Solidification of Simulated Radioactive Incineration Ash by Alkali-activated Slag Composite Cement
Creators
- 1. state Key Laboratory of Green Building Materials, China Building Materials Academy, Beijing (China)
- 2. China Academy of Engineering Physics, Mianyang (China)
Description
Simulated radioactive incineration ash (SRIA) was solidified by alkali-activated slag composite cement (AASCC) modified by metakaolin, zeolite, and polymer emulsion powder. The results show that the performance of solidified waste form containing 40% SRIA meets the requirements of GB 14569.1-93. The lowest leaching rate of Cs+ on 42nd days reaches 1.32 x 10-4 cm/d (GB 7023-86,25 degree C), cumulative leach percentage is only 0.041 cm. Also, the lowest 28 days compressive strength of solidified waste form is 45.6 MPa, and later strength growth is still high. The fast setting characteristic of AASCC overcomes effectively the disadvantageous influence caused by some components in SRIA on hydration of cement. The compressive strength of solidified waste is enhanced remarkably, and the ability of immobilizing radionuclide ions is also improved. This is mainly due to synergistic effect between metakaolin and zeolite. Polymer modification also improves the performance of solidified waste form significantly. The three-dimensional polymer network structure formed by emulsion powder in solidified waste form enhances its toughness and impact resistance, and the durability is improved by reducing interconnected pores and optimizing pore structure. However,it also results in reduction in compressive strength. Thus, it is concluded that the suitable dosage percentage is 5%. (authors)
Additional details
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 44
- Journal Issue
- 4
- Journal Page Range
- p. 400-407
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 43085016
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- ASHES; CEMENTS; CESIUM COMPOUNDS; COMBUSTION; COMPRESSION STRENGTH; EMULSIONS; HYDRATION; KAOLIN; LEACHING; MODIFICATIONS; OPTIMIZATION; POLYMERS; PORE STRUCTURE; POWDERS; RADIOACTIVE WASTE PROCESSING; SIMULATION; SLAGS; SOLIDIFICATION; WASTE FORMS; ZEOLITES
- Descriptors DEC
- ALKALI METAL COMPOUNDS; BUILDING MATERIALS; CHEMICAL REACTIONS; CLAYS; COLLOIDS; COMBUSTION PRODUCTS; DISPERSIONS; DISSOLUTION; INORGANIC ION EXCHANGERS; ION EXCHANGE MATERIALS; MANAGEMENT; MATERIALS; MECHANICAL PROPERTIES; MICROSTRUCTURE; MINERALS; OXIDATION; OXIDE MINERALS; PHASE TRANSFORMATIONS; PROCESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; RESIDUES; SEPARATION PROCESSES; SILICATE MINERALS; SOLVATION; THERMOCHEMICAL PROCESSES; WASTE MANAGEMENT; WASTE PROCESSING; WASTES
Optional Information
- Notes
- 3 figs., 8 tabs., 17 refs.