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 (100) a reference principal PCI margin for a reference loading pattern of the fuel assemblies in the core; calculating (110) a reference secondary PCI margin for the reference pattern; calculating (120) a modified secondary PCI margin for a modified loading pattern of the fuel assemblies in the core, and calculating (130) 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 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 (100) a reference principal PCI margin for a reference loading pattern of the fuel assemblies in the core; calculating (110) a reference secondary PCI margin for the reference pattern; calculating (120) a modified secondary PCI margin for a modified loading pattern of the fuel assemblies in the core, and calculating (130) 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 defective fuel bundle location system for use with a heavy water moderated nuclear fission reactor having a fueling machine, including a test tool defining an internal volume, the test tool being configured to be received within both the fueling machine and a corresponding fuel channel of the reactor, and a test container defining an internal volume, wherein the test container is configured to be received within the internal volume of the test tool and the internal volume of the test container is configured to receive primary fluid from the reactor when the test tool is disposed within the corresponding fuel channel of the reactor.

A neutron detector is disclosed herein. The neutron detector can include a housing defining a cavity, wherein the housing is configured to permit an amount of neutrons emitted from a core of a nuclear reactor to enter the cavity. The neutron detector can also include an amount of a neutron sensitive material dispositioned within the cavity, wherein the neutron sensitive material is configured to generate and emit gamma rays upon interacting with the amount of neutrons. The neutron detector can further include an amount of electron emissive material configured to generate and emit a current of electrons upon interacting with the emitted gamma rays, wherein the current of electrons is indicative of the amount of neutrons emitted from the core of the nuclear reactor.

A neutron detector is disclosed herein. The neutron detector can include a housing defining a cavity, wherein the housing is configured to permit an amount of neutrons emitted from a core of a nuclear reactor to enter the cavity. The neutron detector can also include an amount of a neutron sensitive material dispositioned within the cavity, wherein the neutron sensitive material is configured to generate and emit gamma rays upon interacting with the amount of neutrons. The neutron detector can further include an amount of electron emissive material configured to generate and emit a current of electrons upon interacting with the emitted gamma rays, wherein the current of electrons is indicative of the amount of neutrons emitted from the core of the nuclear reactor.

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.

In an apparatus for evaluating reliability of a nuclear power plant operator, an expected task finishing time for each task of the operator is calculated based on input data for reliability evaluation of the operator to determine a task completion time for each task of the operator based on the calculated expected task finishing time and the input data. An initial time for the tasks is determined based on the input data and the task completion time for a current task. A total execution time of the operator is calculated based on the determined task completion time and initial time. An available time allowed for the operator to complete the tasks is calculated based on a predetermined allowed time and the determined initial time. A task failure probability is obtained from the difference between the calculated total execution time and the calculated available time based on probability distribution information.

A fuel movement simulator system includes a virtual reality (VR) system configured to generate a virtual refuel floor environment; and a fuel movement simulator assembly configured to provide a physical interface to the virtual refuel floor environment, the fuel movement simulator assembly including a replica mast, a replica control console connected to the replica mast, and a support structure configured to support the replica mast and replica control console.

This abnormality diagnosis system for diagnosing abnormalities in a plant is provided with: an abnormality diagnosis control unit which, with respect to an instrument parameter measured in a plant determined to have an indication of abnormality, predicts the development of the instrument parameter by extrapolation, and which generates an abnormality manifestation pattern that is a pattern of behavior of the instrument parameter after prediction; and a data storage unit which stores a plurality of abnormality model patterns PA, PB that are patterns of behavior of the instrument parameters corresponding to causes CA1, CA2, CB1, CB2 of plant abnormality. The abnormality diagnosis control unit makes a matching determination between the abnormality manifestation pattern that has been generated and the plurality of abnormality model patterns PA, PB stored in the data storage unit, and identifies, as the cause of the abnormality in the abnormality manifestation pattern.