Wenxi Tian,
Wenxi Tian
Xi’an Jiaotong University, Xi’an, China
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Aye Myint,
Aye Myint
Xi’an Jiaotong University, Xi’an, China
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Zhihui Li,
Zhihui Li
Xi’an Jiaotong University, Xi’an, China
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Suizheng Qiu,
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, China
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G. H. Su,
G. H. Su
Xi’an Jiaotong University, Xi’an, China
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Dounan Jia
Dounan Jia
Xi’an Jiaotong University, Xi’an, China
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Wenxi Tian
Xi’an Jiaotong University, Xi’an, China
Aye Myint
Xi’an Jiaotong University, Xi’an, China
Zhihui Li
Xi’an Jiaotong University, Xi’an, China
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, China
G. H. Su
Xi’an Jiaotong University, Xi’an, China
Dounan Jia
Xi’an Jiaotong University, Xi’an, China
Paper No:
ICONE12-49351, pp. 643-648; 6 pages
Published Online:
November 17, 2008
Citation
Tian, W, Myint, A, Li, Z, Qiu, S, Su, GH, & Jia, D. "Experimental Study on Dryout Point in Vertical Narrow Annulus Under Low Flow Conditions." Proceedings of the 12th International Conference on Nuclear Engineering. 12th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 25–29, 2004. pp. 643-648. ASME. https://doi.org/10.1115/ICONE12-49351
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