Applications and development of the PORFLO 3D code in nuclear power plant thermal hydraulics

Eveliina Takasuo, Ville Hovi, Mikko Ilvonen

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

7 Citations (Scopus)

Abstract

PORFLO is a 3D two-phase flow simulation code which utilizes porous medium approach in the modeling of complex geometries. The code has been developed specifically for investigating various problems encountered in thermal hydraulic safety analysis of nuclear power plants. The code solution is based on the basic two-phase flow conservation equations with application-specific closure models for pressure loss, interfacial friction and heat transfer. The current main applications of the code include the simulations of flows in the horizontal steam generators of the Loviisa VVER-440 reactors and in the EPR reactor pressure vessel (RPV), and the modeling of the dryout behavior of porous core debris beds in the area of severe accident analysis. In the present work, the status of the code development, the main applications and the simulation results are summarized. In the case of the horizontal steam generator, the PORFLO simulation results are compared to the results obtained by the FLUENT CFD software. In the case of the core debris bed, comparisons to experimental data are also made
Original languageEnglish
Title of host publicationProceedings
Subtitle of host publication20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference
Place of PublicationNew York, NY, USA
PublisherAmerican Society of Mechanical Engineers ASME
Pages393-402
Volume4
ISBN (Print)978-0-7918-4498-4
Publication statusPublished - 2012
MoE publication typeA4 Article in a conference publication
Event20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference - Anaheim, California, United States
Duration: 30 Jul 20123 Aug 2012

Conference

Conference20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference
CountryUnited States
CityAnaheim, California
Period30/07/123/08/12

Fingerprint

Nuclear power plants
Hydraulics
Steam generators
Debris
Two phase flow
Flow simulation
Pressure vessels
Paramagnetic resonance
Porous materials
Conservation
Accidents
Computational fluid dynamics
Friction
Heat transfer
Geometry
Hot Temperature

Keywords

  • Nuclear power
  • porous media model
  • PORFLO
  • thermal-hydraulics
  • CFD

Cite this

Takasuo, E., Hovi, V., & Ilvonen, M. (2012). Applications and development of the PORFLO 3D code in nuclear power plant thermal hydraulics. In Proceedings: 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference (Vol. 4, pp. 393-402). New York, NY, USA: American Society of Mechanical Engineers ASME.
Takasuo, Eveliina ; Hovi, Ville ; Ilvonen, Mikko. / Applications and development of the PORFLO 3D code in nuclear power plant thermal hydraulics. Proceedings: 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. Vol. 4 New York, NY, USA : American Society of Mechanical Engineers ASME, 2012. pp. 393-402
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Takasuo, E, Hovi, V & Ilvonen, M 2012, Applications and development of the PORFLO 3D code in nuclear power plant thermal hydraulics. in Proceedings: 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. vol. 4, American Society of Mechanical Engineers ASME, New York, NY, USA, pp. 393-402, 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference , Anaheim, California, United States, 30/07/12.

Applications and development of the PORFLO 3D code in nuclear power plant thermal hydraulics. / Takasuo, Eveliina; Hovi, Ville; Ilvonen, Mikko.

Proceedings: 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. Vol. 4 New York, NY, USA : American Society of Mechanical Engineers ASME, 2012. p. 393-402.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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AB - PORFLO is a 3D two-phase flow simulation code which utilizes porous medium approach in the modeling of complex geometries. The code has been developed specifically for investigating various problems encountered in thermal hydraulic safety analysis of nuclear power plants. The code solution is based on the basic two-phase flow conservation equations with application-specific closure models for pressure loss, interfacial friction and heat transfer. The current main applications of the code include the simulations of flows in the horizontal steam generators of the Loviisa VVER-440 reactors and in the EPR reactor pressure vessel (RPV), and the modeling of the dryout behavior of porous core debris beds in the area of severe accident analysis. In the present work, the status of the code development, the main applications and the simulation results are summarized. In the case of the horizontal steam generator, the PORFLO simulation results are compared to the results obtained by the FLUENT CFD software. In the case of the core debris bed, comparisons to experimental data are also made

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Takasuo E, Hovi V, Ilvonen M. Applications and development of the PORFLO 3D code in nuclear power plant thermal hydraulics. In Proceedings: 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. Vol. 4. New York, NY, USA: American Society of Mechanical Engineers ASME. 2012. p. 393-402