Patent ID: 11961625
Assignee: NUSCALE POWER, LLC
Field: Engines, pumps, turbines (Mechanical engineering)
Classification: CPC G  H  Y | IPC G  H

Claim 9:
10. A nuclear reactor protection system, comprising:
a first logic circuit configured in hardware to logically derive a first safety determination based at least in part on a first set of inputs, wherein the first safety determination is associated with an estimated condition of a nuclear reactor or a portion thereof,
a second logic circuit configured in hardware to logically derive a second safety determination based at least in part on a second set of inputs, wherein the second safety determination is associated with the estimated condition;
a display interface module (DIM) coupled to the first and second logic circuits and configured in hardware to process the first and second safety determinations or representations thereof and for displaying on a display panel that is directly connected to the DIM;
a monitoring and indication bus (MIB) communicatively coupled to the first logic circuit, the second logic circuit, and the DIM, the MIB configured to communicate status and/or diagnostics information associated with the nuclear reactor protection system to the DIM for displaying on the display panel, wherein the status and/or diagnostics information includes the first and second safety determinations or representations thereof; and
a control circuit communicatively coupled to receive the first and second safety determinations from the first and second logic circuits, the control circuit configured to generate a safety action signal based on the first and second safety determinations, wherein
the safety action signal is configured to control a nuclear reactor safety actuator to address the estimated condition; and
the safety action signal is communicated over the MIB; and

wherein
the DIM is configured to generate one or more panel drive signals configured to operate the display panel to communicate a status of the nuclear reactor safety actuator according to the first and second safety determinations.