Published 2018 | Version v1
Book

CHF modeling in annular two phase flow

  • 1. Reactor Engineering Division, Bhabha Atomic Research Centre, Mumbai (India)

Description

Annular two-phase flow of coolant is encountered in Boiling Water Reactors (BWRs) during normal operation. A practical limit to operation in this regime is attained when the thin annular film of water dries out. Under those conditions, the heat transfer to the coolant deteriorates drastically leading to surface temperature shoot up. This is known as dryout - the mechanism for Critical Heat Flux (CHF) in annular two-phase flow. Due to its importance in establishing the safety margins of BWRs, accurate dryout prediction is essential. Along with prediction results for rod bundles, the paper gives details of methodology and assumptions used by the authors for mechanistic modeling of annular flow in rod bundles. The shortcomings of the present model are identified and scopes for further studies are suggested

Part of:
Proceedings of the national conference on critical heat flux and multiphase flow: abstracts

Additional details

Publishing Information

Publisher
Excel India Publishers
Imprint Place
New Delhi (India)
ISBN
978-93-88237-33-8
Imprint Title
Proceedings of the national conference on critical heat flux and multiphase flow: abstracts
Imprint Pagination
136 p.
Journal Page Range
p. 10-11

Conference

Title
National conference on critical heat flux and multiphase flow
Dates
22-23 Dec 2018
Place
Varanasi (India)

Optional Information