Experiments for CFD-modelling of cooling water and Insulation debris two-phase flow phenomena during loss of coolant accidents

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

Research output: Chapter in Book/Published conference outputConference publication

Abstract

The knowledge of insulation debris generation and transport gains in importance regarding reactor safety research for PWR and BWR. The insulation debris released near the break consists of a mixture of very different fibres and particles concerning size, shape, consistence and other properties. Some fraction of the released insulation debris will be transported into the reactor sump where it may affect emergency core cooling. Experiments are performed to blast original samples of mineral wool insulation material by steam under original thermal-hydraulic break conditions of BWR. The gained fragments are used as initial specimen for further experiments at acrylic glass test facilities. The quasi ID-sinking behaviour of the insulation fragments are investigated in a water column by optical high speed video techniques and methods of image processing. Drag properties are derived from the measured sinking velocities of the fibres and observed geometric parameters for an adequate CFD modelling. In the test rig "Ring line-II" the influence of the insulation material on the head loss is investigated for debris loaded strainers. Correlations from the filter bed theory are adapted with experimental results and are used to model the flow resistance depending on particle load, filter bed porosity and parameters of the coolant flow. This concept also enables the simulation of a particular blocked strainer with CFDcodes. During the ongoing work further results of separate effect and integral experiments and the application and validation of the CFD-models for integral test facilities and original containment sump conditions are expected.
Original languageEnglish
Title of host publication12th International Meeting on Nuclear Reactor Thermal Hydraulics 2007
Subtitle of host publicationNURETH 12
PublisherCurran
Pages207-229
Number of pages23
Volume1
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 Sept 20074 Oct 2007

Meeting

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

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  • CFD-modelling of insulation debris transport phenomena in water flow

    Krepper, E., Cartland-Glover, G., Grahn, A., Weiß, F-P., Alt, S., Hampel, R., Kästner, W. & Seeliger, A., 22 May 2007, 12th International Meeting on Nuclear Reactor Thermal Hydraulics 2007: NURETH 12. Curran, Vol. 2. p. 678-692 15 p.

    Research output: Chapter in Book/Published conference outputOther chapter contribution

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