“…The disposal of high-level radioactive waste in China comprises immobilization in an inert substrate and subsequent deep geological disposal in a geological repository [ 8 , 9 , 10 ]. Glass solidification is currently the only industrially available technology for treating HLW, and borosilicate glass is considered to be a good glass solidification substrate due to its good chemical durability and irradiation resistance [ 7 , 11 , 12 ]. All elements in HLW can be accommodated in borosilicate, but the low solubility of some long-lived radioactive actinides, such as Np, Pu, Cm, and Am, in borosilicate glass can limit the development of glass curing technology.…”