Control of sodium cooled fast breeder nuclear power-stations considered from a safety point of view
Abstract
The evolution of safety control systems for the French sodium cooled pool type fast breeder reactors Phenix and Super Phenix is outlined. The major design features of the plants are summarized, and the theoretical models that have been used in conjunction with experimental results to obtain data on the dynamic behavior of the Phenix reactor are discussed. The basic operating guidelines for the plants are given. The control and safety systems, including the plant protection system, sub-assembly cooling control system, reactivity comparator, and in-line data computer are described in detail, along with the techniques for detection and localization of cladding ruptures.
- Publication:
-
International Federation of Automatic Control, 6th Triennial World Congress
- Pub Date:
- 1975
- Bibcode:
- 1975ifac.proc...10D
- Keywords:
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- Liquid Metal Fast Breeder Reactors;
- Nuclear Power Plants;
- Nuclear Reactor Control;
- Reactor Safety;
- Sodium Graphite Reactors;
- Computerized Simulation;
- Control Simulation;
- Energy Technology;
- Reactor Design;
- Energy Production and Conversion