Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module
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V. Vileiniskis
Abstract
The main objective of the PHEBUS FPT1 experiment was to study the release of fission products and their subsequent transport and deposition in the primary circuit and the containment under the conditions representative of a severe accident of a Pressurised Water Reactor. The FPT1 test was divided into the bundle degradation, aerosol, washing and chemistry phases. The objective of this paper is related to the best estimate analysis of the bundle degradation phase using ASTEC code ICARE module. GRS (Germany) best estimate method was used for the simulation of FPT1 test by employing SUSA 3.5 package. The performed best estimate analysis showed that ICARE module is capable to model the main severe accidents phenomena in the fuel bundle, heating and melting, taking into account the used physical and code parameters uncertainties.
Kurzfassung
Das Hauptziel des PHEBUS FPT1 Experiments war die Freisetzung von Spaltprodukten und deren anschließender Transport und Ablagerung im Primärkühlkreislauf und Containment unter Störfäll-Bedingungen zu studieren. Der FPT1 Test könnte in Abbau-, Aerosol-, Wasch- und Chemie-Phase unterteilt werden. Das Ziel dieser Arbeit ist mit der Best-Estimate Analyse des Bündels Abbauphase mit ASTEC Code ICARE Modul verbunden. Die Best-Estimate Analysismethode wurde für die Simulation des FPT1 Tests durch den Einsatz des SUSA 3.5 Pakets verwendet. Die durchgeführte Best-Estimate Analyse zeigte, dass das ICARE Modul in der Lage ist, die wichtigsten Phänomene eines schweren Störfälls im Brennelementbündel, Erwärmen und Schmelzen, zu modellieren unter Berücksichtigung der Unsicherheiten.der verwendeten physikalischen Parameter und der Code-Parameter.
References
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© 2011, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
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- Multiple condensation induced water hammer events, experiments and theoretical investigations
- Simulation of load following mode of operation for a natural circulation pressure tube type BWR
- CANDU fuel elements behaviour in the load following tests
- Local heat transfer coefficient near the spacer grids
- Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module
- Investigations of bi-directional flow behaviour in presence of a large vertical opening in a fire compartment
- CANDU reactors with reactor grade plutonium/thorium carbide fuel
- Novel method to produce 109Cd via proton irradiation of electroplated silver on a gold-coated copper backing
- Technical Notes/Technische Mitteilungen
- Atmospheric dispersion of accidental release of radioactive gases from high enriched and low enriched fuel of Miniature Neutron Source Reactors (MNSR)
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- Determination of natural uranium, thorium and radium isotopes in water and soil samples by alpha spectroscopy
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Stress analyses for reactor pressure vessels by the example of a product line '69 Boiling Water Reactor
- Multiple condensation induced water hammer events, experiments and theoretical investigations
- Simulation of load following mode of operation for a natural circulation pressure tube type BWR
- CANDU fuel elements behaviour in the load following tests
- Local heat transfer coefficient near the spacer grids
- Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module
- Investigations of bi-directional flow behaviour in presence of a large vertical opening in a fire compartment
- CANDU reactors with reactor grade plutonium/thorium carbide fuel
- Novel method to produce 109Cd via proton irradiation of electroplated silver on a gold-coated copper backing
- Technical Notes/Technische Mitteilungen
- Atmospheric dispersion of accidental release of radioactive gases from high enriched and low enriched fuel of Miniature Neutron Source Reactors (MNSR)
- Fuel burnup of modified fuel assembly configurations for a small medical reactor
- Determination of natural uranium, thorium and radium isotopes in water and soil samples by alpha spectroscopy
