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TECHNICAL PAPERS: Evaporative Boiling and Condensation

Critical Heat Fluxes of Subcooled Water Flow Boiling Against Outlet Subcooling in Short Vertical Tube

[+] Author and Article Information
Koichi Hata

Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011, Japan

Masahiro Shiotsu

Dept. of Energy Science and Technology, Kyoto University, Gokasho, Uji, Kyoto 611-0011, Japan

Nobuaki Noda

National Institute for Fusion Science, 322-6, Oroshi-cho, Toki, Gifu 509-5292, Japan

J. Heat Transfer 126(3), 312-320 (Jun 16, 2004) (9 pages) doi:10.1115/1.1725101 History: Received July 22, 2003; Revised January 21, 2004; Online June 16, 2004
Copyright © 2004 by ASME
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References

Nariai, H., Inasaka, F., and Shimura, T., 1987, “Critical Heat Flux of Subcooled Flow Boiling in Narrow Tube,” Proceedings of the 1987 ASME-JSME Thermal Engineering Joint Conference, 5 , Hemisphere, New York, pp. 455–462.
Celata,  G. P., Cumo,  M., Mariani,  A., Nariai,  H., and Inasaka,  F., 1993, “Influence of Channel Diameter on Subcooled Flow Boiling at High Heat Fluxes,” Int. J. Heat Mass Transfer, 36(13), pp. 3407–3410.
Vandervort,  C. L., Bergles,  A. E., and Jensen,  M. K., 1994, “An Experiment Study of Critical Heat Flux in Very High Heat Flux Subcooled Boiling,” Int. J. Heat Mass Transfer, 37, Suppl. 1, pp. 161–173.
Mudawar,  I., and Bowers,  M. B., 1999, “Ultra-high Critical Heat Flux (CHF) for Subcooled Water Flow Boiling-I: CHF Data and Parametric Effects for Small Diameter Tubes,” Int. J. Heat Mass Transfer, 42, pp. 1405–1428.
Hata, K., Fukuda, K., Shiotsu, M., Sakurai, A., Noda, N., Motojima, O., and Iiyoshi, A., 1998, “Critical Heat Fluxes in Subcooled Boiling of Water Flowing Upward in a Vertical Tube for Wide Ranges of Liquid Velocity, Subcooling and Pressure,” Proceedings of 6th International Conference on Nuclear Engineering, Paper No. ICONE-6362, pp. 1–16.
Hata, K., Fukuda, K., Shiotsu, M., and Sakurai, A., 1999, “The Effect of Diameter on Critical Heat Flux in Vertical Heated Short Tubes of Various Inside Diameters Cooled with an Upward Flow of Subcooled Water,” Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics, pp. 1–20.
Sato, G., Hata, K., Shiotsu, M., and Noda, N., 2000, “Critical Heat Fluxes on Short Vertical Tube Inner Surface in Water Flowing Upward (Effect of tube Inner Diameter and Application to Thermal Analysis of Divertor Plate),” Proceedings of 8th International Conference on Nuclear Engineering, Paper No. ICONE-8126, pp. 1–12.
Hata, K., Sato, T., and Shiotsu, M., 2001, “Influence of Tube Length on Critical Heat Fluxes in Water Flowing Upward,” Proceedings of 9th International Conference on Nuclear Engineering, Paper No. ICONE-9569, pp. 1–12.
Hata, K., Tanimoto, T., Komori, H., Shiotsu, M., and Noda, N., 2003, “Thermal Analysis on Mono-Block Type Divertor Based on Subcooled Flow Boiling Critical Heat Flux Data against Inlet Subcooling in Short Vertical Tube,” Proceedings of 11th International Conference on Nuclear Engineering, Paper No. ICONE11-36118, pp. 1–10.
Nusselt, W., 1931, “Der Wärmeaustausch zweischen Wand und Wasser im Rohr,” Forsch. Geb. Ingenieurwes., 2 , p. 309.
Sakurai, A., Shiotsu, M., Hata, K., and Fukuda, K., 1999, “The Mechanisms of Flow Boiling Critical Heat Fluxes on a Vertical Cylinder and a Short Tube With Upward Flowing Highly Subcooled Water,” Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics, American Nuclear Society (ANS), Thermal Hydraulic Division, pp. 1–36.
Tong,  L. S., 1968, “Boundary-layer Analysis of the Flow Boiling Crisis,” Int. J. Heat Mass Transfer, 11, pp. 1208–1211.
Kutateladze, S. S., and Leont’ev, A. I., 1966, “Some Applications of the Asymptotic Theory of the Turbulent Boundary Layer,” Proceedings of the Third International Heat Transfer Conference, 3 , Am. Inst. Chem. Engrs., New York.
Kutateladze, S. S., 1966, “The Concept of a Fluid with Disappearing Viscosity and Some Problems of the Phenomenological Theory of Turbulence near the Wall,” Invited Lecture, Third International Heat Transfer Conference, Chicago, IL.
Tong, L. S., 1975, “A Phenomenological Study of Critical Heat Flux,” ASME Paper 75-HT-68, ASME, New York.
Celata,  G. P., Cumo,  M., and Mariani,  A., 1993, “Burnout in Highly Subcooled Water Flow Boiling in Small Diameter Tubes,” Int. J. Heat Mass Transfer, 36(5), pp. 1269–1285.
Celata,  G. P., Cumo,  M., Mariani,  A., Simoncini,  M., and Zummo,  G., 1994, “Rationalization of Existing Mechanistic Models for the Prediction of Water Subcooled Flow Boiling Critical Heat,” Int. J. Heat Mass Transfer, 37, Suppl. 1, pp. 347–360.
Hall,  D. D., and Mudawar,  I., 1999, “Ultra-high Critical Heat Flux (CHF) for Subcooled Water Flow Boiling-II: high-CHF Database and Design Equation,” Int. J. Heat Mass Transfer, 42, pp. 1429–1456.

Figures

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Schematic diagram of experimental apparatus
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Vertical cross-sectional view of the test section
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Measurement and data processing system
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Relationship between q and Ts−TL
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Typical photograph of the test tube burned out
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qcr,sub versus (ΔTsub,out)cal for an inner diameter of 3 mm with a heated length of 33 mm at an outlet pressure of 800 kPa
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qcr,sub versus (ΔTsub,out)cal for an inner diameter of 6 mm with a heated length of 66 mm at an outlet pressure of 800 kPa
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qcr,sub versus (ΔTsub,out)cal for an inner diameter of 9 mm with a heated length of 99 mm at an outlet pressure of 800 kPa
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qcr,sub versus (ΔTsub,out)cal for an inner diameter of 12 mm with a heated length of 133 mm at an outlet pressure of 800 kPa
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qcr,sub versus d at (ΔTsub,out)cal of 50 K with the flow velocity of 4.0, 6.9, 9.9 and 13.3 m/s at Pout of 800 kPa
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qcr,sub versus d at (ΔTsub,out)cal of 90 K with the flow velocity of 4.0, 6.9, 9.9, and 13.3 m/s at Pout of 800 kPa
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qcr,sub versus u at (ΔTsub,out)cal of 50 K with the inner diameter of 3, 6, 9, and 12 mm at Pout of 800 kPa
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qcr,sub versus u at (ΔTsub,out)cal of 90 K with the inner diameter of 3, 6, 9, and 12 mm at Pout of 800 kPa
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log(qcr,sub) versus log{(ΔTsub,out)cal} for an inner diameter of 9 mm with a heated length of 99 mm at Pout of 800 kPa
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qcr,sub versus L/d for an inner diameter of 9 mm at ΔTsub,out of 90 K with the flow velocity of 4.0, 6.9, 9.9, and 13.3 m/s
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qcr,sub versus L/d for an inner diameter of 12 mm at ΔTsub,out of 90 K with the flow velocity of 4.0, 6.9, 9.9, and 13.3 m/s
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Ratio of CHF data for the inner diameter of 3, 6, 9, and 12 mm to the values derived from the CHF correlation versus (ΔTsub,out)cal at outlet pressures of 159 kPa–1 MPa
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Comparison of CHF data for the inner diameter of 3 mm with Eq. (7) and Solutions of Celata et al. model
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Comparison of CHF data for the inner diameter of 6 mm with Eq. (7) and Solutions of Celata et al. model
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Comparison of CHF data for the inner diameter of 9 mm with Eq. (7) and Solutions of Celata et al. model
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Comparison of CHF data for the inner diameter of 12 mm with Eq. (7) and Solutions of Celata et al. model
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Comparison of Celata et al. data and our data with the values derived from the CHF correlation
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Comparison of Mudawar and Bowers data and our data with the values derived from the CHF correlation
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Comparison of Vandervort et al. data and our data with the values derived from the CHF correlation
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Time variations in Pipt,Popt,Pin,Pout,q and Ts for Pout=735 kPa,(ΔTsub,out)cal=91.49 K and u=13.3 m/s
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Time variations in ΔTsub,in,ΔTsub,out,(ΔTsub,out)cal,q and Ts for Pout=735 kPa,(ΔTsub,out)cal=91.49 K and u=13.3 m/s
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Relationship between measured outlet subcooling and calculated outlet subcooling for the inner diameter of 3, 6, 9, and 12 mm with L/d=11

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