Advances in immobilization of radionuclide wastes by alkali activated cement and related materials

Nuclear power is seen a significant part of new energy industry because of the low carbon emission feature and high efficiency. Safe and reliable immobilization of radionuclide wastes from nuclear power station is important for its operation. When the Portland cement-based solidifying materials encounter unsatisfying acid resistance, alkali activated cements (AACs) emerge as more durable, low-cost and environmentally friendly options. This paper provides an overview of recent advances of research on immobilization of radionuclide wastes by AAC and related materials. It discusses mechanisms and efficiency of different AACs on the immobilization of low- and intermedium-level radionuclide wastes, representatively the simulating radionuclides strontium and cesium. Immobilization of other radionuclides, such as Co-60, Cd-113 and I-129, by AACs is also reviewed. It is agreed that the immobilization efficiency of radioactive nuclides in AACs is generally better than that in Portland cement-based materials. Technical challenges and future research and development are proposed.

Automated summary

This paper provides an overview of recent advances in the immobilization of radionuclide wastes by alkali activated cements (AACs) and related materials. It discusses the mechanisms and efficiency of AACs in immobilizing different radionuclides, as well as the technical challenges and future research directions.