High Pressure Gas as a Heat Transport Medium: A Symposium Arranged by the Nuclear Energy Group, 9-10th March 1967 |
Contents
Introduction ix | 1 |
Thermodynamic comparison of gas coolants for nuclear reactors | 9 |
Gassolids suspensions as heat transfer media | 17 |
Copyright | |
25 other sections not shown
Common terms and phrases
acoustic argon axial flow blade blower boiler carbon dioxide cent centrifugal channel coefficient convection coolant cooling core correlation cylindrical density diameter dissipation factors Dragon reactor duct effect efficiency equation experimental finned tubing flow area fluid frequency fuel element gas bearing gas circuit gas circulators gas flow gas pressure gas temperature gas-cooled gas-solids gases given graphite heat exchanger heat flux heat transfer area heat transfer coefficient helium high pressure increase insulation lb/inĀ² machines magnox maximum measured mixture Mixture density motor nuclear power Nuclear Power Group obtained Oldbury operating outlet paper parameters particles plate pressure drop pressure vessel radiation range ratio reactor rev/min Reynolds number rotor roughened seal shaft shown in Fig Sizewell speed stainless steel Stanton number steam strain gauges stress sub-channel surface test section thermal conductivity thermocouples tion transducer tube bank turbine values valve variation velocity vibration wall wave