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Reliability Control of Coolant Measure System in RBMK-1500 Reactor Using Preventive Maintenance

  • Juozas Augutis
  • Vaidas Matuzas
  • Eugenijus Uspuras
Conference paper

Abstract

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.

Keywords

Preventive Maintenance Coolant Flow Degradation Level Coolant Flow Rate Signal Impulse 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

  1. 1.
    Almenas K., Kaliatka A., Ušpuras E. Ignalina RBMK-1500, A Source Book Extended and Updated Version. Kaunas 1998Google Scholar
  2. 2.
    Blank L. Statistical Procedures for Engineering, Management, and Science. McGraw-Hill Book, 1980Google Scholar
  3. 3.
    Hoyland A., Rousand M. System Reliability Theory. Models and Statistical Methods. The Norwegian Institute of Technology, John Wiley & Sons, Inc. 1994Google Scholar

Copyright information

© Springer-Verlag London 2004

Authors and Affiliations

  • Juozas Augutis
    • 1
  • Vaidas Matuzas
    • 1
  • Eugenijus Uspuras
    • 2
  1. 1.Vytautas Magnus UniversityKaunasLithuania
  2. 2.Lithuanian Energy InstituteKaunasLithuania

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