Abstract: A system and computer implemented method for automatically performing reload licensing analysis of a nuclear reactor and preparing and generating a reload licensing report. The system and method include collecting input data and processing a plurality of nuclear reactor analysis modules. Each of the nuclear reactor analysis modules receives analysis module input data and generates analysis output data. The analysis module input data is based at least in part on the collected input data. The method also includes verifying at least one analysis output data from one nuclear reactor analysis module by comparing the analysis output data to predetermined analysis output data for the one nuclear reactor analysis module. The method further includes generating a reload licensing report for the nuclear reactor as a function of the analysis output data from two or more nuclear reactor analysis modules.

Abstract: Systems and methods for a nuclear reactor that include developing a first peaking factor at a first burnup threshold for one or more fuel rods. A second peaking factor is developed at a second burnup threshold for the fuel rods. The second burnup threshold is greater than the first burnup threshold. A third peaking factor is developed and is associated with a peak average power threshold for the fuel rods. An adjusted peak nodal power is generated for the fuel rods as a function of a base peak nodal power, the first peaking factor, the second peaking factor, and the third peaking factor.

Abstract: The present invention, in one aspect, is a method for identifying an optimum core loading arrangement. The method generally has an initialization phase and a running, or search, phase. In the initialization phase, an initial core loading arrangement is identified based on the relative reactivity levels of the bundles to be loaded and the reactor core locations. Once the initial core loading arrangement is identified, such arrangement is then optimized, within the defined constraints, in the running phase. More specifically, in the running phase, each core location is analyzed to determine whether such core location reactivity level can be changed from the initial reactivity level to either satisfy a constraint or optimize cycle energy, or both.

Abstract: A method and system for identifying the maximum adverse impact of a mislocated nuclear fuel bundle placement in an nuclear core loading arrangement is presented. The method generally has an initialization phase and a "swap" case evaluation, or "search," phase. In the initialization phase, base conditions for a selected core loading arrangement are determined and parameters for exploring the mislocated fuel bundle loading error problem are set up. In the search phase, the core loading arrangement design space is explored for many combinations of mislocated fuel bundle pairs in order to find a mislocated fuel bundle pair that yields the most limiting core state. A computer system is used to execute specific program routines that simulate the operating conditions of a reactor having mislocation errors involving fuel bundle pairs in a core loading arrangement.