Mixed waste produced by nuclear facilities is diffi cult to dispose of, as it comprises both radiological and chemical hazards.

Considering that most mixed wastes are designated as low-level waste and that heavy metals are the major chemical hazards,

it is highly likely that the diffi culties associated with mixed waste disposal can be resolved by solidifi cation and stabilization

(S/S) treatment. The primary material used for S/S treatment of low-level radioactive and hazardous materials is ordinary

Portland cement (OPC). Conversely, vitrifi cation is recommended for high-level radioactive waste, especially nuclear fuel

material. Additionally, geopolymers with comparable performance to OPC have gained considerable attention recently. This

report reviews the binding mechanisms associated with S/S of OPC, geopolymer, and glass wasteform with radionuclides

and hazardous material, as well as structural degradation, leaching resistance, mechanical changes, and irradiation eff ects

in irradiation environments. It also introduces a multi-scale modeling approach for quantitative evaluation of the physical,

chemical, thermal, and mechanical properties of heterogenous OPC, geopolymers, and glass. Studies on S/S that consider

the properties of mixed waste can enable safe and effi cient mixed waste treatment and enhance the sustainability of nuclear

power generation.