Elastic analysis of beam support impact
Conference
·
· Am. Soc. Mech. Eng., (Pap.); (United States)
OSTI ID:5346472
The effect of gaps present in the seismic supports of nuclear piping systems has been studied with the use of such large general purpose analysis codes as ANSYS. Exact analytical solutions to two simple beam impact problems are obtained to serve as benchmarks for the evaluation of the ability of such codes to model impact between beam elements and their supports. Bernoulli-Euler beam theory and modal analysis are used to obtain analytical solutions for the motion of simply supported and fixed ended beams after impact with a spring support at midspan. The solutions are valid up to the time the beam loses contact with the spring support. Numerical results are obtained which show that convergence for both contact force and bending moment at the point of impact is slower as spring stiffness is increased. Finite element solutions obtained with ANSYS are compared to analytical results and good agreement is obtained.
- Research Organization:
- Sargent and Lundy Engineers, Chicago, IL
- OSTI ID:
- 5346472
- Report Number(s):
- CONF-820601-
- Conference Information:
- Journal Name: Am. Soc. Mech. Eng., (Pap.); (United States) Journal Volume: 82-PVP-58
- 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
ANALYTICAL SOLUTION
BENCHMARKS
BENDING
BERNOULLI LAW
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
ELASTICITY
ENERGY SYSTEMS
FINITE ELEMENT METHOD
IMPACT SHOCK
INFORMATION VALIDATION
MACHINE PARTS
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
MOTION
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL SOLUTION
PIPES
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
SEISMIC EFFECTS
SEISMIC EVENTS
SIMULATION
SPRINGS
STRESS ANALYSIS
STRUCTURAL BEAMS
SUPPORTS
TENSILE PROPERTIES
TESTING
THERMAL POWER PLANTS
VALIDATION
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ANALYTICAL SOLUTION
BENCHMARKS
BENDING
BERNOULLI LAW
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
ELASTICITY
ENERGY SYSTEMS
FINITE ELEMENT METHOD
IMPACT SHOCK
INFORMATION VALIDATION
MACHINE PARTS
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
MOTION
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL SOLUTION
PIPES
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
SEISMIC EFFECTS
SEISMIC EVENTS
SIMULATION
SPRINGS
STRESS ANALYSIS
STRUCTURAL BEAMS
SUPPORTS
TENSILE PROPERTIES
TESTING
THERMAL POWER PLANTS
VALIDATION