Performance analyses of the communication networks of a modern supervision and control system of research reactors
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E. I. El-Madbouly
Abstract
The functions of the Instrumentation and Control (I&C) system in research reactors, the changes in its design according to the advances in the technology, and the internationally established safety requirements on the design and operational performance of this system are reviewed. The main features of the communication networks commonly used in the Supervision and Control systems (SCS) are presented. A methodology for the performance analysis of the communication networks of computer-based distributed SCS is developed and presented along with discussions. Application of this methodology to a modern SCS of a typical research reactor is illustrated.
Kurzfassung
Die Funktionen der I&C Leittechnik in Forschungsreaktoren, die Änderungen aufgrund des technologischen Fortschritts und die international etablierten Sicherheitsanforderungen an die Auslegung und die Betriebsleistung dieses Systems werden bewertet. Die Hauptmerkmale der üblicherweise in den Überwachungs- und Kontrollsystemen (SCS) verwendeten Kommunikationsnetzwerke werden dargestellt. Eine Methodik zur Leistungsanalyse dieser Kommunikationsnetzwerke wurde entwickelt und wird in diesem Beitrag vorgestellt und diskutiert. Die Anwendung dieser Methodik auf ein modernes SCS eines typischen Forschungsreaktors wird beschrieben.
References
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© 2009, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- AVR prototype pebble bed reactor: a safety re-evaluation of its operation and consequences for future reactors
- Design Concept of the High Performance Light Water Reactor
- Behavior of CANDU fuel under power pulse conditions at the TRIGA reactor of INR Pitesti
- Plate heat exchanger – inertia flywheel performance in loss of flow transient
- Performance analyses of the communication networks of a modern supervision and control system of research reactors
- Thermal analytical model for MoO3 ampoules irradiated in a high neutron flux
- Effect of using various grades of plutonium in the protective liquid wall of an IFE type fusion reactor
- A discrete ordinates scheme for void fraction evaluation with nonstandard reflective conditions and weakly divergent beams
- Application of the Laplace transform method for the albedo boundary conditions in multigroup neutron diffusion eigenvalue problems in slab geometry
- Modified Chebyshev polynomial (UN) approximation in the neutron transport theory and computation of critical half thicknesses
- Optimizing the dynamic response of the H. B. Robinson nuclear plant using multiobjective particle swarm optimization
- Assessment for inside building dispersion of aerosol from an outdoor radiological release
- Technical Notes/Technische Mitteilungen
- Analysis of a steam generator tube rupture under realistic initial and boundary conditions
