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
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)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 52014724
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CRITICAL HEAT FLUX; DRYOUT; FUEL ELEMENT CLUSTERS; REACTOR COOLING SYSTEMS; TWO-PHASE FLOW
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; HEAT FLUX; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS