A new irradiation growth model for Zr-based components of nuclear reactors for the DIONISIO code

Abstract

When zirconium-based materials are subjected to irradiation, dimensional changes occur due to irradiation creep and growth. Predicting the behavior of these phenomena is necessary to determine the maximum time of operation required to avoid possible mechanical problems, such as buckling of sheaths, cracks, sheath-cooling channel contact, etc. In this work, a model to evaluate the irradiation growth based on the evolution of microstructural defects such as dislocations and point defects is presented. Preliminary results obtained are in good agreement with experimental data. In addition, the model was incorporated as a new subroutine within the nuclear fuel code DIONISIO and some comparisons with experimental data and previous models in DIONISIO are presented.