Investigation of (3)H, (99)Tc, and (90)Sr transport in fractured rock and the effects of fracture-filling/coating material at LILW disposal facility

对裂隙岩石中 (3)H、(99)Tc 和 (90)Sr 的迁移进行研究,并探讨低中放射性废物处置设施裂隙充填/涂层材料的影响

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Abstract

Batch adsorption, batch diffusion, and flow-through column experiments were conducted using groundwater and fractured rock collected in unsaturated zone to increase our understanding of sorption and transport behavior of radionuclides. Increasing K(d) values were observed in the sequence (90)Sr, (99)Tc, and (3)H regardless of the geological media tested. For all sorbing radionuclides, K(d) values for the fracture-filling/coating material were observed to be higher than those for without fracture-filling/coating material regardless of the groundwater. These higher K(d) values are the result of zeolite mineral in filling/coating material of fractured rock. The batch diffusion and flow-through column experiments were also conducted using the same fractured rock sample, and the results of diffusion and column experiments showed similar trend of radionuclide sorption and transport to sorption experiment. In this study, sorption K(d) of radionuclide was determined and used to increase our understanding of radionuclide retardation through fracture-filling/coating materials.

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