Thermal-hydraulics in nuclear power technology (symposium), 1981

This conference contains 10 papers, all of which are abstracted separately. The papers cover the fundamental theories and phenomena, the performance characteristics of reactor components as well as the behavior of simulated nuclear systems and test reactors. In the fundamental area, the papers are associated with the heat transfer due to condensation in counter-current flooding, the hydrodynamics of a submerged vapor jet, the hydrodynamic criterion of flooding, the prediction of boiling transition, and the striping at the interface of thermal stratification. The papers in the category of plant system behavior are the study of the response of a scaled boiling water reactor system during a loss-of-coolant accident and the modeling of turbulent flow in the Fast Flux Test Facility