Study of thermal stratification phenomena in an LMFBR hot plenum
Compactness is needed for large liquid-metal fast breeder reactor plants to aid in cost reductions. The reactor vessel is particularly large, with a diameter that extends to 20 m, and includes the core, intermediate heat exchangers, pumps, and internal components. The reactor vessel must be made compact. To achieve this, thermal-hydraulic characteristics must be studied in order to provide a safe design. Sodium flow in the hot plenum affects plant dynamics and thermal shock to components. Thermal stratification, especially that occurring after a reactor scram in the hot plenum, and its steep temperature gradient cause thermal fatigue to internal components. Water and sodium negative buoyancy jets have already been studied with simple geometry. The object of this paper is to examine thermal stratification phenomena in a small model with a real hot plenum geometry, experimentally and analytically.
- Research Organization:
- Hitachi Ltd., Ibaraki, Japan
- OSTI ID:
- 5664027
- Report Number(s):
- CONF-851115-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 50; ISSN TANSA
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALKALI METALS
BREEDER REACTORS
CONTAINERS
DESIGN
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FATIGUE
FBR TYPE REACTORS
FLUID FLOW
HEAT EXCHANGERS
HEAT TRANSFER
HYDROGEN COMPOUNDS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICAL PROPERTIES
METALS
OXYGEN COMPOUNDS
PUMPS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTOR SHUTDOWN
REACTOR VESSELS
REACTORS
SAFETY
SCRAM
SHUTDOWNS
SODIUM
STRATIFICATION
TEMPERATURE GRADIENTS
THERMAL FATIGUE
THERMAL SHOCK
TRANSIENTS
WATER