CFD evaluation of hydrogen risk mitigation measures in a VVER-440/213 containment

Matthias Heitsch (Corresponding Author), Risto Huhtanen, Zsolt Techy, Chris Fry, Pal Kostka, Jarto Niemi, Berthold Schramm

Research output: Contribution to journalArticleScientificpeer-review

29 Citations (Scopus)

Abstract

In the PHARE project “Hydrogen Management for the VVER440/213” (HU2002/000-632-04-01), CFD (Computational Fluid Dynamics) calculations using GASFLOW, FLUENT and CFX were performed for the Paks NPP (Nuclear Power Plant), modelling a defined severe accident scenario which involves the release of hydrogen. The purpose of this work is to demonstrate that CFD codes can be used to model gas movement inside a containment during a severe accident. With growing experience in performing such analyses, the results encourage the use of CFD in 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 refinement to their models of wall and bulk steam condensation in order to be able to fully simulate the severe accident under consideration. Several CFD codes were used in parallel to model the same accident scenario in order to reduce uncertainties in the results. Previously it was considered impractical to use CFD codes to simulate a full containment subject to a severe accident extending over many hours. This was because of the expected prohibitive computing times and missing physical capabilities of the codes. This work demonstrates that, because of developments in the capabilities of CFD codes and improvements in computer power, these calculations have now become feasible.

Original languageEnglish
Pages (from-to)385-396
Number of pages12
JournalNuclear Engineering and Design
Volume240
Issue number2
DOIs
Publication statusPublished - 2010
MoE publication typeA1 Journal article-refereed
Event12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 - Pittsburgh, United States
Duration: 30 Sep 20074 Oct 2007

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containment
computational fluid dynamics
Hydrogen
accidents
Computational fluid dynamics
accident
hydrogen
Accidents
evaluation
nuclear power plants
nuclear power plant
Nuclear power plants
deflagration
Steam
steam
integrity
code
mitigation measure
condensation
Condensation

Cite this

Heitsch, M., Huhtanen, R., Techy, Z., Fry, C., Kostka, P., Niemi, J., & Schramm, B. (2010). CFD evaluation of hydrogen risk mitigation measures in a VVER-440/213 containment. Nuclear Engineering and Design, 240(2), 385-396. https://doi.org/10.1016/j.nucengdes.2008.07.022
Heitsch, Matthias ; Huhtanen, Risto ; Techy, Zsolt ; Fry, Chris ; Kostka, Pal ; Niemi, Jarto ; Schramm, Berthold. / CFD evaluation of hydrogen risk mitigation measures in a VVER-440/213 containment. In: Nuclear Engineering and Design. 2010 ; Vol. 240, No. 2. pp. 385-396.
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Heitsch, M, Huhtanen, R, Techy, Z, Fry, C, Kostka, P, Niemi, J & Schramm, B 2010, 'CFD evaluation of hydrogen risk mitigation measures in a VVER-440/213 containment', Nuclear Engineering and Design, vol. 240, no. 2, pp. 385-396. https://doi.org/10.1016/j.nucengdes.2008.07.022

CFD evaluation of hydrogen risk mitigation measures in a VVER-440/213 containment. / Heitsch, Matthias (Corresponding Author); Huhtanen, Risto; Techy, Zsolt; Fry, Chris; Kostka, Pal; Niemi, Jarto; Schramm, Berthold.

In: Nuclear Engineering and Design, Vol. 240, No. 2, 2010, p. 385-396.

Research output: Contribution to journalArticleScientificpeer-review

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T1 - CFD evaluation of hydrogen risk mitigation measures in a VVER-440/213 containment

AU - Heitsch, Matthias

AU - Huhtanen, Risto

AU - Techy, Zsolt

AU - Fry, Chris

AU - Kostka, Pal

AU - Niemi, Jarto

AU - Schramm, Berthold

PY - 2010

Y1 - 2010

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AB - In the PHARE project “Hydrogen Management for the VVER440/213” (HU2002/000-632-04-01), CFD (Computational Fluid Dynamics) calculations using GASFLOW, FLUENT and CFX were performed for the Paks NPP (Nuclear Power Plant), modelling a defined severe accident scenario which involves the release of hydrogen. The purpose of this work is to demonstrate that CFD codes can be used to model gas movement inside a containment during a severe accident. With growing experience in performing such analyses, the results encourage the use of CFD in 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 refinement to their models of wall and bulk steam condensation in order to be able to fully simulate the severe accident under consideration. Several CFD codes were used in parallel to model the same accident scenario in order to reduce uncertainties in the results. Previously it was considered impractical to use CFD codes to simulate a full containment subject to a severe accident extending over many hours. This was because of the expected prohibitive computing times and missing physical capabilities of the codes. This work demonstrates that, because of developments in the capabilities of CFD codes and improvements in computer power, these calculations have now become feasible.

U2 - 10.1016/j.nucengdes.2008.07.022

DO - 10.1016/j.nucengdes.2008.07.022

M3 - Article

VL - 240

SP - 385

EP - 396

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

SN - 0029-5493

IS - 2

ER -