Screening criteria for the verification of seismic adequacy of piping systems
Conference
·
OSTI ID:5559674
- Westinghouse Savannah River Co., Aiken, SC (United States)
- EQE Engineering, Orange County, CA (United States)
- United Engineers and Constructors, Inc., Philadelphia, PA (United States)
This paper describes practical screening criteria to be used by engineering walkdown teams, for the evaluation of seismic adequacy of piping systems. The application of the screening criteria to a nuclear facility are described and compared to the results achieved using conventional analytical techniques. 13 refs.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 5559674
- Report Number(s):
- WSRC-MS-91-030; CONF-910602-59; ON: DE92009846
- Resource Relation:
- Conference: 1991 American Society of Mechanical Engineers (ASME) pressure vessels and piping conference, San Diego, CA (United States), 23-27 Jun 1991
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
NUCLEAR POWER PLANTS
PIPES
SEISMIC EFFECTS
EARTHQUAKES
HEAT TRANSFER
HYDRAULICS
INSPECTION
MECHANICAL ENGINEERING
REACTOR SAFETY
SEISMIC ISOLATION
SPECIFICATIONS
STANDARDS
ENERGY TRANSFER
ENGINEERING
FLUID MECHANICS
MECHANICS
NUCLEAR FACILITIES
POWER PLANTS
SAFETY
SEISMIC EVENTS
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories
NUCLEAR POWER PLANTS
PIPES
SEISMIC EFFECTS
EARTHQUAKES
HEAT TRANSFER
HYDRAULICS
INSPECTION
MECHANICAL ENGINEERING
REACTOR SAFETY
SEISMIC ISOLATION
SPECIFICATIONS
STANDARDS
ENERGY TRANSFER
ENGINEERING
FLUID MECHANICS
MECHANICS
NUCLEAR FACILITIES
POWER PLANTS
SAFETY
SEISMIC EVENTS
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories