Safe Operation of the BOR-60 Development Reactor under Power Station Conditions

摘要

Using BOR-60 as an example, the characteristic features of the safe operation of a nuclear power station with a BN reactor are analyzed from the point of view of irregularities in the operating conditions of the basic equipment and departures from the engineering parameters. The reactor's self-regulating properties which smooth the transient conditions occurring with perturbations in reactivity, and in sodium flow and reactor inlet temperature are demonstrated. Regulation using neutron flux and using the sodium temperature at the reactor outlet are compared from the point of view of increasing the reliability of the control system and minimizing temperature stresses in elements of the circuit during transient processes. Mathematical and experimental data on the optimization of emergency shut-down conditions of the power station and the shut-down cooling of circuits containing different types of equipment are analyzed. Ways and means are described for monitoring the condition of the vessel, fuel subassemblies, and equipment within the vessel during operation at power and during recharging. Sodium-water steam generator operating experience is analyzed and experience is described of steam generator leak monitoring and safety systems in accidents. (ERA citation 08:002147)