CFD-modelling of insulation debris transport phenomena in water flow

Eckhard Krepper, Gregory Cartland-Glover, Alexander Grahn, Frank-Peter Weiß, Sören Alt, Rainer Hampel, Wolfgang Kästner, Andrè Seeliger

Research output: Chapter in Book/Report/Conference proceedingOther chapter contribution

Abstract

The investigation of insulation debris generation, transport and sedimentation becomes important with regard to reactor safety research for PWR and BWR, when considering the long-term behavior of emergency core cooling systems during all types of loss of coolant accidents (LOCA). The insulation debris released near the break during a LOCA incident consists of a mixture of disparate particle population that varies with size, shape, consistency and other properties. Some fractions of the released insulation debris can be transported into the reactor sump, where it may perturb/impinge on the emergency core cooling systems. Open questions of generic interest are the sedimentation of the insulation debris in a water pool, its possible re-suspension and transport in the sump water flow and the particle load on strainers and corresponding pressure drop. A joint research project on such questions is being performed in cooperation between the University of Applied Sciences Zittau/Görlitz and the Forschungszentrum Dresden-Rossendorf. The project deals with the experimental investigation of particle transport phenomena in coolant flow and the development of CFD models for its description. While the experiments are performed at the University at Zittau/Görlitz, the theoretical modeling efforts are concentrated at Forschungszentrum Dresden-Rossendorf. Whereas the paper Alt et al. is focused on the experiments in the present paper the basic concepts for CFD modeling are described and feasibility studies including the conceptual design of the experiments are presented.
Original languageEnglish
Title of host publication12th International Meeting on Nuclear Reactor Thermal Hydraulics 2007
Subtitle of host publicationNURETH 12
PublisherCurran
Pages678-692
Number of pages15
Volume2
ISBN (Print)0-89448-058-8, 978-1-60560-071-0
Publication statusPublished - 22 May 2007
Event12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics - Pittsburgh, PA, United States
Duration: 30 Sep 20074 Oct 2007

Meeting

Meeting12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
Abbreviated titleNURETH-12
CountryUnited States
CityPittsburgh, PA
Period30/09/074/10/07

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