The subcooled flow boiling critical heat fluxes (CHFs) are systematically measured by using the water loop installed the pressurizer to investigate the pressurization gas effect for the flow velocities (u = 4.0 to 13.3 m/s), the inlet subcoolings (ΔTsub,in = 70.08 to 145.57 K) and the inlet pressure (Pin = 740.67 to 975.43 kPa). The SUS304 tube of the inner diameter (d = 3 mm), the heated length (L = 66.5 mm) and L/d = 22.17 with the inner surface of rough finished was used. The CHF data under the pressurization by saturated vapor in a pressurizer were compared with the values calculated from the CHF correlations against outlet and inlet subcoolings based on the experimental data under the nitrogen (N2) gas pressure previously obtained. The CHFs for the dissolved oxygen concentration of 6.59, 4, 2, 1, 0.5, 0.0496 and 0.0265 ppm were systematically measured for the flow velocities (u = 4.0 to 13.3 m/s), the inlet subcoolings (ΔTsub,in = 137.49 to 153.87 K) and the inlet pressure (Pin = 762.97 to 975.78 kPa). And the CHFs for the test tube with the smooth finished inner surface were measured at the dissolved oxygen concentration of 0.1004 and 0.0413 ppm for the same experimental conditions. Influence of the inner surfaces of rough and smooth finished on the CHFs was clarified for low dissolved gas concentration.
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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
Influence of Dissolved Gas Concentration on Subcooled Flow Boiling Critical Heat Flux in Short Vertical Tube
Koichi Hata,
Koichi Hata
Kyoto University, Uji, Kyoto, Japan
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Hirokazu Komori,
Hirokazu Komori
Kyoto University, Uji, Kyoto, Japan
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Masahiro Shiotsu,
Masahiro Shiotsu
Kyoto University, Uji, Kyoto, Japan
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Nobuaki Noda
Nobuaki Noda
National Institute for Fusion Science, Toki, Gifu, Japan
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Koichi Hata
Kyoto University, Uji, Kyoto, Japan
Hirokazu Komori
Kyoto University, Uji, Kyoto, Japan
Masahiro Shiotsu
Kyoto University, Uji, Kyoto, Japan
Nobuaki Noda
National Institute for Fusion Science, Toki, Gifu, Japan
Paper No:
ICONE12-49194, pp. 505-514; 10 pages
Published Online:
November 17, 2008
Citation
Hata, K, Komori, H, Shiotsu, M, & Noda, N. "Influence of Dissolved Gas Concentration on Subcooled Flow Boiling Critical Heat Flux in Short Vertical Tube." 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. 505-514. ASME. https://doi.org/10.1115/ICONE12-49194
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