In spite of wide expansion of digital systems for NPP control, information about realistic operating reliability measures of these systems is still lacking. The paper is a continuation of report  and contains results of analysis of operating reliability of digital control systems used in Ukrainian nuclear power plants. This paper contains: - reliability measures of digital instrumentation and control systems of first generation (designed in 1979–1983); - reliability measures of digital reactor control systems of second generation (designed after 2000) including reasons of failures; - analysis of the reasons of NPP violations due to digital instrumentation and control systems.
- Nuclear Engineering Division
Reliability of Reactor Control Digital Systems
- Views Icon Views
- Share Icon Share
- Search Site
Yastrebenetsky, MA, Siora, AA, & Tokarev, VI. "Reliability of Reactor Control Digital Systems." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control. Brussels, Belgium. July 12–16, 2009. pp. 713-717. ASME. https://doi.org/10.1115/ICONE17-75157
Download citation file: