Flow-induced vibration characteristics of BWR/6-238 jet pumps
Four prototype BWR/6-238 jet pumps (two jet pump pairs) were tested to determine their flow-induced vibration (FIV) characteristics in the High Flow Hydraulic Facility, (HF)/sup 2/, over the period June to September 1978. Tests consisted of operating the jet pumps, which were heavily instrumented with accelerometers, pressure transducers and strain gages, at the design operating condition, as well as at numerous off-design drive flows and M-ratios, and at temperatures between 70/sup 0/F and 180/sup 0/F and at 455 psig. Results were combined with those from past jet pump tests to predict the response at reactor temperature (533/sup 0/F). Major conclusions reached related to the BWR/6-238 jet pump are presented.
- Research Organization:
- General Electric Co., San Jose, CA (USA). Nuclear Engineering Div.
- DOE Contract Number:
- AC02-77ET34209
- OSTI ID:
- 6654640
- Report Number(s):
- GEAP-22201; ON: DE83003103
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
EXPERIMENTAL DATA
FLUID MECHANICS
HYDRAULICS
INFORMATION
MECHANICAL VIBRATIONS
MECHANICS
NUMERICAL DATA
PRESSURE GRADIENTS
PRIMARY COOLANT CIRCUITS
PUMPS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
EXPERIMENTAL DATA
FLUID MECHANICS
HYDRAULICS
INFORMATION
MECHANICAL VIBRATIONS
MECHANICS
NUMERICAL DATA
PRESSURE GRADIENTS
PRIMARY COOLANT CIRCUITS
PUMPS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS