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

Publication Type : Conference Proceedings

Publisher : ASMEDC

Source : Volume 4: Fluid-Structure Interaction

Url : https://doi.org/10.1115/pvp2009-77442

Campus : Coimbatore

School : School of Engineering

Year : 2009

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.

Cite this Research Publication : Raju Ananth, Karen Fujikawa, Jay Gillis, Fluid Flow Field in the Annulus of Boiling Water (BWR) Nuclear Reactors Under Normal and Accident Conditions, Volume 4: Fluid-Structure Interaction, ASMEDC, 2009, https://doi.org/10.1115/pvp2009-77442

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