Stochastic seismic analysis of nuclear power plant structures and piping systems subjected to multiple support excitations

Thesis/Dissertation · Tue Jan 01 00:00:00 EST 1980

OSTI ID:5273623

Lee, M C

A stochastic method, based on random vibration theory, has been developed in this report for the seismic analysis of nuclear power plant structures and piping systems subjected to multiple support excitations. Through either the time or frequency domain, the mean and extreme values of structural and piping system response can be found, including the cross-correlations of modal response and the cross-correlations of multiple support-excitations. Stationary white noise and stationary filtered white noise ground excitations are used in this study. A computer program has been developed to carry out the stochastic seismic analysis. The results for several realistic nuclear power plant structures and piping systems with and without model cross-correlations and support-excitation cross-correlations are compared. Based on the results of this investigation, it is concluded that neglecting these cross-correlations can lead to large errors. The stochastic method reported is proved to be more accurate than the spectrum method and more economical than the time-history method. Therefore, this stochastic method is recommended for use in the seismic analysis of nuclear power plants.

• Research Organization: California Univ., Berkeley (USA)
• OSTI ID: 5273623
• Resource Relation: Other Information: Thesis (Ph.D.)
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
NUCLEAR POWER PLANTS
SEISMIC EFFECTS
COMPUTER CODES
MECHANICAL STRUCTURES
MECHANICAL VIBRATIONS
REACTOR COMPONENTS
SEISMIC EVENTS
STOCHASTIC PROCESSES
SUPPORTS
NUCLEAR FACILITIES
POWER PLANTS
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety