Detection and mitigating rod drive control system degradation in Westinghouse PWRs
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. This paper presents the results of that study pertaining to the electrical and instrumentation portions of the CRD system including ways to detect and mitigate system degradation.
- Authors:
- Publication Date:
- Research Org.:
- Brookhaven National Lab., Upton, NY (USA)
- Sponsoring Org.:
- USNRC
- OSTI Identifier:
- 6492264
- Report Number(s):
- BNL-NUREG-45316; CONF-9010220-7
ON: DE91004017; TRN: 90-035961
- DOE Contract Number:
- AC02-76CH00016
- Resource Type:
- Conference
- Resource Relation:
- Conference: 1990 IEEE nuclear science symposium, Arlington, VA (USA), 23-27 Oct 1990
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CONTROL ROD DRIVES; AGING; ELECTRIC CABLES; PWR TYPE REACTORS; REACTOR CONTROL SYSTEMS; REACTOR INSTRUMENTATION; CONTROL ELEMENTS; FAILURE MODE ANALYSIS; FAILURES; INSPECTION; MAINTENANCE; RECOMMENDATIONS; SURVEILLANCE; CABLES; CONDUCTOR DEVICES; CONTROL SYSTEMS; ELECTRICAL EQUIPMENT; EQUIPMENT; REACTOR COMPONENTS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220400* - Nuclear Reactor Technology- Control Systems; 220900 - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
Citation Formats
Gunther, W, and Sullivan, K. Detection and mitigating rod drive control system degradation in Westinghouse PWRs. United States: N. p., 1990.
Web.
Gunther, W, & Sullivan, K. Detection and mitigating rod drive control system degradation in Westinghouse PWRs. United States.
Gunther, W, and Sullivan, K. 1990.
"Detection and mitigating rod drive control system degradation in Westinghouse PWRs". United States. https://www.osti.gov/servlets/purl/6492264.
@article{osti_6492264,
title = {Detection and mitigating rod drive control system degradation in Westinghouse PWRs},
author = {Gunther, W and Sullivan, K},
abstractNote = {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. This paper presents the results of that study pertaining to the electrical and instrumentation portions of the CRD system including ways to detect and mitigate system degradation.},
doi = {},
url = {https://www.osti.gov/biblio/6492264},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 1990},
month = {Mon Jan 01 00:00:00 EST 1990}
}
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