Investigation of Plant Control Strategies for a Supercritical CO2 Brayton Cycle Coupled to a Sodium-Cooled Fast Reactor using the ANL Plant Dynamics Code

by Anton Moisseytsev & James J. Sienicki
Argonne National Laboratory

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The development of a control strategy for the supercritical CO2 (S-CO2) Brayton cycle has been extended to the investigation of alternate control strategies for a Sodium-Cooled Fast Reactor (SFR) nuclear power plant incorporating a S-CO2 Brayton cycle power converter. Three alternative schemes for controlling the reactor side of the plant, including idealized, autonomous, and independent reactor control, in combination with the existing automatic control strategy for the S-CO2 Brayton cycle are explored using the ANL Plant Dynamics Code together with the SAS4A/SASSYS-1 Liquid Metal Reactor (LMR) Analysis Code System. The results show that autonomous SFR operation may be viable for the particular assumed load change transient and deserves further investigation for other transients and postulated accidents.