A nuclear reactor power system includes: a reactor core comprising a plurality of nuclear fuel elements, each nuclear fuel element comprising: a first cooling channel passing through the nuclear fuel element; and a second cooling channel passing through the nuclear fuel element and fluidly isolated from the first cooling channel; a first cooling system configured to transport a first fluid coolant through the reactor core, the first cooling system fluidly connected to the first cooling channel of each nuclear fuel element; and a second cooling system configured to transport a second fluid coolant through the reactor core, the second cooling system fluidly connected to the second cooling channel of each nuclear fuel element. A direction of first fluid coolant flow through the first cooling channel is the same as a direction of second fluid coolant flow through the second cooling channel.

A radiation source reducing system and method for nuclear power plants whereby radiation source can be reduced are provided. The radiation source reducing system for nuclear power plants includes a dispersant injecting unit, which injects a dispersant into a coolant of a nuclear power plant coolant system. The dispersant is polyacrylic acid, and has an average molecular weight in a range of 16000 to 26000, inclusive.

A radiation source reducing system and method for nuclear power plants whereby radiation source can be reduced are provided. The radiation source reducing system for nuclear power plants includes a dispersant injecting unit, which injects a dispersant into a coolant of a nuclear power plant coolant system. The dispersant is polyacrylic acid, and has an average molecular weight in a range of 16000 to 26000, inclusive.

The present invention provides a small nuclear power generation system being safe and easily controlled by load following, and allowing reductions in manufacturing costs and maintenance and management costs. The small nuclear power generation system has a small nuclear reactor employing a load following control method. The reactor includes: a fuel assembly reactor core 4 having metallic fuel containing one or both of uranium (235, 238) and plutonium-239; a reactor vessel 1 containing the fuel assembly reactor core 4; metallic sodium loaded into the reactor vessel 1 and heated by the fuel assembly reactor core 4; and a neutron reflector 2 for achieving criticality in the reactor core with effective multiplication factor of neutrons emitted from the fuel assembly reactor core 4 being maintained at or above about 1. The load following control method of the reactor allows a neutron effective multiplication factor to be controlled by coupling the neutron reflector to spring or spiral metallic members and utilizing heat deformation in the metallic members due to the temperature in coolant metallic sodium to control the fast neutron reflection efficiency of the neutron reflector

Disclosed is a nuclear reactor system for use with a power grid. The nuclear reactor system comprising a nuclear reactor, an energy storage system coupled to the nuclear reactor, and a control circuit coupled to the nuclear reactor and the energy storage system. The control circuit is configured to monitor a power demand of the power grid, monitor a power output generated from the nuclear reactor, detect a change in the power demand, cause the energy storage system to temporarily compensate for the change in the power demand, and adjust the power output based on the change in the power demand.

A nuclear power plant control system (1) includes a control button (21) which receives an operation for controlling a control target device (40), a notification lamp (12) which notifies that a control signal corresponding to the operation received by the control button (21) arrives at a predetermined position on a path connected from a control panel (20) to the control target device (40), and a control signal inhibition unit (33) which inhibits a control signal from arriving at the control target device (40) in midstream between the predetermined position on the path and the control target device (40) in response to an operation received by a test permission button (11).

Provided in the present disclosure is a control system for a heat supply apparatus of a nuclear power plant, comprising: a first-stage pressure measurement means configured for measuring a first-stage pressure of a turbine to obtain a first-stage pressure signal; a high-exhaust pressure measurement means configured for measuring an exhaust pressure of a turbine high-pressure cylinder to obtain an exhaust pressure signal; a steam extraction heating flow rate measurement means configured for measuring a steam extraction heating flow rate to obtain a steam extraction heating flow rate signal; a data acquisition module configured for acquiring and transmitting the measured first-stage pressure signal, the measured exhaust pressure signal and the measured steam extraction heating flow rate signal to a core operation processing module; the core operation processing module; and a the signal output module.

Provided in the present disclosure is a control system for a heat supply apparatus of a nuclear power plant, comprising: a first-stage pressure measurement means configured for measuring a first-stage pressure of a turbine to obtain a first-stage pressure signal; a high-exhaust pressure measurement means configured for measuring an exhaust pressure of a turbine high-pressure cylinder to obtain an exhaust pressure signal; a steam extraction heating flow rate measurement means configured for measuring a steam extraction heating flow rate to obtain a steam extraction heating flow rate signal; a data acquisition module configured for acquiring and transmitting the measured first-stage pressure signal, the measured exhaust pressure signal and the measured steam extraction heating flow rate signal to a core operation processing module; the core operation processing module; and a the signal output module.

A method for controlling a pressurized water reactor, computer program product and control system, the pressurized water reactor includes a reactor core and a primary cooling circuit. The primary cooling circuit includes a primary cooling medium, which includes: acquiring a plurality of measurable reactor process variables and obtaining a plurality of non-measurable reactor process variables. The method further includes calculating future axial offsets at the end of a predetermined prediction time interval for a plurality of different possible boration/dilution actions based on the plurality of measurable reactor process variables and the plurality of non-measurable reactor process variables, the axial offset being a normalized difference between power of an upper half of the reactor core and a lower half of the reactor core. The calculation of the future axial offset for each of the plurality of different possible boration/dilution actions is performed in parallel.

A method for controlling a pressurized water reactor, computer program product and control system, the pressurized water reactor includes a reactor core and a primary cooling circuit. The primary cooling circuit includes a primary cooling medium, which includes: acquiring a plurality of measurable reactor process variables and obtaining a plurality of non-measurable reactor process variables. The method further includes calculating future axial offsets at the end of a predetermined prediction time interval for a plurality of different possible boration/dilution actions based on the plurality of measurable reactor process variables and the plurality of non-measurable reactor process variables, the axial offset being a normalized difference between power of an upper half of the reactor core and a lower half of the reactor core. The calculation of the future axial offset for each of the plurality of different possible boration/dilution actions is performed in parallel.