Severe accident simulation using CFD codes

Matthias Heitsch, Risto Huhtanen, Zsolt Téchy, Chris Fry, Pál Kostka, Jarto Niemi, Berthold Schramm

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

1 Citation (Scopus)

Abstract

In the PHARE project "Hydrogen Management for the VVER440/213" (HU2002/000-632-04-01), CFD calculations with GASFLOW 2.1, FLUENT 6.1.22 and CFX-5.7.1 were performed for the Paks NPP modeling a defined severe accident scenario involving hydrogen release. The purpose of this work was to demonstrate the use of CFD codes to model a containment undergoing a severe accident.
With growing experience in performing such analyses the results can support the formation of a sound basis for assessing the risk of losing containment integrity as a result of hydrogen deflagrations. As an effective mitigation measure in such a situation, the implementation of catalytic recombiners is planned in the Paks NPP. In order to support these plans both unmitigated and recombiner-mitigated simulations were performed. These are described and selected results are compared. The codes CFX and FLUENT needed to be extended by wall and bulk steam condensation models to be able to simulate all relevant processes during the given accident.
The parallel use of several CFD codes for the same accident scenario was chosen to reduce uncertainties in the results by revealing margins of major findings. Previously it was considered impractical to use CFD codes to simulate a full containment subject to a severe accident and extending over many hours. This was due to prohibitive computing times and missing physical capabilities.
This work demonstrates, supported by developments in CFD codes and improvements in computer power, that these calculations have now become feasible
Original languageEnglish
Title of host publicationProceedings
Subtitle of host publication12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12
PublisherAmerican Nuclear Society ANS
ISBN (Print)978-0-89448-057-7
Publication statusPublished - 2007
MoE publication typeA4 Article in a conference publication
Event12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 - Pittsburgh, United States
Duration: 30 Sep 20073 Oct 2007

Conference

Conference12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12
CountryUnited States
CityPittsburgh
Period30/09/073/10/07

Fingerprint

Accidents
Computational fluid dynamics
Hydrogen
Condensation
Steam
Acoustic waves

Keywords

  • severe accident
  • CFD code
  • hydrogen
  • mitigation
  • PAR

Cite this

Heitsch, M., Huhtanen, R., Téchy, Z., Fry, C., Kostka, P., Niemi, J., & Schramm, B. (2007). Severe accident simulation using CFD codes. In Proceedings: 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 American Nuclear Society ANS.
Heitsch, Matthias ; Huhtanen, Risto ; Téchy, Zsolt ; Fry, Chris ; Kostka, Pál ; Niemi, Jarto ; Schramm, Berthold. / Severe accident simulation using CFD codes. Proceedings: 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. American Nuclear Society ANS, 2007.
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Heitsch, M, Huhtanen, R, Téchy, Z, Fry, C, Kostka, P, Niemi, J & Schramm, B 2007, Severe accident simulation using CFD codes. in Proceedings: 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. American Nuclear Society ANS, 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12, Pittsburgh, United States, 30/09/07.

Severe accident simulation using CFD codes. / Heitsch, Matthias; Huhtanen, Risto; Téchy, Zsolt; Fry, Chris; Kostka, Pál; Niemi, Jarto; Schramm, Berthold.

Proceedings: 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. American Nuclear Society ANS, 2007.

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

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AU - Heitsch, Matthias

AU - Huhtanen, Risto

AU - Téchy, Zsolt

AU - Fry, Chris

AU - Kostka, Pál

AU - Niemi, Jarto

AU - Schramm, Berthold

PY - 2007

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N2 - In the PHARE project "Hydrogen Management for the VVER440/213" (HU2002/000-632-04-01), CFD calculations with GASFLOW 2.1, FLUENT 6.1.22 and CFX-5.7.1 were performed for the Paks NPP modeling a defined severe accident scenario involving hydrogen release. The purpose of this work was to demonstrate the use of CFD codes to model a containment undergoing a severe accident. With growing experience in performing such analyses the results can support the formation of a sound basis for assessing the risk of losing containment integrity as a result of hydrogen deflagrations. As an effective mitigation measure in such a situation, the implementation of catalytic recombiners is planned in the Paks NPP. In order to support these plans both unmitigated and recombiner-mitigated simulations were performed. These are described and selected results are compared. The codes CFX and FLUENT needed to be extended by wall and bulk steam condensation models to be able to simulate all relevant processes during the given accident. The parallel use of several CFD codes for the same accident scenario was chosen to reduce uncertainties in the results by revealing margins of major findings. Previously it was considered impractical to use CFD codes to simulate a full containment subject to a severe accident and extending over many hours. This was due to prohibitive computing times and missing physical capabilities. This work demonstrates, supported by developments in CFD codes and improvements in computer power, that these calculations have now become feasible

AB - In the PHARE project "Hydrogen Management for the VVER440/213" (HU2002/000-632-04-01), CFD calculations with GASFLOW 2.1, FLUENT 6.1.22 and CFX-5.7.1 were performed for the Paks NPP modeling a defined severe accident scenario involving hydrogen release. The purpose of this work was to demonstrate the use of CFD codes to model a containment undergoing a severe accident. With growing experience in performing such analyses the results can support the formation of a sound basis for assessing the risk of losing containment integrity as a result of hydrogen deflagrations. As an effective mitigation measure in such a situation, the implementation of catalytic recombiners is planned in the Paks NPP. In order to support these plans both unmitigated and recombiner-mitigated simulations were performed. These are described and selected results are compared. The codes CFX and FLUENT needed to be extended by wall and bulk steam condensation models to be able to simulate all relevant processes during the given accident. The parallel use of several CFD codes for the same accident scenario was chosen to reduce uncertainties in the results by revealing margins of major findings. Previously it was considered impractical to use CFD codes to simulate a full containment subject to a severe accident and extending over many hours. This was due to prohibitive computing times and missing physical capabilities. This work demonstrates, supported by developments in CFD codes and improvements in computer power, that these calculations have now become feasible

KW - severe accident

KW - CFD code

KW - hydrogen

KW - mitigation

KW - PAR

M3 - Conference article in proceedings

SN - 978-0-89448-057-7

BT - Proceedings

PB - American Nuclear Society ANS

ER -

Heitsch M, Huhtanen R, Téchy Z, Fry C, Kostka P, Niemi J et al. Severe accident simulation using CFD codes. In Proceedings: 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. American Nuclear Society ANS. 2007