Accident Resistance of Molten-Salt Nuclear Reactor

详细

The aim of the present work is to examine the possibilities of the MSR-I molten-salt nuclear actinide-incinerator reactor with a cavity-type core as possessing internal and passive safety characteristics and meeting the requirements imposed on next-generation reactors. Starting from the premises that the basic principles of nuclear safety must not differ from all other types of reactors the MSR-I reactor was analyzed in transient processes without activation of the accident protection system in situations where fuel could not be discharged into subcritical drainage tanks because of operator error or failure of the emergency discharge system. A computational study showed that the basic types of emergency situations can be overcome without destroying the protective barriers or actuating accident protection systems.