Seismic analysis of piping with nonlinear supports
Conference
·
OSTI ID:5026013
The modeling and results of nonlinear time-history seismic analyses for three sizes of pipelines restrained by mechanical snubbes are presented. Numerous parametric analyses were conducted to obtain sensitivity information which identifies relative importance of the model and analysis ingredients. Special considerations for modeling the pipe clamps and the mechanical snubbers based on experimental characterization data are discussed. Comparisions are also given of seismic responses, loads and pipe stresses predicted by standard response spectra methods and the nonlinear time-history methods.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC14-76FF02170
- OSTI ID:
- 5026013
- Report Number(s):
- HEDL-SA-1994-FP; CONF-800804-28
- Country of Publication:
- United States
- Language:
- English
Similar Records
Seismic testing and analysis of a prototypic nonlinear piping system
Nuclear piping seismic support--a simplified approach
Verification of piping response calculations of SMACS code with data from seismic testing of an in-plant piping system
Conference
·
Sun Oct 31 23:00:00 EST 1982
·
OSTI ID:6627123
Nuclear piping seismic support--a simplified approach
Journal Article
·
Sat Jun 01 00:00:00 EDT 1985
· Mech. Eng.; (United States)
·
OSTI ID:6495913
Verification of piping response calculations of SMACS code with data from seismic testing of an in-plant piping system
Technical Report
·
Sun Sep 01 00:00:00 EDT 1991
·
OSTI ID:5244469
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
COOLING SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
LIQUID METAL COOLED REACTORS
PIPES
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RESTRAINTS
SEISMIC EFFECTS
SODIUM COOLED REACTORS
SPECIFICATIONS
STRESS ANALYSIS
STRESSES
TEST REACTORS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
COOLING SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
LIQUID METAL COOLED REACTORS
PIPES
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RESTRAINTS
SEISMIC EFFECTS
SODIUM COOLED REACTORS
SPECIFICATIONS
STRESS ANALYSIS
STRESSES
TEST REACTORS