Experiments on One-Phase Thermally Stratified Flows in Nuclear Reactor Pipe Lines

1. Abstract The one-phase thermal stratified flow phenomenon occurs when two different layers of the same liquid at different temperatures flow separately in horizontal pipes without appreciable mixing. This phenomenon was not considered in the design stage of most of the operating nuclear power plants, but in last two decades it has become apparent due to the temperature monitoring of piping systems. The occurrence of temperature differences of about 200oC have been found in a narrow band around the hot and cold water interface in components under stratified flows. Loadings due to thermal stratification affected the integrity of safety related piping systems. This paper presents the results of a range of experiments performed to simulate one phase thermally stratified flows in geometry and flow condition representing a nuclear reactor steam generator injection nozzle. They have the objective of studying the flow configurations and understanding the evolution of the thermal stratification process. The driving parameter considered to characterize flow under stratified regime due to difference in specific masses is the Froude number. Different Froude numbers, from 0.018 to 0.22, were obtained in different testes by setting injection cold water flow rates and hot water initial temperatures as planned in the test matrix. Results are presented showing the influence of Froude number on the hot and cold water interface position, temperature gradients and striping phenomenon.