Seismic response analyses for reactor facilities at Savannah River

Conference · Tue Jan 01 00:00:00 EST 1991

OSTI ID:5789246

Xu, J ^[1]

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1. Brookhaven National Lab., Upton, NY (USA)

The reactor facilities at the Savannah River Plant (SRP) were designed during the 1950's. The original seismic criteria defining the input ground motion was 0.1 G with UBC (uniform building code) provisions used to evaluate structural seismic loads. Later ground motion criteria have defined the free field seismic motion with a 0.2 G ZPA (free field acceleration) and various spectral shapes. The spectral shapes have included the Housner spectra, a site specific spectra, and the US NRC (Nuclear Regulatory Commission) Reg. Guide 1.60 shape. The development of these free field seismic criteria are discussed in the paper. The more recent seismic analyses have been of the following type: fixed base response spectra, frequency independent lumped parameter soil/structure interaction (SSI), frequency dependent lumped parameter SSI, and current state of the art analyses using computer codes such as SASSI. The results from these computations consist of structural loads and floor response spectra (used for piping and equipment qualification). These results are compared in the paper and the methods used to validate the results are discussed. 14 refs., 11 figs.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5789246
• Report Number(s): BNL-46004; CONF-910602-27; ON: DE91010896
• Resource Relation: Conference: American Society of Mechanical Engineers (ASME) pressure vessels and piping conference, San Diego, CA (USA), 23-27 Jun 1991
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
SPECIAL PRODUCTION REACTORS
REACTOR SAFETY
SEISMIC EFFECTS
AGING
COMPUTER CODES
COMPUTERIZED SIMULATION
GROUND MOTION
REACTOR SHUTDOWN
REGULATIONS
RESPONSE FUNCTIONS
S CODES
SAVANNAH RIVER PLANT
SECONDARY COOLANT CIRCUITS
SOIL-STRUCTURE INTERACTIONS
US NRC
VALIDATION
COOLING SYSTEMS
ENERGY SYSTEMS
FUNCTIONS
MOTION
NATIONAL ORGANIZATIONS
PRODUCTION REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
SHUTDOWNS
SIMULATION
TESTING
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220700 - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors