Journal of Mechanical Science and Technology

The Korean Society of Mechanical Engineers (대한기계학회)
권호 표지

An Experimental Study of Critical Heat Flux in Non-uniformly Heated Vertical Annulus under Low Flow Conditions

  • Published : 2003.08.01
Download PDF
⟨ Previous Next ⟩

Abstract

An experimental study on critical heat flux (CHF) has been performed in an internally heated vertical annulus with non-uniform heating. The CHF data for the chopped cosine heat flux have been compared with those for uniform heat flux obtained from the previous study of the authors, in order to investigate the effect of axial heat flux distribution on CHF. The local CHF with the parameters such as mass flux and critical quality shows an irregular behavior. However, the total critical power with mass flux and the average CHF with critical quality are represented by a unique curve without the irregularity. The effect of the heat flux distribution on CHF is large at low pressure conditions but becomes rapidly smaller as the pressure increases. The relationship between the critical quality and the boiling length is represented by a single curve, independent of the axial heat flux distribution. For non-uniform axial heat flux distribution, the prediction results from Doerffer et al.'s and Bowling's CHF correlations have considerably large errors, compared to the prediction for uniform heat flux distribution.

Keywords

References

  1. ANSI/ASME PTC 19.1 , 1985, 'ASME Performance Test Codes, Supplement on Instruments and Apparatus, Part 1, Measurement Uncertainty,' ASME
  2. Bergles, A. E., Collier, J. G., Delhaye, J. M., Hewitt, G. F. and Mayinger, F., 1981, 'Two-Phase Flow and Heat Transfer in the Power and Process Industries,' Hemisphere Publishing corporation, pp. 262-265
  3. Bowring, R. W., 1977, 'A new Mixed Flow Cluster Dryout Correlation for Pressure in the Range $0.6-15.5 MN/m^2$ (90-2250 psia) - for use in a Transient Blowdown Code,' Heat and Fluid Flow in Water Reactor Safety, Inst. of Mechanical Engineers
  4. Chun, S. Y., Chung, H. J., Hong, S. D., Yang, S. K. jand Chung. M. K., 2000, 'Critical Heat Flux in Uniformly Heated Vertical Annulus Under a Wide Range of Pressures 0.57 to 15.0 MPa,' Journal of the Korean Nuclear Society, Vol. 32, No. 2m pp. 128-141
  5. Chun, S. Y., Chung, H. J., Moon, S. K., Yang,S. K., Chung. M. K., Schoesse, T. and Aritomi, M., 2001, 'Effect of Pressure on Critical Heat Flux in Uniformly Heated Vertical Annulus under low flow conditions,' Nucl. Eng. Des. Vol. 203, pp. 159-174 https://doi.org/10.1016/S0029-5493(00)00307-1
  6. Collier, J. G. and Thome, J. R., 1994, 'Convective Boiling and Condensation, 3rd Edition,' Oxford University Press, pp. 375-382
  7. Doerffer, S., Groeneveld, D. C., Chemg, S. C. and Rudzinski, K. F., 1994, 'A comparison of critical heat flux in tubes and annuli,' Nucl. Eng. Des., Vol. 149, pp. 167-175 https://doi.org/10.1016/0029-5493(94)90283-6
  8. El-Cenk, M. S., Haynes, S. J. and Kim, S. H., 1988, 'Experimental Studies of Critical Heat Flux for Low Flow of Water in Vertical Annuli at Near Atmospheric Pressure,' Int. J. Heat Mass Transfer, Vol. 31, pp. 2291-2304 https://doi.org/10.1016/0017-9310(88)90161-5
  9. Croeneveld, D. C., Cheng, S. C. and Doan,T., 1986, '1986 AECL-UO Critical Heat Flux Look-Up Table,' Heat Transfer Engineering, Vol. 7 [1-2], pp. 46-62 https://doi.org/10.1080/01457638608939644
  10. Groeneveld, D. C., Leung, K. H., Kirillov, P. L., Bobkov, V. P., Smogalev, I. P., Huang, X. C. and Royer, E., 1996, 'The 1995 Look-Up Table for Critical Heat Flux inTubes,' Nucl. Eng. Des., Vol. 1-23 https://doi.org/10.1016/0029-5493(95)01154-4
  11. Mishima, K., and Ishii, M., 1982, 'Experimental Study on Natural Convection Boiling Burnout in Annulus,' Proceeding of the 7th International Heat Transfer Conference, Munchen, Vol. 4, pp. 309-314
  12. Mishima, M. and Nishihara, H., 1987, 'Effect of Channel Geometry on Critical Heat Flux for Low Pressure Water,' Int. J. Heat Mass Transfer, Vol. 30, pp. 1169-1182 https://doi.org/10.1016/0017-9310(87)90046-9
  13. Park, J. W., Baek, W. P. and Chang, S. H., 1997, 'Critical Heat Flux and Flow Pattern for Water Flow in Annular Geometry,' duddlNucl. Eng. Des., Vol. 172, pp. 137-155 https://doi.org/10.1016/S0029-5493(97)00032-0
  14. Rogers, J. T., Salcudean, M. and Tahir, A. E., 1982, 'Flow Boiling Critical Heat Fluxes for Water in a Vertical Annulus at Low Preessure and Velocities,' Proceeding of the 7th International Heat Transfer Conference, Munchen, Vol. 4, pp. 339-344
  15. Rosal, E. R., Cermak, J. O., Tong, L. S., Casterline, J. E.,Kokolis, S. and Matzner, B., 1974, 'High Pressure Rod Bundle DNB Data with Axially Non-Uniform Heat Flux,' Nucl. Eng. Des., Vol. 31, pp. 1-22 https://doi.org/10.1016/0029-5493(74)90129-0
  16. Schoesse, T., Aritomi, M., Kataoka, Y., Lee, S. R., Yoshioka, Y. and Chung,M. K., 1997, 'Critical Heat Flux in a Vertical Annulus Under Low Upward Flow and Near Atmospheric Pressure,' J. Nucl. Sci. Technol., Vol. 34, No. 6, pp. 559-570 https://doi.org/10.3327/jnst.34.559
  17. Todreas, N. E. and Rohsenow, W. M., 1966, 'The Effect of Axial Heat Flux Distribution on Critical Heat Flux in Annular, Two Phase Flow,' Proceeding of the 3rd International Heat Transfer Conference, Chicago, Vol. 3, pp. 78-85
  18. Tong, L. S., Currin, H. B., Larsen, P. S.and Smith, O. G., 1965, 'Influence of Axially Non-Uniform Heat Flux on DNB,' AIChE Preprint 17, 8th National Heat Transfer Conference, Los Angeles
  19. Tong, L. S., 1966, 'Prediction of Departure From Nucleate Boiling for an Axially Non-Uniform Heat Flux Distribution,' Journal of Nuclear Energy, Vol. 21. pp. 241-248 https://doi.org/10.1016/S0022-3107(67)90054-8