The effect of a spacer grid mixing vane on the critical heat flux for a rod bundle

International Journal of Fluid Mechanics Research

Volumn 25, Issue 1-3, 1998, Pages 230-242

  Park, J H ^a   Lee, J S ^a   Gros D'Aillon, M ^b  

^a Seoul National University   (South Korea)

^b CEA GRENOBLE   (France)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 11544315165     PISSN: 21525102     EISSN: 21525110     Source Type: Journal    
DOI: 10.1615/interjfluidmechres.v25.i1-3.200     Document Type: Article

References (14)

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2. Rosal, E. R. et al., High Pressure Rod Bundle DNB Data with Axially Non-Uniform Heat Flux, Nucl. Eng. and Des., 1974, 31, pp. 1-20.
3. Katsaounis, A., Fulfs, H., and Stein, M., Effects of the Core Grids on the Burnout, GKSS 77/E/22, 1977.
4. Ryabov, A. N. et al., Boiling Crisis and Pressure Drop in Rod Bundles with Heat Transfer Enhancement Devices, Heat Transfer-Soviet Research, 1977, 9, No. 1, pp. 112-122.
5. Aden, V. G. et al., The Study of Heat Exchange Enhancement in Models of Fuel Elements Bundles at the Coolant Boiling, 6th Int. Heat Transfer Conf., 1978, Vol. 5, pp. 41-44.
6. Yao, S. C., Hochreiter, L. E., and Leech, W. J., Heat Transfer Augmentation in Rod Bundles Near Grid Spacers, Trans. ASME, 1982, Feb., 104.
7. Nissely, M. E. and Knott, R. P., The Effects of Mixing Vaned Grids on CHF Performance, ANS Annual Meeting, New Orleans, 1984, June, 3-7, p. 842.
8. Suchy, P. and Ulrych, G., Comparison of CHF-Results for Non-Mixing and Mixing Vaned Grids, Presented at the European Two-Phase Flow Group Meeting, Machwood Engineering Lab., England, 1985.
9. Stewart, C. W. et al., COBRA-IV-I, An Interim Version of COBRA for Thermal-Hydraulic Analysis of Rod Bundle Nuclear Fuel Elements and Cores, BNWL, 1962.
10. Janssen, E. et al., Sixteen-Rod Heat Flux Investigation, Steam-Water at 600 to 1250 psia, Two-Phase Flow and Heat Transfer in Rod Bundles, ASME Winter Annual Meeting, 1969, pp. 74-79.
11. Lahey, R. T., Jr., Shiralkar, B. S., and Radcliffe, D. W., Two-Phase Flow and Heat Transfer in Multirod Geometries: Subchannel and Pressure Drop Measurements in a Nine-Rod Bundle for Diabatic and Adibatic Conditions, GEAP-13049, 1970.
12. Reddy, D. G. and Fighetti, C. F., Evaluation of Turbulent Mixing Parameter in Nuclear Fuel Rod Bundles, ASME & JSME Thermal Engineering Joint Conference Proceedings, Hawaii, 1983, pp. 411-415.
13. Lahey, R. T., Jr., Shiralkar, B. S., and Radcliffe, D. W., Mass Flux and Enthalpy Distribution in a Rod Bundle for Single- and Two-Phase Flow Conditions, ASME J. of Heat Transfer, 1971, pp. 197-207.
14. Ulrych, G., Analysis of Pressure Drop in 5×5 Rod Bundles with Spacers, EUROP, Eriangen, 1980.