Validation of fluid-structure interaction calculations in a large-break loss of coolant accident

Antti Timperi, Timo Pättikangas, Ismo Karppinen, Ville Lestinen, Jukka Kähkönen, Timo Toppila

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

6 Citations (Scopus)

Abstract

In the hypothetical LargeBreak Loss Of Coolant Accident (LBLOCA), rapid depressurization of the reactor primary circuit causes loads on the reactor internals. This paper presents numerical simulations of a HDR experiment, where LBLOCA of a pressurized water reactor due to a sudden pipe break in the primary loop was studied. In the experiment, FluidStructure Interaction (FSI) phenomena caused by the flexibility of the core barrel were studied in particular. StarCD Computational Fluid Dynamics (CFD) code and ABAQUS structural analysis code were used for threedimensional calculations. The MpCCI code was used for twoway coupling of the CFD and structural analysis codes in order to take FSI into account. Twoway FSI calculation was also performed with ABAQUS only by modeling water as an acoustic medium. Pressure boundary condition at the pipe break was evaluated with the system code APROS as a twophase calculation. Comparisons with the experiment were made for fluid pressures and break mass flow as well as for structural displacements and strains. Fairly good agreement was found between the experiment and simulation when coupling of the CFD and structural analysis codes was used. For the acoustic calculation, the results showed good agreement in the early phase of the simulation. In the late phase, structural loads were overpredicted by the acoustic calculation due to the effect of bulk flow of water which is not included in the acoustic model.
Original languageEnglish
Title of host publicationProceedings of the 16th International Conference on Nuclear Engineering, ICONE16 2008
Place of PublicationOrlando, Florida
PublisherAmerican Society of Mechanical Engineers ASME
Pages245-254
ISBN (Print)978-0-7918-3820-4
Publication statusPublished - 2008
MoE publication typeA4 Article in a conference publication
Event16th International Conference on Nuclear Engineering, ICONE-16 - Orlando, Florida, United States
Duration: 11 May 200815 May 2008

Conference

Conference16th International Conference on Nuclear Engineering, ICONE-16
Abbreviated titleICONE16
CountryUnited States
CityOrlando, Florida
Period11/05/0815/05/08

Fingerprint

Loss of coolant accidents
Fluid structure interaction
Acoustics
Structural analysis
Computational fluid dynamics
ABAQUS
Dynamic analysis
Experiments
Pipe
Structural loads
Flow of water
Pressurized water reactors
Boundary conditions
Fluids
Networks (circuits)
Computer simulation
Water

Cite this

Timperi, A., Pättikangas, T., Karppinen, I., Lestinen, V., Kähkönen, J., & Toppila, T. (2008). Validation of fluid-structure interaction calculations in a large-break loss of coolant accident. In Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16 2008 (pp. 245-254). Orlando, Florida: American Society of Mechanical Engineers ASME.
Timperi, Antti ; Pättikangas, Timo ; Karppinen, Ismo ; Lestinen, Ville ; Kähkönen, Jukka ; Toppila, Timo. / Validation of fluid-structure interaction calculations in a large-break loss of coolant accident. Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16 2008. Orlando, Florida : American Society of Mechanical Engineers ASME, 2008. pp. 245-254
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abstract = "In the hypothetical LargeBreak Loss Of Coolant Accident (LBLOCA), rapid depressurization of the reactor primary circuit causes loads on the reactor internals. This paper presents numerical simulations of a HDR experiment, where LBLOCA of a pressurized water reactor due to a sudden pipe break in the primary loop was studied. In the experiment, FluidStructure Interaction (FSI) phenomena caused by the flexibility of the core barrel were studied in particular. StarCD Computational Fluid Dynamics (CFD) code and ABAQUS structural analysis code were used for threedimensional calculations. The MpCCI code was used for twoway coupling of the CFD and structural analysis codes in order to take FSI into account. Twoway FSI calculation was also performed with ABAQUS only by modeling water as an acoustic medium. Pressure boundary condition at the pipe break was evaluated with the system code APROS as a twophase calculation. Comparisons with the experiment were made for fluid pressures and break mass flow as well as for structural displacements and strains. Fairly good agreement was found between the experiment and simulation when coupling of the CFD and structural analysis codes was used. For the acoustic calculation, the results showed good agreement in the early phase of the simulation. In the late phase, structural loads were overpredicted by the acoustic calculation due to the effect of bulk flow of water which is not included in the acoustic model.",
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Timperi, A, Pättikangas, T, Karppinen, I, Lestinen, V, Kähkönen, J & Toppila, T 2008, Validation of fluid-structure interaction calculations in a large-break loss of coolant accident. in Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16 2008. American Society of Mechanical Engineers ASME, Orlando, Florida, pp. 245-254, 16th International Conference on Nuclear Engineering, ICONE-16, Orlando, Florida, United States, 11/05/08.

Validation of fluid-structure interaction calculations in a large-break loss of coolant accident. / Timperi, Antti; Pättikangas, Timo; Karppinen, Ismo; Lestinen, Ville; Kähkönen, Jukka; Toppila, Timo.

Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16 2008. Orlando, Florida : American Society of Mechanical Engineers ASME, 2008. p. 245-254.

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

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T1 - Validation of fluid-structure interaction calculations in a large-break loss of coolant accident

AU - Timperi, Antti

AU - Pättikangas, Timo

AU - Karppinen, Ismo

AU - Lestinen, Ville

AU - Kähkönen, Jukka

AU - Toppila, Timo

PY - 2008

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N2 - In the hypothetical LargeBreak Loss Of Coolant Accident (LBLOCA), rapid depressurization of the reactor primary circuit causes loads on the reactor internals. This paper presents numerical simulations of a HDR experiment, where LBLOCA of a pressurized water reactor due to a sudden pipe break in the primary loop was studied. In the experiment, FluidStructure Interaction (FSI) phenomena caused by the flexibility of the core barrel were studied in particular. StarCD Computational Fluid Dynamics (CFD) code and ABAQUS structural analysis code were used for threedimensional calculations. The MpCCI code was used for twoway coupling of the CFD and structural analysis codes in order to take FSI into account. Twoway FSI calculation was also performed with ABAQUS only by modeling water as an acoustic medium. Pressure boundary condition at the pipe break was evaluated with the system code APROS as a twophase calculation. Comparisons with the experiment were made for fluid pressures and break mass flow as well as for structural displacements and strains. Fairly good agreement was found between the experiment and simulation when coupling of the CFD and structural analysis codes was used. For the acoustic calculation, the results showed good agreement in the early phase of the simulation. In the late phase, structural loads were overpredicted by the acoustic calculation due to the effect of bulk flow of water which is not included in the acoustic model.

AB - In the hypothetical LargeBreak Loss Of Coolant Accident (LBLOCA), rapid depressurization of the reactor primary circuit causes loads on the reactor internals. This paper presents numerical simulations of a HDR experiment, where LBLOCA of a pressurized water reactor due to a sudden pipe break in the primary loop was studied. In the experiment, FluidStructure Interaction (FSI) phenomena caused by the flexibility of the core barrel were studied in particular. StarCD Computational Fluid Dynamics (CFD) code and ABAQUS structural analysis code were used for threedimensional calculations. The MpCCI code was used for twoway coupling of the CFD and structural analysis codes in order to take FSI into account. Twoway FSI calculation was also performed with ABAQUS only by modeling water as an acoustic medium. Pressure boundary condition at the pipe break was evaluated with the system code APROS as a twophase calculation. Comparisons with the experiment were made for fluid pressures and break mass flow as well as for structural displacements and strains. Fairly good agreement was found between the experiment and simulation when coupling of the CFD and structural analysis codes was used. For the acoustic calculation, the results showed good agreement in the early phase of the simulation. In the late phase, structural loads were overpredicted by the acoustic calculation due to the effect of bulk flow of water which is not included in the acoustic model.

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SP - 245

EP - 254

BT - Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16 2008

PB - American Society of Mechanical Engineers ASME

CY - Orlando, Florida

ER -

Timperi A, Pättikangas T, Karppinen I, Lestinen V, Kähkönen J, Toppila T. Validation of fluid-structure interaction calculations in a large-break loss of coolant accident. In Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16 2008. Orlando, Florida: American Society of Mechanical Engineers ASME. 2008. p. 245-254