Fracture assessment of reactor circuit (FRAS)

Simulation of thermal striping in a HDR experiment

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

Abstract

Computational Fluid Dynamics (CFD) calculations of thermal striping in a HDR (Heißdampfreaktor) experiment were performed with the commercial Star-CD code. In the experiment, temperature fluctuations caused by instability between layers of cold and hot water flowing in a horizontal pipe were studied. Large-Eddy Simulation (LES) with the Smagorinsky sub-grid scale model was mainly used for turbulence modelling. The vortex method was implemented and validated for simple pipe flow in order to have realistic turbulent inlet conditions for LES. Different geometries and meshes for simulating the experiment were tested. Results obtained with realistic geometry seemed qualitatively correct but the magnitude of temperature fluctuations was too low. This could be connected to too coarse mesh in the model.
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
Pages395-402
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

Circuit simulation
Large eddy simulation
Geometry
Experiments
Pipe flow
Stars
Computational fluid dynamics
Vortex flow
Turbulence
Pipe
Temperature
Hot Temperature
Water

Cite this

Timperi, A. (2009). Fracture assessment of reactor circuit (FRAS): Simulation of thermal striping in a HDR experiment. In SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010 : Interim Report (pp. 395-402). Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2466
Timperi, Antti. / Fracture assessment of reactor circuit (FRAS) : Simulation of thermal striping in a HDR experiment. SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010 : Interim Report . Espoo : VTT Technical Research Centre of Finland, 2009. pp. 395-402 (VTT Tiedotteita - Research Notes; No. 2466).
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author = "Antti Timperi",
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series = "VTT Tiedotteita - Research Notes",
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Timperi, A 2009, Fracture assessment of reactor circuit (FRAS): Simulation of thermal striping in a HDR experiment. 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. 395-402.

Fracture assessment of reactor circuit (FRAS) : Simulation of thermal striping in a HDR experiment. / Timperi, Antti.

SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010 : Interim Report . Espoo : VTT Technical Research Centre of Finland, 2009. p. 395-402 (VTT Tiedotteita - Research Notes; No. 2466).

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

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T1 - Fracture assessment of reactor circuit (FRAS)

T2 - Simulation of thermal striping in a HDR experiment

AU - Timperi, Antti

PY - 2009

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N2 - Computational Fluid Dynamics (CFD) calculations of thermal striping in a HDR (Heißdampfreaktor) experiment were performed with the commercial Star-CD code. In the experiment, temperature fluctuations caused by instability between layers of cold and hot water flowing in a horizontal pipe were studied. Large-Eddy Simulation (LES) with the Smagorinsky sub-grid scale model was mainly used for turbulence modelling. The vortex method was implemented and validated for simple pipe flow in order to have realistic turbulent inlet conditions for LES. Different geometries and meshes for simulating the experiment were tested. Results obtained with realistic geometry seemed qualitatively correct but the magnitude of temperature fluctuations was too low. This could be connected to too coarse mesh in the model.

AB - Computational Fluid Dynamics (CFD) calculations of thermal striping in a HDR (Heißdampfreaktor) experiment were performed with the commercial Star-CD code. In the experiment, temperature fluctuations caused by instability between layers of cold and hot water flowing in a horizontal pipe were studied. Large-Eddy Simulation (LES) with the Smagorinsky sub-grid scale model was mainly used for turbulence modelling. The vortex method was implemented and validated for simple pipe flow in order to have realistic turbulent inlet conditions for LES. Different geometries and meshes for simulating the experiment were tested. Results obtained with realistic geometry seemed qualitatively correct but the magnitude of temperature fluctuations was too low. This could be connected to too coarse mesh in the model.

M3 - Chapter or book article

SN - 978-951-38-7266-3

T3 - VTT Tiedotteita - Research Notes

SP - 395

EP - 402

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

PB - VTT Technical Research Centre of Finland

CY - Espoo

ER -

Timperi A. Fracture assessment of reactor circuit (FRAS): Simulation of thermal striping in a HDR experiment. In SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010 : Interim Report . Espoo: VTT Technical Research Centre of Finland. 2009. p. 395-402. (VTT Tiedotteita - Research Notes; No. 2466).