Development of matrix composition for cementation of non-process waste within the framework of Development Demonstration Center foundation for treatment Spent Nuclear Fuel (STF) to Federal State Unitary Enterprise (FSUE) “Mining and Chemical Combine” (MCC

Abstract

There were presented results of investigations on development of non-process liquid radioactive waste’s technique at Development Demonstration Center for exercise of innovative technologies for Spent Nuclear Fuel (STF), establishing at FSUE “MCC”. Investigations were carrying out on simulator of non-process waste formula. As cementing material were used Portland cement and iron-Portland cement, as sorption additives – Bentonite or clinoptilolite. According with results of investigations was given preliminary recommendations on cementation technology for scheduled complex of treatment STF at MCC.