To assess the safety for disposal of radioactive waste cement composite, the leaching of Cs-137, Co-60, Mn-54 and Sr-85 from a waste composite into a surounding fluid has been studied [1, 2]. Leaching tests were carried out in accordance with a method recommended by IAEA |2, 3|. Determination of retardation factors, KF, and coefficients of distribution, kd, using a simplified mathematical model for analysing the migration of radionuclides, has been developed. |4, 7, 8|
Results presented in this paper are examples of results obtained in a 10 year mortar and concrete testing project, which will influence the design of the engineered trenche system for future central Yugoslavian radioactive waste storage center. |7, 8|.