Abstract The oxidation kinetics acceleration observed in Zircaloy-4 cladding in Pressurized Water Reactor could be partially due to metal irradiation damage occuring in-pile. To check this assumption, several ion irradiation tests of the Zircaloy-4 metal matrix were performed to reproduce the evolution of the metallurgical state in reactor. This study showed that the amorphization process of the intermetallic precipitates (SPPs) does not change significantly the oxidation rate of Zircaloy-4. Implantation of iron in the matrix to simulate iron dissolution from the SPPs has no real impact on the corrosion kinetics. However proton irradiations at 350 °C producing dislocation loops resulted in a significant increase in the oxidation rate.

中文翻译：

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金属基体离子辐照对Zircaloy-4氧化速率的影响

摘要 在压水反应堆中观察到的 Zircaloy-4 包壳的氧化动力学加速可能部分是由于堆中发生的金属辐照损伤。为了验证这一假设，对 Zircaloy-4 金属基体进行了几次离子辐照测试，以重现反应器中冶金状态的演变。该研究表明，金属间沉淀物 (SPP) 的非晶化过程不会显着改变 Zircaloy-4 的氧化速率。在基体中注入铁以模拟 SPP 中的铁溶解对腐蚀动力学没有实际影响。然而，在 350 °C 下产生位错环的质子辐照导致氧化速率显着增加。