Critical heat flux and turbulent mixing in hexagonal tight rod bundles
- 1 December 1998
- journal article
- Published by Elsevier BV in International Journal of Multiphase Flow
- Vol. 24 (8), 1245-1263
- https://doi.org/10.1016/s0301-9322(98)00027-5
Abstract
No abstract availableKeywords
This publication has 15 references indexed in Scilit:
- Critical heat flux in uniformly heated vertical tubesInternational Journal of Heat and Mass Transfer, 1997
- The 1995 look-up table for critical heat flux in tubesNuclear Engineering and Design, 1996
- Critical heat fluxInternational Journal of Multiphase Flow, 1994
- The French Thermal-Hydraulic Program Addressing the Requirements of Future Pressurized Water ReactorsNuclear Technology, 1988
- Critical heat flux of forced convective boiling in uniformly heated vertical tubes with special reference to very large length-to-diameter ratiosInternational Journal of Heat and Mass Transfer, 1987
- CHF in the parameter range of advanced pressurized water reactor coresNuclear Engineering and Design, 1987
- 1986 AECL-UO Critical Heat Flux Lookup TableHeat Transfer Engineering, 1986
- General Features of Advanced Pressurized Water Reactors with Improved Fuel UtilizationNuclear Technology, 1982
- Implications concerning rod bundle crossflow mixing based on measurements of turbulent flow structureInternational Journal of Heat and Mass Transfer, 1974
- Pressure Drop Correlations for Fuel Element SpacersNuclear Technology, 1973