Reactors with Heavy Liquid-Metal Coolants and Some Thermohydraulic Data for them.

UDC: 
621.039.534

Issue of journal:

Abstract: 

The problem of inherent advanced safety of reactors with heavy liquid-metal coolants is considered in the paper by example of the projects of BREST-OD-300 and SVBR-100 reactors. Key specifications of these reactors are given. Results of preliminary thermohydraulic calculation of a central fuel assembly of the BREST-OD-300 core (triangular lattice of fuel elements) are demonstrated. Also the design of a thermohydraulic model for planned experimental research of the SVBR-100 core is in detail described.

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