Seismic considerations for ASME class 1 piping systems
Conference
·
· Am. Soc. Mech. Eng., Pressure Vessels Piping Div., (Tech. Rep.) PVP; (United States)
OSTI ID:5444183
ASME Boiler and Pressure Vessel Code Section III requires that Class 1 piping systems be designed and analyzed to account for self-limiting and non-self-limiting loads for primary stress and fatigue protection. The NRC requires demonstration of equipment operability and piping system functional capability in addition to the structural integrity requirements for Class 1 systems. The NSSS vendors impose further restrictions on these systems in order to satisfy systems design criteria to comply with the assumed loadings utilized in their safeguard analyses. All these requirements, as well as any additional plant specific criteria, restrict and control the design of the Class 1 piping systems. A procedure is required to optimize the design and analysis of these systems, which, in most cases, are governed by systems operating transients and seismic loadings. The objective of this paper is to present a technical overview of seismic analysis of Class 1 piping systems in the areas of: methods of analysis, linearization of non-linear systems, response spectral considerations, coupling and resonance between systems, equipment modeling and limitations, support consideration and optimization, generic fatigue analysis concept, special techniques to resolve overstress problems and criteria to assess as-built deviations.
- Research Organization:
- Westinghouse Electric Corporation, Pittsburgh, PA
- OSTI ID:
- 5444183
- Report Number(s):
- CONF-830607-
- Conference Information:
- Journal Name: Am. Soc. Mech. Eng., Pressure Vessels Piping Div., (Tech. Rep.) PVP; (United States) Journal Volume: PVP-VOL 73
- 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
220900* -- Nuclear Reactor Technology-- Reactor Safety
DESIGN
DYNAMIC LOADS
FATIGUE
FUNCTIONS
MECHANICAL PROPERTIES
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OPTIMIZATION
PIPES
POWER PLANTS
REACTOR COMPONENTS
REGULATIONS
RESPONSE FUNCTIONS
SAFEGUARD REGULATIONS
SEISMIC EFFECTS
SEISMIC EVENTS
STRESS ANALYSIS
STRESSES
THERMAL POWER PLANTS
TRANSIENTS
US NRC
US ORGANIZATIONS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
DESIGN
DYNAMIC LOADS
FATIGUE
FUNCTIONS
MECHANICAL PROPERTIES
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OPTIMIZATION
PIPES
POWER PLANTS
REACTOR COMPONENTS
REGULATIONS
RESPONSE FUNCTIONS
SAFEGUARD REGULATIONS
SEISMIC EFFECTS
SEISMIC EVENTS
STRESS ANALYSIS
STRESSES
THERMAL POWER PLANTS
TRANSIENTS
US NRC
US ORGANIZATIONS