Empirical method to calculate Clinch River Breeder Reactor (CRBR) inlet plenum transient temperatures
Conference
·
OSTI ID:7177396
Sodium flow enters the CRBR inlet plenum via three loops or inlets. An empirical equation was developed to calculate transient temperatures in the CRBR inlet plenum from known loop flows and temperatures. The constants in the empirical equation were derived from 1/4 scale Inlet Plenum Model tests using water as the test fluid. The sodium temperature distribution was simulated by an electrolyte. Step electrolyte transients at 100 percent model flow were used to calculate the equation constants. Step electrolyte runs at 50 percent and 10 percent flow confirmed that the constants were independent of flow. Also, a transient was tested which varied simultaneously flow rate and electrolyte. Agreement of the test results with the empirical equation results was good which verifies the empirical equation.
- Research Organization:
- Westinghouse Electric Corp., Madison, Pa. (USA). Advanced Reactors Div.
- OSTI ID:
- 7177396
- Report Number(s):
- CONF-760816-8
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COOLING SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
MOCKUP
POWER REACTORS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SIMULATION
SODIUM COOLED REACTORS
STRUCTURAL MODELS
TEMPERATURE DISTRIBUTION
TRANSIENTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COOLING SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
MOCKUP
POWER REACTORS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SIMULATION
SODIUM COOLED REACTORS
STRUCTURAL MODELS
TEMPERATURE DISTRIBUTION
TRANSIENTS