Fuel-rod vibration in two-phase flow. [BWR]
Technical Report
·
OSTI ID:6606739
The results of a test program investigating the flow-induced vibration (FIV) characteristics of fuel rods subjected to various thermal hydraulic flow conditions (single-phase flow, two-phase inlet flow, and boiling flow) are presented. The effects of single-phase fluid temperature, mass flux, two-phase inlet quality and bundle power on the FIV characteristics of fuel rods are reported.
- Research Organization:
- General Electric Co., San Jose, CA (USA). Nuclear Engineering Div.
- DOE Contract Number:
- AC02-77ET34209
- OSTI ID:
- 6606739
- Report Number(s):
- GEAP-22077; ON: DE83004455
- 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
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
HYDRAULICS
MECHANICAL VIBRATIONS
MECHANICS
REACTOR COMPONENTS
REACTORS
TEST FACILITIES
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
HYDRAULICS
MECHANICAL VIBRATIONS
MECHANICS
REACTOR COMPONENTS
REACTORS
TEST FACILITIES
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS