A nuclear reactor protection system includes a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs; and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.

A method (90) for determining at least one threshold value of at least one operating parameter of a nuclear reactor is implemented by an electronic determination system and includes the steps of determining (100) a first threshold value of a respective operating parameter for an operation of the reactor at a first power; and determining (110) a second threshold value of said parameter for an operation of the reactor at a second power. The operation at the lower power of the first and second powers is an operation continued for a duration of at least 8 hours over a 24-hour sliding window. The method also includes determining (120) a third threshold value of said parameter for an operation of the reactor at a third power between the first power and the second power.

An electro-technical device includes a first coil connected to a first sensor for receiving a current therefrom representative of a sensed condition, the first coil being anchored at first and second ends. A second coil is connected to a second sensor for receiving a current therefrom representative of a sensed condition, the second coil being anchored at first and second ends and being adjacent to the first coil. When the first and second coils receive an increased current from the first and second sensors, the first and second coils each create a magnetic flux that repel one another in order to cause at least one of the coils to break so that a shutdown signal can be sent.

An electro-technical device includes a first coil connected to a first sensor for receiving a current therefrom representative of a sensed condition, the first coil being anchored at first and second ends. A second coil is connected to a second sensor for receiving a current therefrom representative of a sensed condition, the second coil being anchored at first and second ends and being adjacent to the first coil. When the first and second coils receive an increased current from the first and second sensors, the first and second coils each create a magnetic flux that repel one another in order to cause at least one of the coils to break so that a shutdown signal can be sent.

An electronic device (18) is for managing the display of data to control a nuclear power plant. The data comes from a plurality of electronic control units (16A, 16B, 16C). Each control unit is configured to perform at least one action from among acquiring a value measured by a sensor (12A, 12B, 12C) and controlling an actuator (14A, 14B, 14C), the control units, sensor(s) and/or actuator(s) being according to several different nuclear safety classes. This electronic device (18) is able to be connected to the control units, and includes a set (25) of electronic module(s) (26A, 26B, 26C) for creating overlay(s) (28A, 28B, 28C). Each overlay contains information associated with one or several control units and according to a respective safety class; and a module (30) for generating a page (32) to be displayed, by superposition of several separate overlays.

An electronic device (18) is for managing the display of data to control a nuclear power plant. The data comes from a plurality of electronic control units (16A, 16B, 16C). Each control unit is configured to perform at least one action from among acquiring a value measured by a sensor (12A, 12B, 12C) and controlling an actuator (14A, 14B, 14C), the control units, sensor(s) and/or actuator(s) being according to several different nuclear safety classes. This electronic device (18) is able to be connected to the control units, and includes a set (25) of electronic module(s) (26A, 26B, 26C) for creating overlay(s) (28A, 28B, 28C). Each overlay contains information associated with one or several control units and according to a respective safety class; and a module (30) for generating a page (32) to be displayed, by superposition of several separate overlays.

A nuclear-reactor control-absorber drive mechanism includes a device for monitoring a potential situation of increase to overspeed of the absorber, configured to measure the number of control steps delivered to at least one of the first, second and third phases of the stator during a time window of preset duration or the number of rotation steps of the rotor during a time window of preset duration. The drive is also configured to compare the number of measured control steps with a preset maximum or the number of measured rotation steps with a preset maximum.

A nuclear-reactor control-absorber drive mechanism includes a device for monitoring a potential situation of increase to overspeed of the absorber, configured to measure the number of control steps delivered to at least one of the first, second and third phases of the stator during a time window of preset duration or the number of rotation steps of the rotor during a time window of preset duration. The drive is also configured to compare the number of measured control steps with a preset maximum or the number of measured rotation steps with a preset maximum.

A vacuum micro-electronics device that utilizes fissile material capable of using the existing neutron leakage from the fuel assemblies of a nuclear reactor to produce thermal energy to power the heater/cathode element of the vacuum micro-electronics device and a self-powered detector emitter to produce the voltage/current necessary to power the anode/plate terminal of the vacuum micro-electronics device.

A nuclear reactor power regulator adjusts reactor output based on a reactor output target value and a reactor output change rate. The regulator includes a reactor output calculating device that performs computation based on a thermal equilibrium from power signals of plant parameters to calculate a reactor output signal. A correcting device corrects a continuously obtained reactor output equivalent signal that is considered to be equivalent to a reactor output at a calculation interval of the output signal, so that the output equivalent signal coincides with the output signal. The correcting device calculates a continuous corrected output equivalent signal. A reactor output controlling device calculates a reactor output control signal for controlling the output of the reactor, using the corrected reactor output equivalent signal, the reactor output target value, and the reactor output change rate. A reactor output controller is operated based on the reactor output control signal.