Abstract
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.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
REFERENCES
ShTORM-8A-55 and ShTORM-32M-55 Ball Flow Meters. Technical Description and Operating Instructions (2001).
K. Almenas, A. Kaliatka, and E. Uspuras, Ignalina RBMK-1500. A Source Book, LEI, Kaunas (1998).
B. V. Lysikov and V. K. Prozorov, Thermometry and Flow-Rate Measurement for Nuclear Reactors, Énergoatomiz-dat, Moscow (1985).
R. Fullwood and R. Hall, Probabilistic Risk Assessment in the Nuclear Power Industry, BNL, USA (1988).
Author information
Authors and Affiliations
Rights and permissions
About this article
Cite this article
Augutis, Y., Uspuras, E., Alzbutas, R. et al. Reliability of the Coolant Flow Rate Measuring System at the Ignalina Nuclear Power Plant. Atomic Energy 96, 403–406 (2004). https://doi.org/10.1023/B:ATEN.0000041207.52993.ae
Issue Date:
DOI: https://doi.org/10.1023/B:ATEN.0000041207.52993.ae