Skip to main content
Article
Prediction of Interfacial Area Transport in a Scaled 8x8 BWR Rod Bundle
Nuclear Engineering and Design
  • X. Yang
  • Joshua P. Schlegel, Missouri University of Science and Technology
  • Y. Liu
  • S. Paranjape
  • T. Hibiki
  • M. Ishii
  • S. Bajorek
  • A. Ireland
Abstract

In the two-fluid model, it is important to give an accurate prediction for the interfacial area concentration. In order to achieve this goal, the interfacial area transport equation has been developed. This study focuses on the benchmark of IATE performance in a rod bundle geometry. A set of interfacial area concentration source and sink term models are proposed for a rod bundle geometry based on the confined channel IATE model. This model was selected as a basis because of the relative similarity of the two geometries. Benchmarking of the new model with interfacial area concentration data in an 8x8 rod bundle test section which has been scaled from an actual BWR fuel bundle is performed. The model shows good agreement in bubbly and cap-bubbly flows, which are similar in many types of geometries, while it shows some discrepancy in churn-turbulent flow regime. This discrepancy may be due to the geometrical differences between the actual rod bundle test facility and the facility used to collect the data which benchmarked the original source and sink models.

Department(s)
Nuclear Engineering and Radiation Science
Keywords and Phrases
  • Benchmarking,
  • Boiling water reactors,
  • Geometry,
  • Accurate prediction,
  • Churn-turbulent flow regime,
  • Geometrical differences,
  • Interfacial area concentrations,
  • Interfacial area transport equation,
  • Interfacial area transports,
  • Rod bundles,
  • Two fluid model,
  • Two phase flow,
  • Two-phase flow
Document Type
Article - Journal
Document Version
Citation
File Type
text
Language(s)
English
Rights
© 2016 Elsevier, All rights reserved.
Publication Date
12-1-2016
Publication Date
01 Dec 2016
Disciplines
Citation Information
X. Yang, Joshua P. Schlegel, Y. Liu, S. Paranjape, et al.. "Prediction of Interfacial Area Transport in a Scaled 8x8 BWR Rod Bundle" Nuclear Engineering and Design Vol. 310 (2016) p. 638 - 647 ISSN: 0029-5493
Available at: http://works.bepress.com/joshua-schlegel/68/