| 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 |
