Swelling of metals under irradiation is largely studied in the nuclear industry for its impact on the safe and efficient operation of reactors. However, the case of aluminum alloys remains poorly documented as they are exclusively used in nuclear research reactors which operate at lower temperatures than nuclear power plants. Void swelling in aluminum alloys, which results from the cavities induced by the fast neutron flux in reactor, is measurable only at high fluences, for which few measurement points are available. In this study, samples with various quenching rates were used in order to simulate the variations obtainable during the fabrication of large reactor components. A first series of samples were irradiated with heavy ions in single beam (Au⁴⁺) to understand the impact of the quenched microstructure on the voids swelling. A second series of samples were irradiated in a triple beam (W⁹⁺, He⁺ and Si⁺) to simulate the aluminum transmutation occurring inside reactors. Samples were investigated at very fine scale and characterized to understand the key mechanisms of swelling. Then, quantitative measurements of the swelling were performed in each sample. A high dispersion of the swelling values and a higher value are observed after ion irradiation compared to neutron irradiation for a similar irradiation dose, which seems to be related to the very high damage rate created by ion-irradiation. Therefore, it appears relevant to complement the description of swelling in aluminum alloys with a modeling approach. Swelling values from the literature were incorporated into a Brailsford & Bullough swelling model for two different damage rates, after estimating the parameters of the model from the literature. This work aims at a better comprehension of the swelling of aluminum alloys both from a quantitative and qualitative point of view and draws the basics requirements for future swelling models.

金属在辐照下的膨胀在核工业中被广泛研究，因为它对反应堆的安全和有效运行的影响。然而，铝合金的情况仍然缺乏记录，因为它们专门用于在比核电站更低的温度下运行的核研究反应堆。铝合金中的空洞膨胀是由反应堆中快中子通量引起的空腔引起的，只能在高通量下进行测量，可用的测量点很少。在这项研究中，使用具有不同淬火速率的样品来模拟大型反应器组件制造过程中可获得的变化。第一系列样品用单束重离子（Au ⁴⁺) 了解淬火微观结构对空隙膨胀的影响。用三束光束（W ⁹⁺、He ⁺和 Si ⁺) 来模拟反应器内发生的铝嬗变。对样品进行了非常精细的研究和表征，以了解膨胀的关键机制。然后，对每个样品进行溶胀的定量测量。与类似辐照剂量的中子辐照相比，在离子辐照后观察到溶胀值的高度分散和更高的值，这似乎与离子辐照产生的非常高的损伤率有关。因此，用建模方法补充铝合金膨胀的描述似乎是相关的。在估计文献中模型的参数后，文献中的膨胀值被合并到用于两种不同损坏率的 Brailsford & Bullough 膨胀模型中。