Theoretical and experimental damping values of piping systems at high ductilities
Conference
·
OSTI ID:5360440
This paper presents a simplified theoretical explanation and test data for piping system damping during post-yield dynamic behavior. The theoretical frequency and damping variations with material ductility are discussed. The results of high excitation level tests from seven sources are described and correlated on common bases. Starting with 0% of critical damping at a local ductility of 1 (yield strain), damping values of from 30 to 50% of critical are estimated at the time of piping system failure. Since 50% of critical damping corresponds to no dynamic amplification at resonance, it is concluded that the input energy is being continually and completely dissipated by the forcing function changing the plastic dynamic deflection shape, with no dynamic amplification of displacements. An experimental method for consistent estimation of damping values at elastoplastic response levels is recommended.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5360440
- Report Number(s):
- EGG-M-31686; CONF-870636-15; ON: DE88006717
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
COOLING SYSTEMS
DAMPING
DATA
DUCTILITY
ENERGY SYSTEMS
EXPERIMENTAL DATA
INFORMATION
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
PIPES
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RESEARCH PROGRAMS
RESTRAINTS
SAFETY
SEISMIC EFFECTS
STRAINS
TENSILE PROPERTIES
THERMAL POWER PLANTS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
COOLING SYSTEMS
DAMPING
DATA
DUCTILITY
ENERGY SYSTEMS
EXPERIMENTAL DATA
INFORMATION
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
PIPES
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RESEARCH PROGRAMS
RESTRAINTS
SAFETY
SEISMIC EFFECTS
STRAINS
TENSILE PROPERTIES
THERMAL POWER PLANTS