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http://dx.doi.org/10.22807/KJMP.2022.35.1.25

Manufacture of non-sintered cement solidifier using clay, waste soil and blast furnace slag as solidifying agents: Mineralogical investigation  

Jeon, Ji-Hun (Department of Geology and Research Institute of Natural Science (RINS), Gyeongsang National University (GNU))
Lee, Jong-Hwan (Department of Geology and Research Institute of Natural Science (RINS), Gyeongsang National University (GNU))
Lee, Woo-Chun (Department of Geology and Research Institute of Natural Science (RINS), Gyeongsang National University (GNU))
Lee, Sang-Woo (Department of Geology and Research Institute of Natural Science (RINS), Gyeongsang National University (GNU))
Kim, Soon-Oh (Department of Geology and Research Institute of Natural Science (RINS), Gyeongsang National University (GNU))
Publication Information
Korean Journal of Mineralogy and Petrology / v.35, no.1, 2022 , pp. 25-39 More about this Journal
Abstract
This study was conducted to evaluate the manufacturing process of non-sintered cement for the safe containment of radioactive waste using low level or ultra-low level radioactive waste soil generated from nuclear-decommissioning facilities, clay minerals, and blast furnace slag (BFS) as an industrial by-product recycling and to characterize the products using mineralogical and morphological analyses. A stepwise approach was used: (1) measuring properties of source materials (reactants), such as waste soil, clay minerals, and BFS, (2) manufacturing the non-sintered cement for the containment of radioactive waste using source materials and deducing the optimal mixing ratio of solidifying and adjusting agents, and (3) conducting mineralogical and morphological analyses of products from the hydration reactions of manufactured non-sintered cement solidifier (NSCS) containing waste concrete generated from nuclear-decommissioning facilities. The analytical results of NSCS using waste soil and clay minerals confirmed none of the hydration products, but calcium silicate (CSH) and ettringite were examined as hydration products in the case of using BFS. The compressive strength of NSCS manufactured with the optimum mixing ratio and using waste soil and clay minerals was 3 MPa after the 28-day curing period, and it was not satisfied with the acceptance criteria (3.44 MPa) for being brought in disposal sites. However, the compressive strength of NSCS using BFS was estimated to be satisfied with the acceptance criteria, despite manufacturing conditions, and it was maximized to 27 MPa at the optimal mixing ratio. The results indicate that the most relevant NSCS for the safe containment of radioactive waste can be manufactured using BFS as solidifying agent and using waste soil and clay minerals as adsorbents for radioactive nuclides.
Keywords
Nuclear-decommissioning facilities; Radioactive waste; Non-sintered cement; Solidifier; Solidifying agent;
Citations & Related Records
Times Cited By KSCI : 7  (Citation Analysis)
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