Safe operation of the BOR-60 experimental fast reactor in power plant conditions

On the basis of the BOR-60 facility an analysis is made of characteristic requirements for safe operation of a fast-reactor power plant, from the standpoint of stability against perturbations in the operation of the main components and systems and against deviations from the design values of process parameters. The authors demonstrate the self-regulation properties of the facility which ensure smooth transient regimes even when there are perturbations in reactivity and in the flow rate and temperature of the sodium at the reactor inlet. Regulation by neutron flux and by sodium outlet temperature are compared from the point of view of increasing the reliability of the control system and minimizing temperature strains in the components during transient processes. The paper analyses calculated and experimental data on optimization of emergency shut-down and cooling regimes using different combinations of equipment. The means and methods used to verify the state of the reactor vessel, fuel assemblies and in-vessel reactor systems during operation on power and during reloading are described; operating experience with sodium/water steam generators is analysed, as in the use of leak verification, control and protection for steam generators under accident conditions. It is concluded that the methods and means used to ensure safe operation of the BOR-60 can be applied in the power plants with fast sodium-cooled reactors which are being planned for the future. (author)