Duke Power Company's control rod wear program
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:7089503
Recent examinations performed at several foreign and domestic pressurized water reactors have identified significant control rod cladding wear, leading to the conclusion that previously believed control rod lifetimes are not attainable. To monitor control rod performance and reduce safety concerns associated with wear, Duke Power Company has developed a comprehensive control rod wear program for Ag-In-Cd and boron carbide (B[sub 4]C) rods at the McGuire and Catawba nuclear stations. Duke Power currently uses the Westinghouse 17 x 17 Ag-In-Cd control rod design at McGuire Unit 1 and the Westinghouse 17 x 17 hybrid B[sub 4]C control rod design with a Ag-In-Cd tip at McGuire Unit 2 and Catawba Units 1 and 2. The designs are similar, with the exception of the absorber material and clad thickness. There are 53 control rods per unit.
- OSTI ID:
- 7089503
- Report Number(s):
- CONF-901101--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 62
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
CATAWBA-1 REACTOR
CATAWBA-2 REACTOR
CONTROL ELEMENTS
CONTROL SYSTEMS
EDDY CURRENT TESTING
ELECTROMAGNETIC TESTING
ENRICHED URANIUM REACTORS
FLOW STRESS
FLUID-STRUCTURE INTERACTIONS
LIFETIME
MAINTENANCE
MATERIALS TESTING
MC GUIRE-1 REACTOR
MC GUIRE-2 REACTOR
NONDESTRUCTIVE TESTING
PERFORMANCE
POST-IRRADIATION EXAMINATION
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR MAINTENANCE
REACTOR SAFETY
REACTORS
SAFETY
SERVICE LIFE
STRESSES
SURVEILLANCE
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEAR
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
CATAWBA-1 REACTOR
CATAWBA-2 REACTOR
CONTROL ELEMENTS
CONTROL SYSTEMS
EDDY CURRENT TESTING
ELECTROMAGNETIC TESTING
ENRICHED URANIUM REACTORS
FLOW STRESS
FLUID-STRUCTURE INTERACTIONS
LIFETIME
MAINTENANCE
MATERIALS TESTING
MC GUIRE-1 REACTOR
MC GUIRE-2 REACTOR
NONDESTRUCTIVE TESTING
PERFORMANCE
POST-IRRADIATION EXAMINATION
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR MAINTENANCE
REACTOR SAFETY
REACTORS
SAFETY
SERVICE LIFE
STRESSES
SURVEILLANCE
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEAR