FFTF thermal-stratification results during transition flow
Data from pre-operational testing of FFTF revealed two unexpected thermal-hydraulic phenomena. The first phenomenon, outlet plenum thermal stratification, was investigated for impact on component thermal stresses and peak cladding temperature. All measured thermal transients were found to meet the design thermal transient limits. However, future LMFBR designs should account for stratification in developing outlet plenum design thermal transients. Second, thermal stratification in the primary hot leg piping was observed after loss-of-flow transients. The resulting temperature gradient, however, was sufficiently small so that thermal stress limits in the piping were not exceeded. Use of the Richardson Number may provide estimates of extent of piping stratification in future plant designs.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 6243851
- Report Number(s):
- HEDL-SA-2807; CONF-830132-3; ON: DE83012149
- Resource Relation:
- Conference: Specialists meeting on liquid metal thermal hydraulics in plena and pipes, Sunnyvale, CA, USA, 17 Jan 1983; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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FFTF REACTOR
HEAT TRANSFER
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LOSS OF FLOW
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TEMPERATURE GRADIENTS
THERMAL STRESSES
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SODIUM COOLED REACTORS
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