膨润土
离子强度
化学
胶体
放射性废物
放射性核素
微粒
背景(考古学)
环境化学
核化学
地质学
岩土工程
水溶液
物理化学
古生物学
有机化学
物理
量子力学
作者
Zhen Zhang,Jiaxi Heng,Qiang Jin,Zongyuan Chen,Wangsuo Wu,Zhijun Guo
出处
期刊:Radiochimica Acta
[R. Oldenbourg Verlag]
日期:2022-01-21
卷期号:110 (3): 219-227
被引量:2
标识
DOI:10.1515/ract-2021-1096
摘要
Abstract China is considering Beishan granitic formation (Gansu Province, China) as the site for high-level radioactive waste (HLW) repositories. Thus, it is crucial to understand the transport behavior of radionuclide in Beishan granitic media under disposal conditions. In this context, the co-transport of U(VI) (as the representative of radionuclides) and bentonite colloid (BC, from erosion of compacted bentonite) in particulate Beishan granite was studied as a function of important in-situ factors, such as BC concentration, ionic strength, pH and flow rate. We found that the increase of BC concentration (BC = 240–480 mg/L) did not affect the transport of individual BC, whereas it significantly facilitated the transport of U(VI). The increase of ionic strength ( I = 0.001–0.01 M NaCl) or decrease of pH (pH = 7.50–5.40) obviously inhibited the BC transport, where these inhibiting effects were relatively slight for the transport of U(VI). The increase of flow rate significantly facilitated both the transport of BC and U(VI). Finally, a two-site kinetic attachment/detachment model was applied to describe the breakthrough curves of individual and co-transport of BC. The experimental and modeling results of this study have a significant implication on the safety assessment of HLW repositories built in granitic formation.
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