A method and a system for monitoring a state of a nuclear power plant capable of reducing a state prediction error of a sensor during startup, full power, shut down operation of a nuclear power plant, and of providing an early warning, without an error alarm includes remotely and automatically diagnosing the state of a sensor, device, system and power plant. The method and comprises: a first layer that compares a sensor measurement value and a device measurement value with predicted values so as to detect anomalies of the sensor and the device; a second layer that classifies a type of the sensor and diagnoses the presence or absence of an anomaly of the sensor on the basis of an anomaly value of the sensor provided from the first layer.

A control assembly (10) for a nuclear reactor includes a reactivity control device (11) comprising a control rod cluster (12) comprising an attaching head (22), and a drive rod (14) comprising an attaching device (16) for attaching the drive rod (14) to the attaching head (22). The attaching device (16) is movable between a connection position and a disconnection position. The drive rod (14) and the attaching device (16) define an axial trough recess (34) forming a sleeve (35). A checking device (13) engages with the reactivity control device (11) comprising a probe rod (36) which is free to move translationally in the sleeve (35) and comprises a lower end (38) abutting the attaching head (22) of the control rod cluster (12).

An exposure dose measurement simulation device according to an embodiment of the present invention includes: a virtual work area generating portion that generates a virtual work area corresponding to a work area of a radiation facility; and an exposure dose prediction portion that predicts an exposure dose of a worker positioned in the virtual work area, wherein the exposure dose prediction portion includes a database portion that includes first data on a spatial dose rate of the radiation facility and second data on a position of a radiation source in the radiation facility, and a first exposure dose calculation portion that calculates the exposure dose of the worker positioned in the virtual work area using the first data and second data.

An exposure dose measurement simulation device according to an embodiment of the present invention includes: a virtual work area generating portion that generates a virtual work area corresponding to a work area of a radiation facility; and an exposure dose prediction portion that predicts an exposure dose of a worker positioned in the virtual work area, wherein the exposure dose prediction portion includes a database portion that includes first data on a spatial dose rate of the radiation facility and second data on a position of a radiation source in the radiation facility, and a first exposure dose calculation portion that calculates the exposure dose of the worker positioned in the virtual work area using the first data and second data.

The invention relates to a device for controlling a plurality of nuclear reactors in clusters, comprising, for each reactor, a plurality of sensors for measuring operating parameters as well as a system for controlling the nuclear reactor, the nuclear reactors being grouped into clusters having a cluster head.

The invention relates to a device for controlling a plurality of nuclear reactors in clusters, comprising, for each reactor, a plurality of sensors for measuring operating parameters as well as a system for controlling the nuclear reactor, the nuclear reactors being grouped into clusters having a cluster head.

A nuclear power plant includes a nuclear structure, a frontline support equipment, and a support structure. The nuclear structure includes, and is configured to protect from incurring damage due to a damaging event, at least one of a nuclear reactor or a nuclear fuel storage. The frontline support equipment is configured to perform a fundamental safety function. The support structure is spatially separate from the nuclear structure and includes an initiating support equipment configured to trigger the frontline support equipment to perform the fundamental safety function such that the fundamental safety function is performed independently of the initiating support equipment subsequent to the triggering. The support structure may be a non-protected structure that is not configured to protect the initiating support equipment from incurring damage due to the damaging event.

A nuclear power plant includes a nuclear structure, a frontline support equipment, and a support structure. The nuclear structure includes, and is configured to protect from incurring damage due to a damaging event, at least one of a nuclear reactor or a nuclear fuel storage. The frontline support equipment is configured to perform a fundamental safety function. The support structure is spatially separate from the nuclear structure and includes an initiating support equipment configured to trigger the frontline support equipment to perform the fundamental safety function such that the fundamental safety function is performed independently of the initiating support equipment subsequent to the triggering. The support structure may be a non-protected structure that is not configured to protect the initiating support equipment from incurring damage due to the damaging event.

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.

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.