Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Critical Heat Flux in Uniformly Heated Vertical Annulus Under a Wide Range of Pressures 0.57 to 15.0 MPa

  • Published : 2000.04.01
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Abstract

The critical heat flux (CHF）experiments have been carried out in a wide range of pressures for an internally heated vertical annulus. The experimental conditions covered ranges of pressures from 0.57 to 15.01 MPa, mass fluxes of 0 kg/$m^2$s and from 200 to 650 kg/$m^2$s, and inlet subcoolings from 85 to 413 kJ/kg. The characteristics of the present data and the effect of pressure on CHF are discussed. Most of the CHFs were identified to dryout of the liquid film in the annular or annular-mist flow. For the mass flux of 200 kg/$m^2$s, there were the indications that the CHF occurred at the transition from annular to annular-mist How in the pressure range of 3~10 MPa. For the mass fluxes of 550 and 650 kg/$m^2$s, the CHFs had a maximum value at a pressure of 2~3 MPa, and the pressure at the maximum CHF values had a trend moving toward the pressure at the peak value of pool boiling CHF as the mass flux decreased. The CHF data under a zero mass flux condition indicate that both the effects of pressure and inlet subcooling on the CHF were smaller, compared with those on the CHF with net water upward flow.

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References

  1. E. Janssen and J. A. Kervinen, 'Burnout conditions for single rod in annular geometry, water at 600 to 1400 psia,' general Electric Company, Atomic Energy Commisson, USA, GEAP-3899 (1963)
  2. K. M. Becker et al., 'Burnout data for flow of boiling water in vertical round duct, annuli, and rod clusters,' Aktiebolaget Atomenergi, Stocholm, Sweden, AE-177 (1965)
  3. P. G. Barnett, 'A Correlation of burnout data for uniformly heated annuli and its use for predicting burnout in uniformly heated rod bundles,' AEEW-R463 (1966)
  4. K. Mishma and M. Ishii, 'Experimental study on natural convection boiling burnout in annulus,' Proceeding of the 7th INternational Heat Transfer Conference, Munchen, 4, 309-314 (1982)
  5. J. T. Rogers et al., 'Flow boiling critical heat fluxes for water in a vertical annulus at low pressure and velocities,' Proceeding of the 7th International Heat Transfer Conference, Munchen, 4, 339-344 (1982)
  6. M. S. El-Genk et al., 'Esperimental studies of critical heat flux for low flow of water in vertical annuli at near atmospheric pressure,' Int. J. Heat Mass Transfer, 31, 2291-2304 (1988) https://doi.org/10.1016/0017-9310(88)90161-5
  7. J. W. Park et al., 'Critical heat flux and flow pattern for water flow in annular goemetry,' Nucl. Eng. Des., 172, 137-155 (1994) https://doi.org/10.1016/S0029-5493(97)00032-0
  8. H. Kumamaru et al., 'Critical heat flux for annulus under high-pressure, low-flow and mixed inlet conditions,' J. Nucl. Sci. Tech., 27[1], 68-80 (1990)
  9. ANSI/ASME PTC 19.1 ,'ASME performance test codes, supplement on istrument and apparatus, part 1, measurement uncertainty,' (1985)
  10. M. Mishima and H. Nishihara, 'Effect of channel geometry on critical heat flus for low pressure water,' Int J. Heat Mass Trasfer, 30, 1169-1182 (1987) https://doi.org/10.1016/0017-9310(87)90046-9
  11. Y. Katto and T. Hirao, 'Critical heat flus of counter-flow boiling in u uniformely heated vertical tube with a closed bottom,' Int. J. Heat Mass Trasfer, 34, 993-1001 (1991) https://doi.org/10.1016/0017-9310(91)90010-C
  12. D. H. Hwang and S. H. Chang, 'Development of a phenomenological model for the prodiction of dryout locations under flooding-limited critical heat flux conditions,' Nucl. Eng. Des., 148, 475-486 (1994) https://doi.org/10.1016/0029-5493(94)90127-9
  13. G. B. Wallis, 'One-dimensional two-phase flow,' McGraw-Hill Book Company, 336-342 (1969)
  14. K. Mishima and M. Ishii, 'Flow regime transition criteria for upwark two-phase flow in vertical tube,' Int. J. Heat Mass Transfer, 27, 723-737 (1984) https://doi.org/10.1016/0017-9310(84)90142-X
  15. F. H. Bowditch and D. J. Mogford, 'An experimental and analytical study of fluid flow and critical heat flus in PWR fuel elements,' AEE Winfrith, AEEW-R2050 (1987)
  16. V. G. Morozov, 'New experimental data on critical heat loads at boiling of liquids on a submerged heating surface,' Int. J. Heat Mass Trasfer, 5, 661-666 (1962) https://doi.org/10.1016/0017-9310(62)90088-1