Experimental studies of the seismic response of piping systems supported by multiple structures: Final report
Technical Report
·
OSTI ID:6174426
An extensive series of experiments on the seismic response of a model piping system in a structure has been completed on the shaking table of the Earthquake Simulator Laboratory of the University of California, Berkeley. The purpose of these experiments was to provide data to assess the accuracy of current piping analysis methods for predicting the seismic response of multiple support piping systems. The piping system tested was a half-scale model and the structure in which it was located comprised two steel frames which could be interconnected to act as a single structure or disconnected to act as separate structures. The piping system was attached at several points to each structure and spanned the gap between the two. This report describes the experimental program, the results of which are presented in several forms - extreme values, time histories, floor response spectra and Fourier spectra. Examples of these are given and the response of the piping system when the two frame structures are braced together to act as a single unit is compared to that when the structures are unbraced and act independently. The response of the piping system when rod hangers only are used is compared to that when rods and snubbers, rods and springs, are used in combination. The response of the supports during seismic loading is illustrated by time history plots and by hysteresis plots of force-displacement characteristics under dynamic conditions.
- Research Organization:
- California Univ., Berkeley (USA). Dept. of Civil Engineering; Electric Power Research Inst., Palo Alto, CA (USA)
- OSTI ID:
- 6174426
- Report Number(s):
- EPRI-NP-4865; ON: TI87920260
- 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
DATA
EARTHQUAKES
EXPERIMENTAL DATA
INFORMATION
MECHANICAL VIBRATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
PIPES
POWER PLANTS
REACTOR SAFETY EXPERIMENTS
RESTRAINTS
SCALE MODELS
SEISMIC EFFECTS
SEISMIC EVENTS
STRUCTURAL MODELS
THERMAL POWER PLANTS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
DATA
EARTHQUAKES
EXPERIMENTAL DATA
INFORMATION
MECHANICAL VIBRATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
PIPES
POWER PLANTS
REACTOR SAFETY EXPERIMENTS
RESTRAINTS
SCALE MODELS
SEISMIC EFFECTS
SEISMIC EVENTS
STRUCTURAL MODELS
THERMAL POWER PLANTS