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Simulation of H2 distribution and combustion in LWR containments using Lumped Parameter Codes

  • J. Burkhardt , M. Klöcker , T. Brähler and M. K. Koch
Published/Copyright: April 5, 2013
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Kerntechnik
From the journal Kerntechnik Volume 74 Issue 5-6

Abstract

This article focuses on the validation of the Lumped Parameter (LP) computer codes COCOSYS and ASTEC in the field of containment phenomena during severe accidents. The release of hydrogen (H2) as an open jet from the primary circuit into the containment might cause atmospheric H2-stratifications which in turn may result in an ignitable atmospheric mixture. If this mixture is ignited, the integrity of the containment can be endangered due to the pressure and temperature rise, resulting from the combustion process. The emphasis of the paper lies on these three phenomena referring to possible successive phases of a loss of coolant accident.

Kurzfassung

Dieser Artikel befasst sich mit der Validierung der Lumped Parameter (LP) Codes COCOSYS und ASTEC im Rahmen von Containment Störfallanalysen. Ausgehend von der strahlförmigen Freisetzung von Wasserstoff (H2) aus dem Primärkreislauf ins Containment kann sich eine atmosphärische Schichtung einstellen, aus der sich wiederum ein zündfähiges Gasgemisch bilden kann. Wenn dieses Gasgemisches gezündet wird, ist die Integrität des Containments möglicherweise, durch den aus der Verbrennung resultierenden Druck- und Temperaturanstieg, gefährdet. Der Schwerpunkt dieser Veröffentlichung liegt in der Betrachtung dieser drei Phänomene, die in der Abfolge nacheinander mögliche Phasen eines Kühlmittelverluststörfalls darstellen.

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References

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Received: 2009-7-1
Published Online: 2013-04-05
Published in Print: 2009-11-01

© 2009, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Main results of the European project NURESIM on the CFD-modelling of two-phase Pressurized Thermal Shock (PTS)
  7. Simulation of H2 distribution and combustion in LWR containments using Lumped Parameter Codes
  8. CFD modelling of insulation debris transport phenomena in water flow
  9. Investigation of coolant mixing in head parts of VVER-440 fuel assemblies with burnable poison
  10. Prediction of time dependent standby failure rates for periodically tested components taking into account the operational history
  11. Closed loop auto control system software for Miniature Neutron Source Reactors (MNSRs)
  12. Numerical simulation of passive catalytic recombiner
  13. Some affine solutions for CANDLE burn-up waves in 1D-geometry
  14. Assessment of radiological consequences due to routine atmospheric discharges from nuclear power plants
  15. Chebyshev acceleration of criticality calculations in boundary element applications to neutron diffusion
  16. Legendre polynomial series of the infinite medium Green's Function in neutral particle transport theory: the half-space albedo problem
  17. A model for calculation of forward isotropic scattering with application to transport equation in slab geometry
  18. Training and retraining programme for research reactor operating personnel
https://doi.org/10.3139/124.110042

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Main results of the European project NURESIM on the CFD-modelling of two-phase Pressurized Thermal Shock (PTS)
  7. Simulation of H2 distribution and combustion in LWR containments using Lumped Parameter Codes
  8. CFD modelling of insulation debris transport phenomena in water flow
  9. Investigation of coolant mixing in head parts of VVER-440 fuel assemblies with burnable poison
  10. Prediction of time dependent standby failure rates for periodically tested components taking into account the operational history
  11. Closed loop auto control system software for Miniature Neutron Source Reactors (MNSRs)
  12. Numerical simulation of passive catalytic recombiner
  13. Some affine solutions for CANDLE burn-up waves in 1D-geometry
  14. Assessment of radiological consequences due to routine atmospheric discharges from nuclear power plants
  15. Chebyshev acceleration of criticality calculations in boundary element applications to neutron diffusion
  16. Legendre polynomial series of the infinite medium Green's Function in neutral particle transport theory: the half-space albedo problem
  17. A model for calculation of forward isotropic scattering with application to transport equation in slab geometry
  18. Training and retraining programme for research reactor operating personnel
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