Critical Heat Flux: A Review of Recent Publications
- 1 July 1977
- journal article
- review article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 34 (2) , 135-171
- https://doi.org/10.13182/nt77-a39695
Abstract
Although much effort has been devoted to the subject of critical heat flux (CHF) during the last 20 years, the design correlations for CHF predictions in tubes, annuli, and rod bundles are still empirical and generally apply only to restricted ranges of parameters. Recently, experimental data on CHF large test sections have been obtained both in steam generators and reactor geometry. A survey of these new data and correlations gives a general picture of the state-of-the-art, linking the new and old results. Existing theoretical analyses stress the importance for future work. Additional experimental work is needed to optimize rod bundle correlations and to extend the validity of correlations to wider ranges and to unusual geometries. The indirect heating problem is not well understood, and continued efforts in theoretical analyses are needed.Keywords
This publication has 15 references indexed in Scilit:
- Use of the “Lagrangian and Eulerian Points of View” in the Transient Critical Heat Flux Calculations for BWR Rod Bundles and Experimental VerificationsNuclear Technology, 1975
- High pressure rod bundle DNB data with axially non-uniform heat fluxNuclear Engineering and Design, 1974
- Transient Critical Heat Flux and Spacer Grid StudiesNuclear Technology, 1974
- State-of-the-Art in BWR Rod Bundle Burnout PredictionsNuclear Technology, 1974
- A Model to Predict Convective Subcooled Critical Heat FluxJournal of Heat Transfer, 1974
- Two-Phase Mixing for Annular Flow in Simulated Rod Bundle GeometriesNuclear Science and Engineering, 1973
- Fluid to fluid modeling of critical heat flux: A compensated distortion modelInternational Journal of Heat and Mass Transfer, 1973
- Subchannel thermal analysis of rod bundle coresNuclear Engineering and Design, 1972
- THE CRITICAL HEAT FLUX FOR THE FLOW OF STEAM–WATER MIXTURES THROUGH PIPESPublished by Elsevier ,1969
- An Evaluation of the Departure from Nucleate Boiling in Bundles of Reactor Fuel RodsNuclear Science and Engineering, 1968