Seismic analysis of piping systems subjected to independent-support excitation
Conference
·
OSTI ID:6276759
This paper presents a comparison of dynamic responses of piping systems subject to independent-support excitation using the response spectrum and time-history methods. The BNL finite-element computer code PSAFE2 has been used to perform all the analyses. The time-history method combines both the inertia as well as static effect on the piping responses due to independent-support excitations at each time point, thus representing the actual responses. A sample problem is analyzed subjected to two independent support excitations and the results are presented in comparison with the response spectrum methods with uniform or independent-support motion.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6276759
- Report Number(s):
- BNL-NUREG-32862; CONF-830607-11; ON: DE83012215
- Country of Publication:
- United States
- Language:
- English
Similar Records
Seismic analysis of piping systems subjected to multiple support excitations
Assessment of alternate procedures for the seismic analysis of multiply supported piping systems
Comparison study of time history and response spectrum responses for multiply supported piping systems. [PWR; BWR]
Journal Article
·
Sat Oct 31 23:00:00 EST 1981
· Am. Soc. Mech. Eng., (Pap.); (United States)
·
OSTI ID:5083316
Assessment of alternate procedures for the seismic analysis of multiply supported piping systems
Conference
·
Sat Jun 01 00:00:00 EDT 1985
·
OSTI ID:5569608
Comparison study of time history and response spectrum responses for multiply supported piping systems. [PWR; BWR]
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5937051
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPUTER CALCULATIONS
MATHEMATICAL MODELS
MECHANICAL STRUCTURES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
SEISMIC EFFECTS
STRESS ANALYSIS
SUPPORTS
THERMAL POWER PLANTS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPUTER CALCULATIONS
MATHEMATICAL MODELS
MECHANICAL STRUCTURES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
SEISMIC EFFECTS
STRESS ANALYSIS
SUPPORTS
THERMAL POWER PLANTS