Solidification of Low Level Radioactive Waste by Alkali Activated Slag Cement with Hight Volume Reduction

Abstract

  A study of solidification of radioactive wastes by a tailored alkali activated slag cement (AASC) was carried out in both bench size tests and pilot plant tests.
The target wastes were concentrates,ion exchange resin,incinerator ash and HEPA filter in nuclear power stations and reprocessing facilities. In addition, an application of AASC was studied to be used in the cement grouting. It was confirmed that the solidified waste forms have a high content of each waste and suitable physical and chemical properties.
  The data of retention ability of radionuclides in the waste forms were obtained experimentally and it was suggested that the waste forms have the satisfactory retention required for safety operations in LLW disposal site.
  In this paper, the solidification behavior of AASC for the each waste was reported and an integrated treatment system was discussed and compared with the current solidification systems.