Thermal-hydraulic experiments and code validation (TOKE)

Condensation pool experiments with non-condensable gas and Fluent 5 simulations

Jani Laine, Minna Tuomainen

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

Abstract

The formation, size and distribution of non-condensable gas bubbles in the condensation pool of the Olkiluoto nuclear power plant (NPP) in a conceivable loss-of-coolant accident (LOCA) was studied experimentally with a scaled down condensation pool test rig. Particularly, it was important to find out if any air bubbles flowed inside the emergency core cooling system (ECCS) strainer close to the pool wall and bottom. The effect of non-condensable gas on the performance of an ECCS pump was also examined. Computational fluid dynamics (CFD) calculations with the Fluent 5 code were made to support the design of the test rig and the planning of the experiments. Compressed air was blown to the test pool through blowdown pipes or, alternatively, air was injected directly into the intake pipe of the ECCS pump. The first large air bubbles forming at the blowdown pipe outlet touched the ECCS strainer. When two blowdown pipes were used simultaneously, a lot of air bubbles were detected inside the strainer during the first 30 seconds. A 3-7 % volume fraction of air injected directly into the pump intake pipe was enough to make the pump head and flow collapse.
Original languageEnglish
Title of host publicationFINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002
Subtitle of host publicationFinal Report
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages150-155
ISBN (Electronic)951-38-6086-8
ISBN (Print)951-38-6085-X
Publication statusPublished - 2002
MoE publication typeNot Eligible

Publication series

NameVTT Tiedotteita - Research Notes
PublisherVTT
Number2164
ISSN (Print)1235-0605
ISSN (Electronic)1455-0865

Fingerprint

Condensation
Cooling systems
Pipe
Hydraulics
Pumps
Air
Gases
Experiments
Loss of coolant accidents
Compressed air
Nuclear power plants
Volume fraction
Computational fluid dynamics
Hot Temperature
Planning

Cite this

Laine, J., & Tuomainen, M. (2002). Thermal-hydraulic experiments and code validation (TOKE): Condensation pool experiments with non-condensable gas and Fluent 5 simulations. In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report (pp. 150-155). Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2164
Laine, Jani ; Tuomainen, Minna. / Thermal-hydraulic experiments and code validation (TOKE) : Condensation pool experiments with non-condensable gas and Fluent 5 simulations. FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo : VTT Technical Research Centre of Finland, 2002. pp. 150-155 (VTT Tiedotteita - Research Notes; No. 2164).
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Laine, J & Tuomainen, M 2002, Thermal-hydraulic experiments and code validation (TOKE): Condensation pool experiments with non-condensable gas and Fluent 5 simulations. in FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita - Research Notes, no. 2164, pp. 150-155.

Thermal-hydraulic experiments and code validation (TOKE) : Condensation pool experiments with non-condensable gas and Fluent 5 simulations. / Laine, Jani; Tuomainen, Minna.

FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo : VTT Technical Research Centre of Finland, 2002. p. 150-155 (VTT Tiedotteita - Research Notes; No. 2164).

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

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AB - The formation, size and distribution of non-condensable gas bubbles in the condensation pool of the Olkiluoto nuclear power plant (NPP) in a conceivable loss-of-coolant accident (LOCA) was studied experimentally with a scaled down condensation pool test rig. Particularly, it was important to find out if any air bubbles flowed inside the emergency core cooling system (ECCS) strainer close to the pool wall and bottom. The effect of non-condensable gas on the performance of an ECCS pump was also examined. Computational fluid dynamics (CFD) calculations with the Fluent 5 code were made to support the design of the test rig and the planning of the experiments. Compressed air was blown to the test pool through blowdown pipes or, alternatively, air was injected directly into the intake pipe of the ECCS pump. The first large air bubbles forming at the blowdown pipe outlet touched the ECCS strainer. When two blowdown pipes were used simultaneously, a lot of air bubbles were detected inside the strainer during the first 30 seconds. A 3-7 % volume fraction of air injected directly into the pump intake pipe was enough to make the pump head and flow collapse.

M3 - Chapter or book article

SN - 951-38-6085-X

T3 - VTT Tiedotteita - Research Notes

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BT - FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002

PB - VTT Technical Research Centre of Finland

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Laine J, Tuomainen M. Thermal-hydraulic experiments and code validation (TOKE): Condensation pool experiments with non-condensable gas and Fluent 5 simulations. In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report. Espoo: VTT Technical Research Centre of Finland. 2002. p. 150-155. (VTT Tiedotteita - Research Notes; No. 2164).