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Fluid Flow Field in the Annulus of Boiling Water (BWR) Nuclear Reactors Under Normal and Accident Conditions

[+] Author Affiliations
Raju Ananth, Jay Gillis

Structural Integrity Associates, Inc., San Jose, CA

Karen Fujikawa

Structural Integrity Associates, Inc., Centennial, CO

Paper No. PVP2009-77442, pp. 63-73; 11 pages
doi:10.1115/PVP2009-77442
From:
  • ASME 2009 Pressure Vessels and Piping Conference
  • Volume 4: Fluid-Structure Interaction
  • Prague, Czech Republic, July 26–30, 2009
  • Conference Sponsors: Pressure Vessels and Piping
  • ISBN: 978-0-7918-4367-3 | eISBN: 978-0-7918-3854-9
  • Copyright © 2009 by ASME

abstract

This paper presents a theoretical study of the velocity field in the annulus formed between the Reactor Pressure Vessel (RPV) and the shroud of a Boiling Water Reactor (BWR) under normal and accident flow conditions. Simplified geometry and an ideal irrotational flow are assumed to solve the problem using velocity potentials.

Copyright © 2009 by ASME

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