Prediction of check valve performance and degradation in nuclear power plant systems: Final report, September 1987--April 1988
Technical Report
·
OSTI ID:5157375
Degradation and failure of swing check valves and resulting damage to plant equipment has led to a need to develop a method to predict performance and degradation of these valves in nuclear power plant systems. This Phase I investigation developed methods which can be used to predict the stability of the check valve disk when piping disturbances such as elbows, reducers, and generalized turbulence sources are present upstream of the valve within 10 pipe diameters. Major findings include the flow velocity required to achieve a full open, stable disk position, the magnitude of disk motion developed with these upstream disturbances with flow velocities below full open conditions, as well as disk natural frequency data which can be used to predict wear and fatique damage. Reducers were found to cause little or no performance degradation. Elbow effects must be considered when located within 5 diameters of the check valve, while severe turbulence source have significant effect at distances to 10 diameters. Clearway swing check designs were found to be particularly sensitive to manufacturing tolerances and installation variable making them likely candidates for premature failure. Reducing the disk full opening angle on these clearway designs in significant performance improvement.
- Research Organization:
- Kalsi Engineering, Inc., Sugar Land, TX (USA)
- OSTI ID:
- 5157375
- Report Number(s):
- NUREG/CR-5159; KEI-1559; ON: TI88011557
- Country of Publication:
- United States
- Language:
- English
Similar Records
Prediction of check valve performance and degradation in nuclear power plant systems
Sizing swing check valves for stability and minimum velocity limits
Effects of compressibility on flow characteristics and dynamics of swing check valves. Part 2
Technical Report
·
Wed Aug 01 00:00:00 EDT 1990
·
OSTI ID:6665911
Sizing swing check valves for stability and minimum velocity limits
Journal Article
·
Sun Oct 31 23:00:00 EST 1993
· Journal of Pressure Vessel Technology; (United States)
·
OSTI ID:5531211
Effects of compressibility on flow characteristics and dynamics of swing check valves. Part 2
Journal Article
·
Thu May 01 00:00:00 EDT 1997
· Journal of Pressure Vessel Technology
·
OSTI ID:477460
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
AGING
CONTROL EQUIPMENT
COOLING SYSTEMS
DAMAGE
DOCUMENT TYPES
ENERGY SYSTEMS
EQUIPMENT
FLOW REGULATORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERFORMANCE
POWER PLANTS
PROGRESS REPORT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
THERMAL POWER PLANTS
VALVES
220200* -- Nuclear Reactor Technology-- Components & Accessories
AGING
CONTROL EQUIPMENT
COOLING SYSTEMS
DAMAGE
DOCUMENT TYPES
ENERGY SYSTEMS
EQUIPMENT
FLOW REGULATORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERFORMANCE
POWER PLANTS
PROGRESS REPORT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
THERMAL POWER PLANTS
VALVES