Verification and validation of numerical models of the transport of insulation debris

G.M. Cartland Glover*, A. Kratzsch, E. Krepper, S. Renger, A. Seeliger, F. Zacharias, S. Alt, W. Kästner, H. Kryk, F.-P. Weiss

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

Abstract

A combination of the two-fluid and drift flux models have been used to model the transport of fibrous debris. This debris is generated during loss of coolant accidents in the primary circuit of pressurized or boiling water nuclear reactors, as high pressure steam or water jets can damage adjacent insulation materials including mineral wool blankets. Fibre agglomerates released from the mineral wools may reach the containment sump strainers, where they can accumulate and compromise the long-term operation of the emergency core cooling system. Single-effect experiments of sedimentation in a quiescent rectangular column and sedimentation in a horizontal flow are used to verify and validate this particular application of the multiphase numerical models. The utilization of both modeling approaches allows a number of pseudocontinuous dispersed phases of spherical wetted agglomerates to be modeled simultaneously. Key effects on the transport of the fibre agglomerates are particle size, density and turbulent dispersion, as well as the relative viscosity of the fluid-fibre mixture.
Original languageEnglish
Pages (from-to)255-270
Number of pages16
JournalThe Journal of Computational Multiphase Flows
Volume4
Issue number3
DOIs
Publication statusPublished - Sep 2012

Bibliographical note

Selected for publication in a special issue of the Journal of Computational Multiphase Flows. Originally presented at NURETH-14 in Toronto Canada, the 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics

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  • Verification and validation of numerical models of the transport of insulation debris

    Cartland Glover, G. M., Kratzsch, A., Krepper, E., Renger, S., Seeliger, A., Zacharias, F., Alt, S., Kästner, W., Kryk, H. & Weiss, F. P., 25 Sep 2011, Proceedings of the 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14). ASME

    Research output: Chapter in Book/Published conference outputConference publication

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