Reliability Control of Coolant Measure System in RBMK-1500 Reactor Using Preventive Maintenance
The reliability of a system, which is designed for measurement of coolant flow through fuel channels in Ignalina nuclear power plant RBMK-1500 reactors, is considered. Existing flowmeters degradation level assessment criteria has been analysed and new mathematical model for assessment of degradation level is presented.
KeywordsPreventive Maintenance Coolant Flow Degradation Level Coolant Flow Rate Signal Impulse
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