Direct Condensation and Entrainment Experiments with Steam and Water


Direct Condensation and Entrainment Experiments with Steam and Water

Seidel, T.

In a hypothetical Small Break Loss of Coolant Accident in a Pressurized Water Reactor, the Reactor Pressure Vessel wall may be exposed to thermal stress, since Emergency Core Cooling Systems inject cold water into the hot reactor system. The loads on the primary loop and RPV walls are determined by mixing processes with the surrounding hot water and by the condensation of steam on the free surface.
In order to develop Computational Fluid Dynamics Simulations for future safety assessment and design purposes, experiments with stratified steam-water surfaces and with plunging liquid jets have been carried out and are being analyzed. It is shown, that the results may be used to develop and to validate CFD-models for reactor safety applications. Analysis, conditioning and summary of measured data is ongoing and promising.

Keywords: Direct Contact Condensation; steam; water; experiments; high pressure

  • Lecture (Conference)
    45th Annual Meeting on Nuclear Technology, 06.-8.5.2014, Frankfurt Main, Deutschland
  • Contribution to proceedings
    45th Annual Meeting on Nuclear Technology, 06.-8.5.2014, Frankfurt Main, Deutschland
    Proceedings AMNT 2014 (CD)

Permalink: https://www.hzdr.de/publications/Publ-20256
Publ.-Id: 20256