THE SPENT FUEL MANAGEMENT AND AUTOMATIC NUCLEAR CROSS-SECTION INPUT DATA GENERATION METHOD FOR NUCLEAR REACTOR CORE DESIGN

摘要

A method for managing a spent fuel and generating nuclear cross section input data for designing a nuclear reactor core are provided to prevent a human error and to reduce a time for obtaining input data of a design code for modeling a 3D core. Necessary input data is produced from output data of an ANC(Advanced Nodal Code) and an ALAMO(Automated Linkage of ANC modeling operations) code about the previously stored past cycles and is stored in a GUI(Graphic User Interface) database(S11). A current cycle nuclear reactor core loading pattern is produced and is displayed on the GUI screen(S12). The displayed current cycle nuclear core loading pattern is modified and changed(S13). The input data of the modified and changed current cycle nuclear reactor core loading pattern is databased and outputted to the electronic file type.