Improved thermal hydraulic analyses of nuclear reactor and containment (THARE)

APROS CCFL model validation

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

Abstract

The upper tie plate countercurrent flow limitation correlation of APROS was validated against experimental data obtained at a full-scale test facility representing the upper tie plate of the VVER-440 fuel channel. Water and air treated as non-condensable gas were used as the fluids in the simulation. Values for the free parameters of the CCFL correlation were first defined, and then two experiments with different pressures were simulated. The simulation results show good agreement with the experimental results for the mass flow rates for which a quasi-stationary state could be established in the simulation software.
Original languageEnglish
Title of host publicationSAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010
Subtitle of host publicationInterim Report
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages182-190
ISBN (Electronic)978-951-38-7267-0
ISBN (Print)978-951-38-7266-3
Publication statusPublished - 2009
MoE publication typeNot Eligible

Publication series

NameVTT Tiedotteita - Research Notes
PublisherVTT
Number2466
ISSN (Print)1235-0605
ISSN (Electronic)1455-0865

Fingerprint

model validation
containment
hydraulics
simulation
countercurrent
software
fluid
air
gas
nuclear reactor
experiment
water

Cite this

Kurki, J. (2009). Improved thermal hydraulic analyses of nuclear reactor and containment (THARE): APROS CCFL model validation. In SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010: Interim Report (pp. 182-190). Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2466
Kurki, Joona. / Improved thermal hydraulic analyses of nuclear reactor and containment (THARE) : APROS CCFL model validation. SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010: Interim Report . Espoo : VTT Technical Research Centre of Finland, 2009. pp. 182-190 (VTT Tiedotteita - Research Notes; No. 2466).
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abstract = "The upper tie plate countercurrent flow limitation correlation of APROS was validated against experimental data obtained at a full-scale test facility representing the upper tie plate of the VVER-440 fuel channel. Water and air treated as non-condensable gas were used as the fluids in the simulation. Values for the free parameters of the CCFL correlation were first defined, and then two experiments with different pressures were simulated. The simulation results show good agreement with the experimental results for the mass flow rates for which a quasi-stationary state could be established in the simulation software.",
author = "Joona Kurki",
year = "2009",
language = "English",
isbn = "978-951-38-7266-3",
series = "VTT Tiedotteita - Research Notes",
publisher = "VTT Technical Research Centre of Finland",
number = "2466",
pages = "182--190",
booktitle = "SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010",
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Kurki, J 2009, Improved thermal hydraulic analyses of nuclear reactor and containment (THARE): APROS CCFL model validation. in SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010: Interim Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita - Research Notes, no. 2466, pp. 182-190.

Improved thermal hydraulic analyses of nuclear reactor and containment (THARE) : APROS CCFL model validation. / Kurki, Joona.

SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010: Interim Report . Espoo : VTT Technical Research Centre of Finland, 2009. p. 182-190 (VTT Tiedotteita - Research Notes; No. 2466).

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

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T1 - Improved thermal hydraulic analyses of nuclear reactor and containment (THARE)

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PY - 2009

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AB - The upper tie plate countercurrent flow limitation correlation of APROS was validated against experimental data obtained at a full-scale test facility representing the upper tie plate of the VVER-440 fuel channel. Water and air treated as non-condensable gas were used as the fluids in the simulation. Values for the free parameters of the CCFL correlation were first defined, and then two experiments with different pressures were simulated. The simulation results show good agreement with the experimental results for the mass flow rates for which a quasi-stationary state could be established in the simulation software.

M3 - Chapter or book article

SN - 978-951-38-7266-3

T3 - VTT Tiedotteita - Research Notes

SP - 182

EP - 190

BT - SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010

PB - VTT Technical Research Centre of Finland

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Kurki J. Improved thermal hydraulic analyses of nuclear reactor and containment (THARE): APROS CCFL model validation. In SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010: Interim Report . Espoo: VTT Technical Research Centre of Finland. 2009. p. 182-190. (VTT Tiedotteita - Research Notes; No. 2466).