Prediction of check valve performance and degradation in nuclear power plant systems
Technical Report
·
OSTI ID:6665911
- Kalsi Engineering, Inc., Sugar Land, TX (USA)
Check valve failures in nuclear power plants have led to safety concerns as well as extensive damage and loss of plant availability in recent years. Swing check valve internals may experience premature deterioration if the disc is not firmly held open against its stop. At the present time no guidelines exist for the prediction of degradation trends and the determination of suitable inspection intervals. This research is aimed at developing a reliable quantitative wear and fatigue prediction model for swing check valves which can be used to improve the safety and reliability of their operation. Additionally, the predictive techniques can be used to augment check valve preventive maintenance programs by providing the plant engineer with quantitative and conservative estimates of damage potential for check valve internals. 21 refs., 30 figs., 8 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Kalsi Engineering, Inc., Sugar Land, TX (USA)
- Sponsoring Organization:
- NRC
- OSTI ID:
- 6665911
- Report Number(s):
- NUREG/CR-5583; KEI--1656; ON: TI90016729
- 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
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
CONTROL EQUIPMENT
DOCUMENT TYPES
EQUATIONS
EQUIPMENT
FAILURES
FATIGUE
FLOW REGULATORS
IMPACT SHOCK
IMPACT TESTS
MAINTENANCE
MATERIALS TESTING
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICAL TESTS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERFORMANCE
POWER PLANTS
PREDICTION EQUATIONS
PROGRESS REPORT
REACTOR SAFETY
RELIABILITY
SAFETY
TESTING
THERMAL POWER PLANTS
VALVES
WEAR
220200* -- Nuclear Reactor Technology-- Components & Accessories
220900 -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
CONTROL EQUIPMENT
DOCUMENT TYPES
EQUATIONS
EQUIPMENT
FAILURES
FATIGUE
FLOW REGULATORS
IMPACT SHOCK
IMPACT TESTS
MAINTENANCE
MATERIALS TESTING
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICAL TESTS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERFORMANCE
POWER PLANTS
PREDICTION EQUATIONS
PROGRESS REPORT
REACTOR SAFETY
RELIABILITY
SAFETY
TESTING
THERMAL POWER PLANTS
VALVES
WEAR