Pre-test analysis of a pipe system for high-level vibration response and failure
Conference
·
OSTI ID:5790063
Simplified elastic and inelastic analyses for high level vibration response and cyclic failure capacity of a prototypic light-water reactor pipe system were carried out in a pretest environment. The system consists of a steam generator and a circulating pump with associated piping that has been tested on a shake table. Five analyses, ranging from standard linear elastic to detailed inelastic transient analysis, are compared in terms of response. With the inelastic analysis, subsequent failure analysis indicated that strain in the 3% to 4% range can be expected if the planned inputs are realized. Possible cyclic failure was predicted by through-wall cracking and leaking in 20 to 40 cycles of maximum strain range, caused by ratchet-fatigue in the pressurized system. 20 refs., 7 figs.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (USA)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 5790063
- Report Number(s):
- WHC-SA-1016; CONF-910602--25; ON: DE91010835
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
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ACCELERATION
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COORDINATED RESEARCH PROGRAMS
DAMPING
DEFORMATION
DYNAMIC LOADS
ELASTICITY
ENERGY SYSTEMS
EPRI
FAILURES
FRACTURE MECHANICS
FUNCTIONS
JAPANESE ORGANIZATIONS
MECHANICAL PROPERTIES
MECHANICAL VIBRATIONS
MECHANICS
NATIONAL ORGANIZATIONS
NONLINEAR PROBLEMS
PIPES
PRIMARY COOLANT CIRCUITS
PUMPS
PWR TYPE REACTORS
RATCHETING
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH PROGRAMS
RESPONSE FUNCTIONS
SEISMIC EFFECTS
SIMULATION
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STRAINS
TENSILE PROPERTIES
TIME DEPENDENCE
US AEC
US DOE
US ERDA
US NRC
US ORGANIZATIONS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS