Title :
Detecting and mitigating rod drive control system degradation in Westinghouse PWRs
Author :
Gunther, W. ; Sullivan, K.
Author_Institution :
Brookhaven Nat. Lab., Upton, NY, USA
fDate :
12/1/1991 12:00:00 AM
Abstract :
A study of the effects of aging on the Westinghouse Control Rod Drive (CRD) System was performed as part of the US NRC´s Nuclear Plant Aging Research (NPAR) Program. For the study, the CRD system boundary includes the power and logic cabinets associated with the manual control rod movement, and the control rod mechanism itself. The aging-related degradation of the interconnecting cables and connectors and the rod-position-indicating system also were considered. The authors present the results of that study pertaining to the electrical and instrumentation portions of the CRD system, including ways to detect and mitigate system degradation
Keywords :
ageing; control systems; fission reactor core control and monitoring; fission reactor safety; nuclear power stations; nuclear reactor quality assurance; Westinghouse PWRs; aging; connectors; control rod mechanism; interconnecting cables; manual control rod movement; rod drive control system degradation; Aging; Assembly; Coils; Connectors; Control systems; Degradation; Grippers; Inductors; Integrated circuit interconnections; Logic;
Journal_Title :
Nuclear Science, IEEE Transactions on
