Flow visualization study of inverted annular flow of post dryout heat transfer region. [PWR; BWR]
The inverted annular flow is important in the area of LWR accident analysis in terms of the maximum cladding temperature and effectiveness of the emergency core cooling. However, the inverted annular flow thermal-hydraulics is not well understood due to its special heat transfer condition of film boiling. The review of existing data indicates further research is needed in the areas of basic hydrodynamics related to liquid core disintegration mechanisms, slug and droplet formation, entrainment, and droplet size distributions. In view of this, the inverted flow is studied in detail experimentally. A new experimental apparatus has been constructed in which film boiling heat transfer can be established in a transparent test section. The test section consists of two coaxial quartz tubes. The annular gap between these two tubes is filled with a hot, clear fluid (syltherm 800) so as to maintain film boiling temperatures and heat transfer rates at the inner quartz tube wall. Data on liquid core stability, core break-up mechanism, and dispersed-core liquid slug and droplet sizes are obtained using F 113 as a test fluid. Both high speed movies and flash photographs (3 ..mu..sec) are used.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5843130
- Report Number(s):
- CONF-851007-7; ON: DE85010482
- Resource Relation:
- Conference: 3. international meeting on reactor thermal hydraulics, Newport, RI, USA, 15 Oct 1985
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
ECCS
REACTOR ACCIDENTS
HEAT TRANSFER
HYDRAULICS
HYDRODYNAMICS
PWR TYPE REACTORS
CRITICAL HEAT FLUX
DRYOUT
FILM BOILING
REACTOR SAFETY
TEST FACILITIES
ACCIDENTS
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FLUID MECHANICS
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