Thermal-hydraulic characteristics in a liquid-metal fast breeder reactor hot plenum
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:6029876
The most important problem in the thermal-hydraulic designs of the pool-type fast breeder reactor is to estimate the thermal conditions affecting the vessel and/or internal structures during both steady and transient operations. The severity of these conditions in the Japanese pool-type reactor, which will be reinforced and equipped with special devices for seismic demands, is apt to be much greater than for other countries. Water tests and thermal-hydraulic analyses have been performed to study such conditions. The effects of the elevations of upper internal structure discharge and intermediate heat exchanger intakes on flow patterns, free surface disturbance, and thermal stratification in the hot plenum have been estimated. From the results of the experiments, suitable elevations could be recommended by comparing some thermal-hydraulic characteristics. The calculations agreed well with the experimental results for the steady-state flow patterns and thermal transients, with the exception of thermal stratification.
- Research Organization:
- Central Research Inst. of Electric Power Industry, (CRIEPI), Tokyo
- OSTI ID:
- 6029876
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 88:3; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Study of thermal stratification phenomena in an LMFBR hot plenum
Numerical Experiments of Coolant Mixing in a Lower Plenum of PWR Under Asymmetric Thermal- Hydraulics Conditions
Open upper plenum of LOF thermal hydraulics and inherent control rod insertion
Conference
·
Thu Oct 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5664027
Numerical Experiments of Coolant Mixing in a Lower Plenum of PWR Under Asymmetric Thermal- Hydraulics Conditions
Conference
·
Sat Jul 01 00:00:00 EDT 2006
·
OSTI ID:20995481
Open upper plenum of LOF thermal hydraulics and inherent control rod insertion
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6664802
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CONTAINERS
DESIGN
DISTURBANCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
HEAT EXCHANGERS
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
POOL TYPE REACTORS
PRESSURE VESSELS
REACTORS
SEISMIC EFFECTS
STEADY-STATE CONDITIONS
THERMODYNAMICS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CONTAINERS
DESIGN
DISTURBANCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
HEAT EXCHANGERS
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
POOL TYPE REACTORS
PRESSURE VESSELS
REACTORS
SEISMIC EFFECTS
STEADY-STATE CONDITIONS
THERMODYNAMICS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS