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CFD analysis of a void distribution benchmark in a rod bundle

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Published/Copyright: August 22, 2013
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Kerntechnik
From the journal Kerntechnik Volume 78 Issue 1

Abstract

The NUPEC “PWR Subchannel and Bundle Tests” (PSBT) were designed to investigate critical heat flux phenomena in rod bundles and yield data to validate hot channel codes. Some of the tests are suitable for validating a CFD wall boiling model. The paper presents CFD calculations of the void distribution tests of the PSBT benchmark using ANSYS CFX-12.1. First, relevant aspects of the implemented wall boiling model are reviewed highlighting the uncertainties in several model parameters. It is then shown that the measured cross sectionally averaged values can be reproduced well with a single set of calibrated model parameters for different tests cases. For the reproduction of patterns of void distribution cross sections attention has to be focussed on the modelling of turbulence in the narrow channel. Only a turbulence model with the capability to resolve turbulent secondary flows is able to reproduce at least qualitatively the observed void distribution patterns.

Kurzfassung

Die NUPEC “PWR Subchannel and Bundle Tests” (PSBT) waren zur Untersuchung kritischer Wärmestromphänomene in Brennelementbündeln und zur Validierung von Heißkanalcodes ausgelegt. Einige der Tests sind zur Validierung von CFD-Wandsiedemodellen geeignet. Die Arbeit präsentiert CFD-Analysen der Gasgehaltsverteilung unter Verwendung des CFD-Codes ANSYS CFX-12.1. Zunächst werden die wichtigsten Aspekte des implementierten Modells und Unsicherheiten der Modellparameter herausgestellt. Es kann gezeigt werden, dass die gemessenen querschnittsgemittelten Messwerte mit einem Satz im Rahmen der Modellunsicherheiten kalibrierter Modellparameter reproduziert werden kann. Für die Reproduktion der Verteilungsmuster des Dampfgehaltes im Kanalquerschnitt muss die Modellierung der Turbulenz beachtet werden. Nur ein Turbulenzmodell, das die turbulenten Sekundärströmungen auflösen kann, ist in der Lage, die beobachteten Verteilungsmuster zu reproduzieren.

3 Dr. Eckhard Krepper, E-mail:

References

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Received: 2012-11-2
Published Online: 2013-08-22
Published in Print: 2013-03-19

© 2013, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Editorial
  6. Actual status of the research alliances “Condensation Induced Water Hammer” and “Boiling processes in Pressurized Water Reactors”
  7. Technical Contributions/Fachbeiträge
  8. High-resolution two-phase flow measurement techniques for the generation of experimental data for CFD code qualification
  9. Condensation induced water hammer (CIWH) – relevance in the nuclear industry and state of science and technology
  10. Experiments of condensation-induced water hammers at the UniBw Munich
  11. Development of a 1 D hybrid HTC model using CFD simulations for the analysis of direct contact condensation as the driving force for water hammers
  12. 1D Models for Condensation Induced Water Hammer in Pipelines
  13. Modelling, simulation and experiments on boiling processes in pressurized water reactors
  14. CFD analysis of a void distribution benchmark in a rod bundle
  15. CFD-modelling of subcooled boiling
  16. On the pair correlation function in a bubble swarm
  17. Large Eddy Simulation of the shear flow instability in a rod-bundle assembly
  18. Small scale boiling experiments using two-dimensional imaging with high-speed camera and optical coherence tomography
  19. Validation of mechanistic CHF models using optical measuring techniques
  20. Experimental investigations of single and two-phase flow in a heated rod bundle
  21. CFD-Modeling of turbulent flows in rod bundle and comparison to experiments
  22. About the change in boiling behaviour of water with coolant additives in PWR
  23. Simulation of external reactor vessel cooling in a lumped-parameter code
https://doi.org/10.3139/124.110310

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Editorial
  6. Actual status of the research alliances “Condensation Induced Water Hammer” and “Boiling processes in Pressurized Water Reactors”
  7. Technical Contributions/Fachbeiträge
  8. High-resolution two-phase flow measurement techniques for the generation of experimental data for CFD code qualification
  9. Condensation induced water hammer (CIWH) – relevance in the nuclear industry and state of science and technology
  10. Experiments of condensation-induced water hammers at the UniBw Munich
  11. Development of a 1 D hybrid HTC model using CFD simulations for the analysis of direct contact condensation as the driving force for water hammers
  12. 1D Models for Condensation Induced Water Hammer in Pipelines
  13. Modelling, simulation and experiments on boiling processes in pressurized water reactors
  14. CFD analysis of a void distribution benchmark in a rod bundle
  15. CFD-modelling of subcooled boiling
  16. On the pair correlation function in a bubble swarm
  17. Large Eddy Simulation of the shear flow instability in a rod-bundle assembly
  18. Small scale boiling experiments using two-dimensional imaging with high-speed camera and optical coherence tomography
  19. Validation of mechanistic CHF models using optical measuring techniques
  20. Experimental investigations of single and two-phase flow in a heated rod bundle
  21. CFD-Modeling of turbulent flows in rod bundle and comparison to experiments
  22. About the change in boiling behaviour of water with coolant additives in PWR
  23. Simulation of external reactor vessel cooling in a lumped-parameter code
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