Nonlinear piping damping and response predictions
Conference
·
OSTI ID:6558164
The high level dynamic testing of four prototypic piping systems, used to provide benchmarks for analytical prediction comparisons, is overviewed. The size of pipe tested ranged from one-inch to six-inches in diameter and consisted of carbon steel or stainless steel material. Failure of the tested systems included progressive gross deformation or some combination of ratchetting-fatigue. Pretest failure predictions and post test comparisons using simplified elastic and elasto-plastic methods are presented. Detailed non-linear inelastic analyses are also shown, along with a typical ratchet-fatigue failure calculation. A simplified method for calculating modal equivalent viscous damping for snubbers and plastic hinges is also described. Conclusions are made regarding the applicability of the various analytical failure predictive methods and recommendations are made for future analytic and test efforts.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 6558164
- Report Number(s):
- HEDL-SA-3616-FP; CONF-8610135-61; ON: DE87005475
- Country of Publication:
- United States
- Language:
- English
Similar Records
Simplified analytical methods and experimental correlations of damping in piping during dynamic high-level inelastic response
Analytical methods and experimental correlations for piping high level inelastic seismic response
Seismic ratchet-fatigue failure of piping systems
Conference
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:6440455
Analytical methods and experimental correlations for piping high level inelastic seismic response
Conference
·
Wed Oct 01 00:00:00 EDT 1986
·
OSTI ID:6558152
Seismic ratchet-fatigue failure of piping systems
Conference
·
Tue Nov 25 23:00:00 EST 1986
·
OSTI ID:6797377
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CARBON STEELS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
DAMPING
DEFORMATION
DYNAMICS
FAILURES
FATIGUE
FRACTURES
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICAL VIBRATIONS
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
REACTOR MATERIALS
RESEARCH PROGRAMS
RISK ASSESSMENT
RUPTURES
SEISMIC EFFECTS
STAINLESS STEELS
STEELS
TESTING
THERMAL POWER PLANTS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CARBON STEELS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
DAMPING
DEFORMATION
DYNAMICS
FAILURES
FATIGUE
FRACTURES
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICAL VIBRATIONS
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
REACTOR MATERIALS
RESEARCH PROGRAMS
RISK ASSESSMENT
RUPTURES
SEISMIC EFFECTS
STAINLESS STEELS
STEELS
TESTING
THERMAL POWER PLANTS