Assessment of glass dissolution kinetics, under disposal relevant temperature and pH environments, is required to credibly estimate radionuclide release rates from vitrified radioactive waste. Leaching of the International Simple Glass (ISG) under acidic to hyperalkaline conditions was examined. Forward rate measurements have been obtained using the dynamic leaching SPFT protocol and rate parameters for B, Na and Si in the basic regime; errors in rates predicted using these parameters at high pH and temperature are significant because the fitting uses logarithmic data. Longer term behaviour under hyperalkaline conditions, representative of some disposal environments, was investigated using the PCT and MCC-1 static leaching protocols with Ca(OH)₂ solutions for up to 120 days (PCT) and 720 days (MCC-1). In hyperalkaline conditions dissolution was incongruent for all elements and the presence of alternating zirconia-rich and zirconia-poor alteration layers was observed on all leached monoliths, indicating the occurrence of a self-organisation phenomenon during leaching.

为了可靠地估算玻璃化放射性废物中的放射性核素释放速率，需要在处置相关温度和pH环境下评估玻璃溶解动力学。研究了在酸性至高碱性条件下对国际简单玻璃（ISG）的浸出。使用动态浸出SPFT协议和基本方案中B，Na和Si的速率参数已经获得了前向速率测量。在高pH和高温下使用这些参数预测的速率误差很大，因为拟合使用对数数据。使用具有Ca（OH）₂的PCT和MCC-1静态浸出方案研究了在高碱性条件下（代表某些处置环境）的长期行为解决方案最长可使用120天（PCT）和720天（MCC-1）。在高碱性条件下，所有元素的溶解均不一致，并且在所有浸出的整料上均观察到交替出现的富氧化锆和贫氧化锆交替变化层的存在，表明在浸出过程中发生了自组织​​现象。