Next Article in Journal
Quality-Relevant Monitoring of Batch Processes Based on Stochastic Programming with Multiple Output Modes
Next Article in Special Issue
Current Advances in Biofouling Mitigation in Membranes for Water Treatment: An Overview
Previous Article in Journal
3D CPFD Simulation of Circulating Fluidized Bed Downer and Riser: Comparisons of Flow Structure and Solids Back-Mixing Behavior
Previous Article in Special Issue
Thermal Isolation of a Clean Alloy from Waste Slag and Polymeric Residue of Electronic Waste
Open AccessArticle

Stabilization/Solidification of Strontium Using Magnesium Silicate Hydrate Cement

1
Faculty of Infrastructure Engineering, Dalian University of Technology, Dalian 116024, China
2
Hebei Provincial Key Laboratory of Inorganic Nonmetallic Materials and Hebei Provincial Industrial Solid Waste Comprehensive Utilization Technology Innovation Center, College of Materials Science and Engineering, North China University of Science and Technology, Tangshan 063210, China
3
Department of Civil and Environmental Engineering, Imperial College London, London SW7 2AZ, UK
*
Author to whom correspondence should be addressed.
Processes 2020, 8(2), 163; https://doi.org/10.3390/pr8020163
Received: 17 November 2019 / Revised: 29 December 2019 / Accepted: 30 December 2019 / Published: 1 February 2020
(This article belongs to the Special Issue Gas, Water and Solid Waste Treatment Technology)
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 × 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. View Full-Text
Keywords: magnesium silicate hydrate; radioactive waste; stabilization/solidification; strontium; leaching magnesium silicate hydrate; radioactive waste; stabilization/solidification; strontium; leaching
Show Figures

Figure 1

MDPI and ACS Style

Zhang, T.; Zou, J.; Li, Y.; Jia, Y.; Cheeseman, C.R. Stabilization/Solidification of Strontium Using Magnesium Silicate Hydrate Cement. Processes 2020, 8, 163.

Show more citation formats Show less citations formats
Note that from the first issue of 2016, MDPI journals use article numbers instead of page numbers. See further details here.

Article Access Map by Country/Region

1
Back to TopTop