Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE): Steam and helium mixture with a containment cooler, simulation of Panda facility experiment ST4.1 (THARE)

Risto Huhtanen, Ari Silde

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Abstract

An experiment of steam and helium injection and mixing, stratification and helium enrichment due to condensation of steam in a tube bundle cooler is simulated with a CFD-code Fluent and a lumper parameter code APROS Containment. The experimental facility PANDA simulates a two part compartment connected with a corridor. The qualitative comparison with experimental results is shown.
Original languageEnglish
Title of host publicationSAFIR2010
Subtitle of host publicationThe Finnish Research Programme on Safety 2007-2010: Final Report
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages216-224
ISBN (Electronic)978-951-38-7690-6
ISBN (Print)978-951-38-7689-0
Publication statusPublished - 2011
MoE publication typeNot Eligible

Publication series

SeriesVTT Tiedotteita - Research Notes
Number2571
ISSN1235-0605

Fingerprint

containment
nuclear reactors
coolers
steam
hydraulics
helium
corridors
compartments
charge flow devices
stratification
bundles
simulation
condensation
injection
tubes

Cite this

Huhtanen, R., & Silde, A. (2011). Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE): Steam and helium mixture with a containment cooler, simulation of Panda facility experiment ST4.1 (THARE). In SAFIR2010: The Finnish Research Programme on Safety 2007-2010: Final Report (pp. 216-224). Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2571
Huhtanen, Risto ; Silde, Ari. / Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE) : Steam and helium mixture with a containment cooler, simulation of Panda facility experiment ST4.1 (THARE). SAFIR2010: The Finnish Research Programme on Safety 2007-2010: Final Report. Espoo : VTT Technical Research Centre of Finland, 2011. pp. 216-224 (VTT Tiedotteita - Research Notes; No. 2571).
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abstract = "An experiment of steam and helium injection and mixing, stratification and helium enrichment due to condensation of steam in a tube bundle cooler is simulated with a CFD-code Fluent and a lumper parameter code APROS Containment. The experimental facility PANDA simulates a two part compartment connected with a corridor. The qualitative comparison with experimental results is shown.",
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Huhtanen, R & Silde, A 2011, Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE): Steam and helium mixture with a containment cooler, simulation of Panda facility experiment ST4.1 (THARE). in SAFIR2010: The Finnish Research Programme on Safety 2007-2010: Final Report. VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita - Research Notes, no. 2571, pp. 216-224.

Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE) : Steam and helium mixture with a containment cooler, simulation of Panda facility experiment ST4.1 (THARE). / Huhtanen, Risto; Silde, Ari.

SAFIR2010: The Finnish Research Programme on Safety 2007-2010: Final Report. Espoo : VTT Technical Research Centre of Finland, 2011. p. 216-224 (VTT Tiedotteita - Research Notes; No. 2571).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

TY - CHAP

T1 - Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE)

T2 - Steam and helium mixture with a containment cooler, simulation of Panda facility experiment ST4.1 (THARE)

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AU - Silde, Ari

PY - 2011

Y1 - 2011

N2 - An experiment of steam and helium injection and mixing, stratification and helium enrichment due to condensation of steam in a tube bundle cooler is simulated with a CFD-code Fluent and a lumper parameter code APROS Containment. The experimental facility PANDA simulates a two part compartment connected with a corridor. The qualitative comparison with experimental results is shown.

AB - An experiment of steam and helium injection and mixing, stratification and helium enrichment due to condensation of steam in a tube bundle cooler is simulated with a CFD-code Fluent and a lumper parameter code APROS Containment. The experimental facility PANDA simulates a two part compartment connected with a corridor. The qualitative comparison with experimental results is shown.

M3 - Chapter or book article

SN - 978-951-38-7689-0

T3 - VTT Tiedotteita - Research Notes

SP - 216

EP - 224

BT - SAFIR2010

PB - VTT Technical Research Centre of Finland

CY - Espoo

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Huhtanen R, Silde A. Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE): Steam and helium mixture with a containment cooler, simulation of Panda facility experiment ST4.1 (THARE). In SAFIR2010: The Finnish Research Programme on Safety 2007-2010: Final Report. Espoo: VTT Technical Research Centre of Finland. 2011. p. 216-224. (VTT Tiedotteita - Research Notes; No. 2571).