[EN - 09] - Boiling, Condensation and Multiphase Flow I

0208 Two-phase Flow Pattern of Carbon Dioxide in a Microchannel
0261 Experimental investigation on thermally stratified flows in nuclear reactors piping
0449 Evaluation of the Critical Heat Flux Margin
0612 The Effect of the Surface Condition on Nucleate Pool Boiling of Refrigerant R-11 on Cylindrical Copper Surfaces
1974 Thermal-Hydraulic Analysis of the IEA-R1 Research Reactor – A Comparison Between Ideal and Actual Conditions


<< back