Fast Flux Test Facility sodium pump operating experience - mechanical
Conference
·
OSTI ID:6956787
The Heat Transport System (HTS) pumps were designed, fabricated, tested, and installed in the Fast Flux Test Facility (FFTF) Plant during the period from September 1970 through July 1977. Since completion of the installation and sodium fill in December 1978, the FFTF Plant pumps have undergone extensive testing and operation with HTS testing and reactor operation. Steady-state hydraulic and mechanical performances have been and are excellent. In all, FFTF primary and secondary pumps have operated in sodium for approximately 75,000 hours and 79,000 hours, respectively, to August 24, 1987.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 6956787
- Report Number(s):
- WHC-SA-0144; CONF-871199-3; ON: DE88011947
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ALKALI METALS
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FLUIDS
LIQUID METAL COOLED REACTORS
LIQUID METALS
LIQUIDS
MATERIALS
METALS
OPERATION
PERFORMANCE
PRIMARY COOLANT CIRCUITS
PUMPS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
REACTOR OPERATION
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SECONDARY COOLANT CIRCUITS
SODIUM
SODIUM COOLED REACTORS
TEST REACTORS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ALKALI METALS
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FLUIDS
LIQUID METAL COOLED REACTORS
LIQUID METALS
LIQUIDS
MATERIALS
METALS
OPERATION
PERFORMANCE
PRIMARY COOLANT CIRCUITS
PUMPS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
REACTOR OPERATION
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SECONDARY COOLANT CIRCUITS
SODIUM
SODIUM COOLED REACTORS
TEST REACTORS