The French concept developed to dispose high-level radioactive waste in geological repository relies on glassy waste forms, isolated from the claystone host rock by steel containers. Understanding interactions between glass and surrounding materials is key for assessing the performance of a such system. Here, isotopically tagged SON68 glass, steel and claystone were studied through an integrated mockup conducted at 50 °C for 2.5 years. Post-mortem analyses were performed from nanometric to millimetric scales using TEM, STXM, ToF-SIMS and SEM techniques. The glass alteration layer consisted of a crystallized Fe-rich smectite mineral, close to nontronite, supporting a dissolution/reprecipitation controlling mechanism for glass alteration. The mean glass dissolution rate ranged between 1.6 × 10⁻² g m⁻² d⁻¹ to 3.0 × 10⁻² g m⁻² d⁻¹, a value only 3–5 times lower than the initial dissolution rate. Thermodynamic calculations highlighted a competition between nontronite and protective gel, explaining why in the present conditions the formation of a protective layer is prevented.

法国提出的将高放射性废物处置在地质处置库中的概念依赖于玻璃状废物形式，这些形式是通过钢制容器与粘土岩基质隔离的。了解玻璃与周围材料之间的相互作用是评估此类系统性能的关键。在这里，通过在50°C下进行了2.5年的集成样机研究了带有同位素标记的SON68玻璃，钢和粘土石。使用TEM，STXM，ToF-SIMS和SEM技术，从纳米级到毫米级进行了事后分析。玻璃蚀变层由结晶的富铁蒙脱石矿物组成，接近蒙脱石，支持玻璃蚀变的溶解/再沉淀控制机制。玻璃的平均溶解速度为1.6×10 ^-2  g m^-2  d ^-1至3.0×10 ^-2 g m ^-2  d ^-1，该值仅比初始溶出度低3-5倍。热力学计算突显了囊脱石和保护性凝胶之间的竞争，解释了为什么在当前条件下可以防止形成保护层。