An Experimental Study of Critical Heat Flux in Non-uniformly Heated Vertical Annulus under Low Flow Conditions |
Chun, Se-Young
(Korea Atomic Energy Research Institute)
Moon, Sang-Ki (Korea Atomic Energy Research Institute) Baek, Won-Pil (Korea Atomic Energy Research Institute) Chung, Moon-Ki (Korea Atomic Energy Research Institute) Masanori Aritomi (Research Laboratory for Nuclear Reactor, Tokyo Institute of Technology,) |
1 | ANSI/ASME PTC 19.1 , 1985, 'ASME Performance Test Codes, Supplement on Instruments and Apparatus, Part 1, Measurement Uncertainty,' ASME |
2 | Bowring, R. W., 1977, 'A new Mixed Flow Cluster Dryout Correlation for Pressure in the Range (90-2250 psia) - for use in a Transient Blowdown Code,' Heat and Fluid Flow in Water Reactor Safety, Inst. of Mechanical Engineers |
3 | 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 |
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 과학기술학회마을 |
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 DOI ScienceOn |
6 | Collier, J. G. and Thome, J. R., 1994, 'Convective Boiling and Condensation, 3rd Edition,' Oxford University Press, pp. 375-382 |
7 | 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 DOI ScienceOn |
8 | 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 DOI ScienceOn |
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 DOI ScienceOn |
10 | 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 DOI ScienceOn |
11 | 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 |
12 | 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 |
13 | 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 |
14 | 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 DOI ScienceOn |
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 DOI ScienceOn |
16 | 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 DOI ScienceOn |
17 | 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 DOI ScienceOn |
18 | 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 |
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 DOI ScienceOn |