A computer-implemented method for analyzing nuclear reactor data comprising acts of: receiving, from one or more sensors associated with an operating nuclear reactor, data indicative of an operating condition of the reactor; determining, by a reactor core modeling system that is adapted to model a nuclear reactor having a core including a plurality of fuel assemblies and based at least in part of the operating condition of the nuclear reactor, a plurality of fuel moves for certain groups of the plurality of fuel assemblies within the core, wherein the act of determining the plurality of fuel moves comprises acts of: determining, by the reactor core modeling system for a plurality of fuel cycles of the nuclear reactor, a plurality of possible group moves, each possible group move of the plurality of group moves associated with at least one fuel cycle of the plurality of fuel cycles; and determining an optimal group move for the at least one fuel cycle by determining whether one or more predefined limits associated with the reactor are exceeded for each possible group move; removing any possible group move from the plurality of group moves when one or more predefined limits are determined to be exceeded; and determining, for each possible group move remaining in the plurality of possible group moves, a score associated with the possible group move; determining, by the reactor core modeling system, an optimal sequence of group moves from the remaining plurality of possible group moves, wherein each sequence of group moves has a time separation between the group moves over multiple fuel cycles; and moving, based at least in part on the optimal group move for the cycle, one or more fuel assemblies within the core. receiving, from one or more sensors associated with an operating nuclear reactor, data indicative of an operating condition of the reactor; determining, by a reactor core modeling system that is adapted to model a nuclear reactor having a core including a plurality of fuel assemblies and based at least in part of the operating condition of the nuclear reactor, a plurality of fuel moves for certain groups of the plurality of fuel assemblies within the core, wherein the act of determining the plurality of fuel moves comprises acts of: determining, by the reactor core modeling system for a plurality of fuel cycles of the nuclear reactor, a plurality of possible group moves, each possible group move of the plurality of group moves associated with at least one fuel cycle of the plurality of fuel cycles; and determining an optimal group move for the at least one fuel cycle by determining whether one or more predefined limits associated with the reactor are exceeded for each possible group move; removing any possible group move from the plurality of group moves when one or more predefined limits are determined to be exceeded; and determining, for each possible group move remaining in the plurality of possible group moves, a score associated with the possible group move; determining, by the reactor core modeling system, an optimal sequence of group moves from the remaining plurality of possible group moves, wherein each sequence of group moves has a time separation between the group moves over multiple fuel cycles; and moving, based at least in part on the optimal group move for the cycle, one or more fuel assemblies within the core. determining, by the reactor core modeling system for a plurality of fuel cycles of the nuclear reactor, a plurality of possible group moves, each possible group move of the plurality of group moves associated with at least one fuel cycle of the plurality of fuel cycles; and determining an optimal group move for the at least one fuel cycle by determining whether one or more predefined limits associated with the reactor are exceeded for each possible group move; removing any possible group move from the plurality of group moves when one or more predefined limits are determined to be exceeded; and determining, for each possible group move remaining in the plurality of possible group moves, a score associated with the possible group move; determining whether one or more predefined limits associated with the reactor are exceeded for each possible group move; removing any possible group move from the plurality of group moves when one or more predefined limits are determined to be exceeded; and determining, for each possible group move remaining in the plurality of possible group moves, a score associated with the possible group move; determining, by the reactor core modeling system, an optimal sequence of group moves from the remaining plurality of possible group moves, wherein each sequence of group moves has a time separation between the group moves over multiple fuel cycles; and moving, based at least in part on the optimal group move for the cycle, one or more fuel assemblies within the core.