Conference
Validation of fluent software for prediction of flow distribution and pressure gradients in a multi-branch flow header
Abstract
Flow headers are commonly used in nuclear reactors, boilers and heat exchangers to distribute fluid to small branches along the body of the header or to combine flow from the branches along the header. Historically, nuclear safety analysis has been performed using one-dimensional averaged system codes, and as such the distribution headers are cross-sectionally averaged. In this paper, flow distribution and pressure gradients along a …
Authors
Muhana A; Novog D
Volume
1
Pagination
pp. 390-403
Publication Date
December 1, 2008
Conference proceedings
Canadian Nuclear Society 29th Annual Conference of the Canadian Nuclear Society and 32nd CNS Cna Student Conference 2008