CFD modelling of insulation debris transport phenomena in water flow
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E. Krepper
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 behaviour of emergency core cooling systems during all types of loss of coolant accidents. 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 modelling efforts are concentrated at Forschungszentrum Dresden-Rossendorf. In the current paper the basic concepts for CFD modelling are described and feasibility studies are presented.
Kurzfassung
Die Untersuchung von Freisetzung, Transport und Ablagerung von Isolationsmaterial ist in der Sicherheitsforschung von Druck- und Siedewasserreaktoren für die Betrachtung der Langzeit-Notkühlung bei Leckstörfällen wichtig. Zwischen der Hochschule Zittau und dem Forschungszentrum Dresden-Rossendorf wird durch das Bundesministerium für Wirtschaft und Technologie ein Projekt zur Untersuchung damit im Zusammenhang stehender Fragen gefördert. Das Projekt befasst sich der experimentellen Untersuchung des Fasertransportes und der darauf basierenden Entwicklung von CFD-Modellen. Während in der Hochschule Zittau Experimente durchgeführt werden, sind die Arbeiten zur CFD-Modellierung in Rossendorf konzentriert. Neben dem Transport der Fasern in einer Wasserströmung werden Fragen der Anlagerung von Fasern und des Differenzdruckaufbaus auf einem faserbelegten Sieb untersucht. Die vorliegende Arbeit stellt die wesentlichsten Konzepte der CFD-Modellierung sowie Machbarkeitsstudien vor.
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© 2009, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Main results of the European project NURESIM on the CFD-modelling of two-phase Pressurized Thermal Shock (PTS)
- Simulation of H2 distribution and combustion in LWR containments using Lumped Parameter Codes
- CFD modelling of insulation debris transport phenomena in water flow
- Investigation of coolant mixing in head parts of VVER-440 fuel assemblies with burnable poison
- Prediction of time dependent standby failure rates for periodically tested components taking into account the operational history
- Closed loop auto control system software for Miniature Neutron Source Reactors (MNSRs)
- Numerical simulation of passive catalytic recombiner
- Some affine solutions for CANDLE burn-up waves in 1D-geometry
- Assessment of radiological consequences due to routine atmospheric discharges from nuclear power plants
- Chebyshev acceleration of criticality calculations in boundary element applications to neutron diffusion
- Legendre polynomial series of the infinite medium Green's Function in neutral particle transport theory: the half-space albedo problem
- A model for calculation of forward isotropic scattering with application to transport equation in slab geometry
- Training and retraining programme for research reactor operating personnel
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Main results of the European project NURESIM on the CFD-modelling of two-phase Pressurized Thermal Shock (PTS)
- Simulation of H2 distribution and combustion in LWR containments using Lumped Parameter Codes
- CFD modelling of insulation debris transport phenomena in water flow
- Investigation of coolant mixing in head parts of VVER-440 fuel assemblies with burnable poison
- Prediction of time dependent standby failure rates for periodically tested components taking into account the operational history
- Closed loop auto control system software for Miniature Neutron Source Reactors (MNSRs)
- Numerical simulation of passive catalytic recombiner
- Some affine solutions for CANDLE burn-up waves in 1D-geometry
- Assessment of radiological consequences due to routine atmospheric discharges from nuclear power plants
- Chebyshev acceleration of criticality calculations in boundary element applications to neutron diffusion
- Legendre polynomial series of the infinite medium Green's Function in neutral particle transport theory: the half-space albedo problem
- A model for calculation of forward isotropic scattering with application to transport equation in slab geometry
- Training and retraining programme for research reactor operating personnel
