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.

当对锆基材料进行辐照时，由于辐照蠕变和生长而发生尺寸变化。对这些现象的行为进行预测对于确定避免可能的机械问题（如护套弯曲，裂纹，护套冷却通道接触等）所需的最大运行时间是必要的。在这项工作中，将基于辐射增长来评估模型介绍了微观结构缺陷如位错和点缺陷的演变。初步结果与实验数据吻合良好。此外，该模型已作为新的子例程纳入了核燃料代码DIONISIO中，并与DIONISIO中的实验数据和以前的模型进行了一些比较。