Published 1996
| Version v1
Book
A review of phenomenological models for predicting critical heat flux in flow boiling
Description
In a water cooled nuclear reactor, fuel clad surface operates at a temperature close to the saturation temperature of water. Maximum heat flux levels are invariably very high. At the design stage, it has to be confirmed that under any likely situation, the heat flux does not exceed critical heat flux. To understand the phenomenon of critical heat flux, many phenomenological models have been developed and are reviewed in this paper. (author). 27 refs., 15 figs
Additional details
Publishing Information
- Publisher
- Tata McGraw-Hill Publishing Company Limited.
- Imprint Place
- New Delhi (India)
- ISBN
- 0-07-462307-9
- Imprint Title
- Heat and mass transfer 95
- Imprint Pagination
- 975 p.
- Journal Page Range
- p. 81-90.
Conference
- Title
- 2. ISHMT-ASME heat and mass transfer conference; 13. national heat and mass transfer conference.
- Dates
- 28-30 Dec 1995.
- Place
- Surathkal (India).
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 27075604
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOILING; BUBBLES; CRITICAL HEAT FLUX; DESIGN; DRYOUT; FILMS; FLOW MODELS; FLUID FLOW; HEAT TRANSFER; REVIEWS; WATER COOLED REACTORS
- Descriptors DEC
- DOCUMENT TYPES; ENERGY TRANSFER; HEAT FLUX; MATHEMATICAL MODELS; PHASE TRANSFORMATIONS; REACTORS