OPTIMIZING THE IN-CORE FUEL MANAGEMENT OF BWRS USING ROSA

摘要

The in-core fuel management of a nuclear reactor is a challenging task due to the virtually infinite number of possible loading patterns one could theoretically adopt. The ROSA (Reloading Optimization by Simulated Annealing) code is an optimization tool that has been successfully used in the last couple of decades to facilitate the core design of several Pressurized Water Reactors. In this paper we discuss the ongoing development of a version of ROSA capable of performing the core design of Boiling Water Reactors. We focus the discussion on the modifications of the neutronic module of the code that are needed to improve the accuracy when performing depletion calculations of BWRs.