A method of determination of a nuclear core loading pattern defining the disposition of fuel assemblies includes definition of at least one potential core loading pattern, calculation of predictive bowing of the fuel assemblies at the end of the operation cycle for each potential core loading pattern, the calculation being carried out by an automatic learning algorithm trained on a training data set comprising a plurality of others loading patterns and, for each of them, the measures of bowing of fuel assemblies at the end of cycle, evaluation of the at least one core loading pattern based on the predictive bowing calculations and at least one predetermined criteria, and selection of one of the potential core loading patterns.

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.

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 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 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 to determine a global core reactivity bias and the corresponding estimated critical conditions of a nuclear reactor core prior to achieving reactor criticality. The method first requires collection and evaluation of the inverse count rate ratio (ICRR) data; specifically, fitting measured ICRR vs. predicted ICRR data. The global core reactivity bias is then determined as the amount of uniform reactivity adjustment to the prediction that produces an ideal comparison between the measurement and the prediction.

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.

The generation of a nuclear core loading distribution includes receiving a reactor core parameter distribution associated with a state of a reference nuclear reactor core, generating an initial fuel loading distribution for a simulated beginning-of-cycle (BOC) nuclear reactor core, selecting an initial set of positions for a set of regions within the simulated BOC core, generating an initial set of fuel design parameter values utilizing a design variable of each of the regions, calculating a reactor core parameter distribution of the simulated BOC core utilizing the generated initial set of fuel design parameter values associated with the set of regions located at the initial set of positions of the simulated BOC core and generating a loading distribution by performing a perturbation process on the set of regions of the simulated BOC core to determine a subsequent set of positions for the set of regions within the simulated BOC core.

The generation of a nuclear core loading distribution includes receiving a reactor core parameter distribution associated with a state of a reference nuclear reactor core, generating an initial fuel loading distribution for a simulated beginning-of-cycle (BOC) nuclear reactor core, selecting an initial set of positions for a set of regions within the simulated BOC core, generating an initial set of fuel design parameter values utilizing a design variable of each of the regions, calculating a reactor core parameter distribution of the simulated BOC core utilizing the generated initial set of fuel design parameter values associated with the set of regions located at the initial set of positions of the simulated BOC core and generating a loading distribution by performing a perturbation process on the set of regions of the simulated BOC core to determine a subsequent set of positions for the set of regions within the simulated BOC core.

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.