Visualization and Investigation of Natural Circulation in a Vessel with Tube Bundle Configuration Using DPIDV and LDV Comparison of DPIDV and LDV Measurements

Abstract : This paper deals with the investigation of single-phase natural convection flows of air in a tube bundle configuration. Nuclear reactor safety research forms the background for the experiments. In this context the examination of circulation flow is important regarding high pressure loss-of-coolant-accidents. Safety considerations make it necessary to determine the influence of the developing natural convection flows on the heating-up of the reactor core and the reactor pressure vessel installations, especially in the upper plenum. For verification of reactor safety codes, in our case the 2D thermal-hydraulics computer code FRECON, specialized benchmark experiments are needed. (Author)