Optimisation by mathematical modeling of physicochemical characteristics of concrete containers in radioactive waste management

Abstract

A method for obtaining an optimal concrete container composition used for storing radioactive waste from nuclear power plants is developed. It is applied to the radionuclides 60Co, 137Cs, 85Sr, and 54Mn. A set of recipes for concrete composition leading to an optimal solution is given.

Keywords

• concrete
• waste
• permeability
• mechanical characteristics
• leakage test