A method, system, and apparatus for the thermal storage of nuclear reactor generated energy including diverting a selected portion of energy from a portion of a nuclear reactor system to an auxiliary thermal reservoir and, responsive to a shutdown event, supplying a portion of the diverted selected portion of energy to an energy conversion system of the nuclear reactor system.

A method, system, and apparatus for the thermal storage of nuclear reactor generated energy including diverting a selected portion of energy from a portion of a nuclear reactor system to an auxiliary thermal reservoir and, responsive to a shutdown event, supplying a portion of the diverted selected portion of energy to an energy conversion system of the nuclear reactor system.

Provided is an apparatus for evaluating a response time of a plant protection system. The apparatus includes: a classification module classifying a design process related to a response time requirement of each channel performing a safety function into four operations of a safety analysis operation, a system design operation, a response time analysis operation, and a response time test operation; and an integrated evaluation module determining whether a response time evaluation is proper based on a time t1 derived in the safety analysis operation, a time t2 derived in the system design operation, a time t3 derived in the response time analysis operation, and a time t4 derived in the response time test operation.

A method of determining reactivity of a nuclear reactor by a reactivity computer may include receiving a neutron detector response for a discrete period of time, performing a statistical check on the neutron detector response, determining if the neutron detector response is acceptable based on the statistical check, and calculating reactivity using a prior delayed neutron concentration if the neutron detector response is not acceptable and using a newly calculated delayed neutron concentration if the neutron detector response is acceptable.

The present invention relates to a screen sharing system of a nuclear power plant main control room for improving operation safety of a power plant. According to an example of the present invention, a power plant control screen of each operator is shared in real-time among other operators by a simple manipulation such that operators can easily simultaneously check a power plant operation screen of other operators, whereby a mistake of another operator can be detected and manipulated in time, thus improving operation safety of a power plant.

A method, system, and apparatus for the thermal storage of nuclear reactor generated energy including diverting a selected portion of energy from a portion of a nuclear reactor system to an auxiliary thermal reservoir and, responsive to a shutdown event, supplying a portion of the diverted selected portion of energy to an energy conversion system of the nuclear reactor system.

One variation of a method for deploying a nuclear reactor system includes: constructing a tunnel at a particular location; and installing the nuclear reactor, loaded with a first core assembly, within the tunnel. The method further includes, during an operating period: in response to detecting a high-energy demand period: triggering operation of the nuclear reactor at a first capacity, directing a first portion of energy output to a charging station for charging electric vehicles, and directing a second portion, less than the first portion, of energy output to a gas sequestration subsystem; and, in response to detecting a low-energy demand period, triggering operation of the nuclear reactor at a second capacity less than the first capacity, directing a third portion of energy, less than the first portion, output to the charging station, and directing a fourth portion of energy, exceeding the second portion, output to the gas sequestration subsystem.

A method for calculating a PCI margin associated with a loading pattern of a nuclear reactor including a core into which fuel assemblies are loaded according to the loading pattern is implemented by an electronic system. The fuel assemblies include fuel rods each including fuel pellets of nuclear fuel and a cladding surrounding the pellets. This method includes calculating a reference principal PCI margin for a reference loading pattern of the fuel assemblies in the core; calculating a reference secondary PCI margin for the reference pattern; calculating a modified secondary PCI margin for a modified loading pattern of the fuel assemblies in the core, and calculating a modified principal PCI margin for the modified pattern, depending on a comparison of the modified secondary PCI margin with the reference secondary PCI margin.

A reactor water radioactivity concentration of a nuclear power plant can be predicted with high accuracy. First, a plant state quantity prediction value is calculated by using a physical model that describes plant state quantities of the power plant including a flow rate of feedwater and a metal corrosion product concentration in feedwater of the reactor water is calculated. Next, data for supervised learning is created, and the data for supervised learning includes the previously calculated plant state quantity prediction value and a plant state quantity such as the flow rate of feedwater, the metal corrosion product concentration in feedwater, a metal corrosion product concentration in reactor water, and a radioactive metal corrosion concentration of the reactor water in the reactor as input data and includes a radioactive metal corrosion concentration in the reactor water which is an actual measured value as output data, and a predictive model is trained.

A nuclear-power-plant computer-based procedure display device is disposed in a main control room of a nuclear power plant, and includes a operating procedure storage unit that stores a computer-based procedure in which plant operation procedures of the nuclear power plant are divided into procedure steps and listed, a operating procedure display unit that displays the computer-based procedure, and a operating procedure display control unit that controls display of the computer-based procedure. In a case where the procedure step displayed on the operating procedure display unit is selected by an operator, the operating procedure display control unit displays an indication that the procedure step is selected, on the operating procedure display unit.