Reliability of the coolant flow rate measuring system at the ignalina nuclear power plant

Age assessment and control of the reliability of the coolant flow-rate measurement system of the RBMK-1500 reactor at the Ignalina nuclear power plant are examined. A statistical analysis is made of the data obtained from measurements of the techanical characteristics of SHADR-32M flow meters. A mat...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2004-06, Vol.96 (6), p.403-406
Main Authors: AUGUTIS, Yu, USPURAS, E, ALZBUTAS, R, MATUZAS, V
Format: Article
Language:English
Subjects:
Applied sciences
Assessments
Control systems
Coolants
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Flow measurement
Flow rates
Flowmeters
Fuels
Installations for energy generation and conversion: thermal and electrical energy
Mathematical models
Nuclear engineering
Nuclear fuels
Nuclear power generation
Nuclear power plants
Nuclear reactor components
Statistical analysis
Strategy
Studies
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Summary:Age assessment and control of the reliability of the coolant flow-rate measurement system of the RBMK-1500 reactor at the Ignalina nuclear power plant are examined. A statistical analysis is made of the data obtained from measurements of the techanical characteristics of SHADR-32M flow meters. A mathematical model of the aging of flow meters and reliability estimates is constructed. A strategy is developed for replacing SHADR; this strategy makes it possible to support the required relaibility of the entire coolant flow-rate measurement system.
ISSN:1063-4258
1573-8205
DOI:10.1023/B:ATEN.0000041207.52993.ae