Review of nuclear piping seismic design requirements
Journal Article
·
· Nuclear Safety; (United States)
OSTI ID:6928120
- G.C. Slagis Associates, Walnut Creek, CA (United States)
- Oak Ridge National Lab., TN (United States)
Modern-day nuclear plant piping systems are designed with a large number of seismic supports and snubbers that may be detrimental to plant reliability. Experimental tests have demonstrated the inherent ruggedness of ductile steel piping for seismic loading. Present methods to predict seismic loads on piping are based on linear-elastic analysis methods with low damping. These methods overpredict the seismic response of ductile steel pipe. Section III of the ASME Boiler and Pressure Vessel Code stresses limits for piping systems that are based on considerations of static loads and hence are overly conservative. Appropriate stress limits for seismic loads on piping should be incorporated into the code to allow more flexible piping designs. The existing requirements and methods for seismic design of piping systems, including inherent conservations, are explained to provide a technical foundation for modifications to those requirements. 30 refs., 5 figs., 3 tabs.
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6928120
- Journal Information:
- Nuclear Safety; (United States), Journal Name: Nuclear Safety; (United States) Vol. 35:1; ISSN 0029-5604; ISSN NUSAAZ
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210700 -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
220900 -- Nuclear Reactor Technology-- Reactor Safety
ALLOYS
COMPILED DATA
DATA
DESIGN
HIGH ALLOY STEELS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL VIBRATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
PIPES
POWER PLANTS
REGULATIONS
SAFETY
SAFETY STANDARDS
SEISMIC EFFECTS
STAINLESS STEELS
STANDARDS
STEELS
STRESSES
TESTING
THERMAL POWER PLANTS
210700 -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
220900 -- Nuclear Reactor Technology-- Reactor Safety
ALLOYS
COMPILED DATA
DATA
DESIGN
HIGH ALLOY STEELS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL VIBRATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
PIPES
POWER PLANTS
REGULATIONS
SAFETY
SAFETY STANDARDS
SEISMIC EFFECTS
STAINLESS STEELS
STANDARDS
STEELS
STRESSES
TESTING
THERMAL POWER PLANTS