Dynamic analysis techniques--a sensitivity study for piping systems at a nuclear power plant

Journal Article · Thu Jan 01 04:00:00 EST 1981 · HTD (Publ.) (Am. Soc. Mech. Eng.); (United States)

OSTI ID:5487445

Suryoutomo, H; Bacher, R

The original seismic analysis of the piping systems for a nuclear power plant considered two different seismic load cases. Each case represented the response due to a combination of the vertical component and one of the two orthogonal horizontal components (N-S or E-W) of an earthquake. The highest response of the two load cases was used to evaluate the piping systems. The current USNRC Regulatory Guide 1.92 requires that all three earthquake components shall be considered to act simultaneously on the systems with special consideration of the closely spaced modes. The study presented in this paper was performed to evaluate the differences in the piping stresses and pipe support loads obtained from these two analytical approaches. This study also includes the effect of the differential seismic anchor movements, calculated support stiffnesses and the effects of closely spaced modes in the modal summation procedure, and compares the relative results of the two analytical approaches. 4 refs.

• Research Organization: Earthquake Eng Syst Inc, San Francisco, Calif
• OSTI ID: 5487445
• Journal Information: HTD (Publ.) (Am. Soc. Mech. Eng.); (United States), Journal Name: HTD (Publ.) (Am. Soc. Mech. Eng.); (United States) Vol. 53; ISSN ASMHD
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
EARTHQUAKES
MECHANICAL STRUCTURES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
REACTOR SAFETY
SAFETY
SEISMIC EFFECTS
SEISMIC EVENTS
STRESS ANALYSIS
SUPPORTS
THERMAL POWER PLANTS