Journal
PROCESSES
Volume 8, Issue 2, Pages -Publisher
MDPI
DOI: 10.3390/pr8020163
Keywords
magnesium silicate hydrate; radioactive waste; stabilization; solidification; strontium; leaching
Categories
Funding
- National Natural Science Foundation of China [51778101, 61704017, 51808217]
- National Key R&D program of China [2017YFE0107000]
- State Key Laboratory of Coastal and O ffshore engineering of Dalian University of Technology [LP1808]
- Dalian High-level Talent Innovation Program [2017RQ051]
- fundamental Research Funds for the Central Universities [DUT19JC27]
- Natural Science Foundation of Hebei Province [E2019209403]
- Key R&D Program of Hebei Province [19273803D]
- Post-doctoral Research Project of Hebei Province [B2019003028]
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Magnesium silicate hydrate (M-S-H) cement, formed by reacting MgO, SiO2, and H2O, was used to encapsulate strontium (Sr) radionuclide. Samples were prepared using light-burned magnesium oxide and silica fume, with sodium hexametaphosphate added to the mix water as a dispersant. The performance of the materials formed was evaluated by leach testing and the microstructure of the samples was also characterized. The stabilizing/solidifying effect on Sr radionuclide in the MgO-SiO2-H2O system with low alkalinity is demonstrated in the study. The leaching rate in a standard 42-day test was 2.53 x 10(-4) cm/d, and the cumulative 42-day leaching fraction was 0.06 cm. This meets the relevant national standard performance for leaching requirements. Sr2+ was effectively incorporated into the M-S-H hydration products and new phase formation resulted in low Sr leaching being observed.
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