### Abstract

This presentation describes the current status of the
PORFLO code and the latest developments made in the
second subtask of the SAFIR2010/TRICOT project. The
present work is a continuation of the corresponding
previous SAFIR project.
In PORFLO, the basic features of the computer code
include assumption of porous medium, description of the
problem in Cartesian coordinates and the use of either
the five-equation model (with a mixture momentum
conservation equation) or the six-equation model for the
solution of the two-phase flow problem. The most
important development steps made during 2008 were: the
implementation of the six-equation model to PORFLO and
the development of new iterative solvers and
preconditioning methods for the solution of the pressure
correction equations of both the five-equation SIMPLE
algorithm and the newly developed (six-equation)
Phase-Coupled SIMPLE algorithm. As a result of the new
iterative solvers and preconditioning methods the
computation time has been reduced almost by an order of
magnitude.

Original language | English |
---|---|

Title of host publication | SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010 |

Subtitle of host publication | Interim Report |

Place of Publication | Espoo |

Publisher | VTT Technical Research Centre of Finland |

Pages | 131-141 |

ISBN (Electronic) | 978-951-38-7267-0 |

ISBN (Print) | 978-951-38-7266-3 |

Publication status | Published - 2009 |

MoE publication type | Not Eligible |

### Publication series

Series | VTT Tiedotteita - Research Notes |
---|---|

Number | 2466 |

ISSN | 1235-0605 |

## Fingerprint Dive into the research topics of 'Tridimensional core transient analysis methods (TRICOT): The porous medium model PORFLO for 3D two-phase flow and its application to BWR fuel bundle simulations'. Together they form a unique fingerprint.

## Cite this

Ilvonen, M., & Hovi, V. (2009). Tridimensional core transient analysis methods (TRICOT): The porous medium model PORFLO for 3D two-phase flow and its application to BWR fuel bundle simulations. In

*SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010: Interim Report*(pp. 131-141). VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2466 http://www.vtt.fi/inf/pdf/tiedotteet/2009/T2466.pdf