Effect of PVRC damping with independent support motion response spectrum analysis of piping systems
Conference
·
OSTI ID:5579401
The Technical Committee for Piping Systems of the Pressure Vessel Research Committee (PVRC) has recommended new damping values to be used in the seismic analyses of piping systems in nuclear power plants. To evaluate the effects of coupling these recommendations with the use of independent support motion analyses methods, two sets of seismic analyses have been carried out for several piping systems. One set based on the use of uniform damping as specified in Regulatory Guide 1.61, the other based on the PVRC recommendations. In each set the analyses were performed using independent support motion time history and response spectrum methods as well as the envelope spectrum method. In the independent response spectrum analyses, 14 response estimates were in fact obtained by considering different combination procedures between the support group contributions and all sequences of combinations between support groups, modes and directions. For each analysis set, the response spectrum results were compared with time history estimates of those results. Comparison tables were then prepared depicting the percentage by which the response spectrum estimates exceeded the time history estimates. By comparing the result tables between both analysis sets, the impact of PVRC damping can be observed. Preliminary results show that the degree of exceedance of the response spectrum estimates based on PVRC damping is less than that based on uniform damping for the same piping problem. Expressed differently the results obtained if ISM methods are coupled with PVRC damping are not as conservative as those obtained using uniform damping.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5579401
- Report Number(s):
- BNL-NUREG-37840; CONF-860722-13; ON: TI86010542
- 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
CONTAINERS
CONTROL EQUIPMENT
DAMPING
EQUIPMENT
FLOW REGULATORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
PRESSURE VESSELS
RESEARCH PROGRAMS
SEISMIC EFFECTS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
VALVES
220200* -- Nuclear Reactor Technology-- Components & Accessories
CONTAINERS
CONTROL EQUIPMENT
DAMPING
EQUIPMENT
FLOW REGULATORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
PRESSURE VESSELS
RESEARCH PROGRAMS
SEISMIC EFFECTS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
VALVES