Ratcheting of pressurized piping subjected to seismic loading
Journal Article
·
· Journal of Pressure Vessel Technology; (United States)
- Akron Univ., OH (United States). Dept. of Mechanical Engineering
The ABAQUS finite element code was used to model a pressurized pipe and subjected to cyclic bending loads to investigate ratcheting. A 1-in. schedule 40 pipe was loaded with a slow (static) cyclic load. The pipe internal pressure was varied from 0 to 6000 psi. In this paper, two types of materials were considered: an elastic perfectly plastic and a bilinear elastic-plastic material. Two types of finite elements of the ABAQUS program were compared to analytical solutions to evaluate the element accuracy in the plastic regime. Depending upon loading conditions and specified material properties, three different responses were observed from the finite element analyses: cyclic plasticity, ratcheting of the hoop strain, or shakedown. These analytical results are compared to some experimental measurements.
- OSTI ID:
- 6912322
- Journal Information:
- Journal of Pressure Vessel Technology; (United States), Journal Name: Journal of Pressure Vessel Technology; (United States) Vol. 114:3; ISSN JPVTAS; ISSN 0094-9930
- 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
220501 -- Nuclear Reactor Technology-- Environmental Aspects-- Siting
220504 -- Nuclear Reactor Technology-- Environmental Aspects-- Design Basis & Hypothetical Accidents-- (1992-)
220900* -- Nuclear Reactor Technology-- Reactor Safety
A CODES
ANALYTICAL SOLUTION
CALCULATION METHODS
COMPUTER CODES
CONTAINERS
DESIGN
DYNAMIC LOADS
ENGINEERING
FINITE ELEMENT METHOD
MATERIALS TESTING
NUMERICAL SOLUTION
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTOR VESSELS
SAFETY
SAFETY ANALYSIS
SAFETY ENGINEERING
SEISMIC EFFECTS
TESTING
220200 -- Nuclear Reactor Technology-- Components & Accessories
220501 -- Nuclear Reactor Technology-- Environmental Aspects-- Siting
220504 -- Nuclear Reactor Technology-- Environmental Aspects-- Design Basis & Hypothetical Accidents-- (1992-)
220900* -- Nuclear Reactor Technology-- Reactor Safety
A CODES
ANALYTICAL SOLUTION
CALCULATION METHODS
COMPUTER CODES
CONTAINERS
DESIGN
DYNAMIC LOADS
ENGINEERING
FINITE ELEMENT METHOD
MATERIALS TESTING
NUMERICAL SOLUTION
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTOR VESSELS
SAFETY
SAFETY ANALYSIS
SAFETY ENGINEERING
SEISMIC EFFECTS
TESTING