Thermowell flow-induced vibrations measured in laboratory and FFTF plant piping
Conference
·
OSTI ID:6513510
This paper describes the various laboratory and field tests conducted to assure that flow-induced vibrations do not exist in the piping thermowells of the Fast Flux Test Facility. FFTF thermowells are subjected to a wide range of flowing sodium velocities during testing and operation. Early design work indicated a need to provide special attention to thermowell response in the drag direction at the higher sodium flow rates associated with FFTF testing. The results of this study provide some additional insight into response characteristics of a tube in liquid cross flow with emphasis on motion in the drag direction.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- DOE Contract Number:
- AC14-76FF02170
- OSTI ID:
- 6513510
- Report Number(s):
- HEDL-SA-2278-FP; CONF-810625-12; TRN: 81-010445
- Resource Relation:
- Conference: ASME PVP conference, Denver, CO, USA, 21 Jun 1981
- Country of Publication:
- United States
- Language:
- English
Similar Records
Scale-model characterization of flow-induced vibrational response of FFTF reactor internals
Thermal expansion movements of piping during FFTF plant startup
Piping vibrations measured during FFTF startup
Conference
·
Wed Oct 01 00:00:00 EDT 1980
·
OSTI ID:6513510
Thermal expansion movements of piping during FFTF plant startup
Conference
·
Sun Mar 01 00:00:00 EST 1981
·
OSTI ID:6513510
Piping vibrations measured during FFTF startup
Conference
·
Sun Mar 01 00:00:00 EST 1981
·
OSTI ID:6513510
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FFTF REACTOR
PRIMARY COOLANT CIRCUITS
THERMOCOUPLES
HYDRAULICS
LIQUID FLOW
MECHANICAL VIBRATIONS
PERFORMANCE TESTING
PIPES
REACTOR INSTRUMENTATION
SODIUM
ALKALI METALS
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FLUID FLOW
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MEASURING INSTRUMENTS
MECHANICS
METALS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
TESTING
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
FFTF REACTOR
PRIMARY COOLANT CIRCUITS
THERMOCOUPLES
HYDRAULICS
LIQUID FLOW
MECHANICAL VIBRATIONS
PERFORMANCE TESTING
PIPES
REACTOR INSTRUMENTATION
SODIUM
ALKALI METALS
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FLUID FLOW
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MEASURING INSTRUMENTS
MECHANICS
METALS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
TESTING
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors