Thermal-hydraulic model of the reactor facility with lead coolant in the ATHLET code

Thermal-hydraulic model of the reactor facility with lead coolant in the ATHLET code

This article presents the results of the creation of a thermal-hydraulic model of a reactor facility with lead coolant based on the BREST-OD-300. Neutron physics was not considered. The work carried out calculations and modeling of the stationary process and transient modes, such as: shutdown of one...

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Veröffentlicht in:Journal of physics. Conference series 2018-11, Vol.1133 (1), p.12013
Hauptverfasser: Chudinova, V A, Nikonov, S P
Format: Artikel
Sprache:eng
Schlagworte:
Coolants
Hydraulic models
Neutron physics
Nuclear safety
Shutdowns
Stationary processes
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Zusammenfassung:This article presents the results of the creation of a thermal-hydraulic model of a reactor facility with lead coolant based on the BREST-OD-300. Neutron physics was not considered. The work carried out calculations and modeling of the stationary process and transient modes, such as: shutdown of one of the MCP at different reactor power, disconnection of one of the feed pumps. The ATHLET code developed in GRS (Society for the Safety of Installations and Reactors, Garching, Germany) is used as a calculation program.
ISSN:1742-6588
1742-6596
DOI:10.1088/1742-6596/1133/1/012013