Duke Power Company's control rod wear program
Creators
Description
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 (B4C) 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 B4C 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
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 62
- Journal Page Range
- p. 419-420.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 11-16 Nov 1990.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24038713
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CATAWBA-1 REACTOR; CATAWBA-2 REACTOR; CONTROL ELEMENTS; EDDY CURRENT TESTING; FLOW STRESS; FLUID-STRUCTURE INTERACTIONS; MC GUIRE-1 REACTOR; MC GUIRE-2 REACTOR; MONITORING; PERFORMANCE; POST-IRRADIATION EXAMINATION; REACTOR CONTROL SYSTEMS; REACTOR MAINTENANCE; REACTOR SAFETY; SERVICE LIFE; WEAR
- Descriptors DEC
- CONTROL SYSTEMS; ELECTROMAGNETIC TESTING; ENRICHED URANIUM REACTORS; LIFETIME; MAINTENANCE; MATERIALS TESTING; NONDESTRUCTIVE TESTING; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; STRESSES; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901101--.