Zuckerburg Institute for Water Research, Jacob Blaustein Institutes for Desert Research, Ben Gurion University of the Negev, Midreshet Ben Gurion 8499000, Israel.
Glenn T. Seaborg Institute, Lawrence Livermore National Laboratory, PO Box 808, Livermore, CA 94550, USA.
Sci Total Environ. 2021 Feb 25;757:143818. doi: 10.1016/j.scitotenv.2020.143818. Epub 2020 Nov 19.
The influence of montmorillonite colloids on the mobility of Pu, U and Cs through a chalk fracture was investigated to assess the transport potential for radioactive waste. Radioisotopes of each element, along with the conservative tracer tritium, were injected in the presence and absence of montmorillonite colloids into a naturally fractured chalk core. In parallel, batch experiments were conducted to obtain experimental sorption coefficients (K, mL/g) for both montmorillonite colloids and the chalk fracture material. Breakthrough curves were modelled to determine diffusivity and sorption of each radionuclide to the chalk and the colloids under advective conditions. Uranium sorbed sparingly to chalk (log K = 0.7 ± 0.2) in batch sorption experiments. U(VI) breakthrough was controlled primarily by the matrix diffusion and sorption to chalk (15 and 25% recovery with and without colloids, respectively). Cesium, in contrast, sorbed strongly to both the montmorillonite colloids and chalk (batch log K = 3.2 ± 0.01 and 3.9 ± 0.01, respectively). The high affinity to chalk and low colloid concentrations overwhelmed any colloidal Cs transport, resulting in very low Cs breakthrough (1.1-5.5% mass recovery). Batch and fracture transport results, and the associated modelling revealed that Pu migrates both as Pu (IV) sorbed to montmorillonite colloids and as dissolved Pu(V) (7% recovery). Transport experiments revealed differences in Pu(IV) and Pu(V) transport behavior that could not be quantified in simple batch experiments but are critical to effectively predict transport behavior of redox-sensitive radionuclides. Finally, a brackish groundwater solution was injected after completion of the fracture flow experiments and resulted in remobilization and recovery of 2.2% of the total sorbed radionuclides which remained in the core from previous experiments. In general, our study demonstrates consistency in sorption behavior between batch and advective fracture transport. The results suggest that colloid-facilitated radionuclide transport will enhance radionuclide migration in fractured chalk for those radionuclides with exceedingly high affinity for colloids.
研究了蒙脱土胶体对通过白垩裂缝迁移 Pu、U 和 Cs 的影响,以评估放射性废物的迁移潜力。在存在和不存在蒙脱土胶体的情况下,将每种元素的放射性同位素以及保守示踪剂氚注入天然裂缝白垩岩心。同时,进行了批实验以获得蒙脱土胶体和白垩岩心的实验吸附系数(K,mL/g)。根据穿透曲线,在对流条件下,确定了每种放射性核素在白垩岩和胶体中的扩散和吸附。铀在批吸附实验中对白垩岩的吸附能力较弱(log K = 0.7 ± 0.2)。U(VI)的穿透主要受基质扩散和对白垩岩的吸附控制(有和没有胶体时分别为 15%和 25%的回收率)。相比之下,Cs 强烈吸附于蒙脱土胶体和白垩岩(批吸附 log K = 3.2 ± 0.01 和 3.9 ± 0.01)。对白垩岩和胶体的高亲和力以及胶体 Cs 的低浓度使得胶体 Cs 迁移变得微不足道,从而导致 Cs 穿透量非常低(质量回收率为 1.1-5.5%)。批处理和断裂传输结果以及相关建模表明,Pu 既作为吸附在蒙脱土胶体上的 Pu(IV),也作为溶解的 Pu(V)(回收率为 7%)进行迁移。运输实验揭示了 Pu(IV)和 Pu(V)的迁移行为的差异,这些差异无法通过简单的批实验来量化,但对于有效地预测氧化还原敏感放射性核素的迁移行为至关重要。最后,在完成断裂流动实验后注入了咸地下水溶液,导致从之前实验中吸附在岩心中的放射性核素中有 2.2%重新移动和回收。总的来说,我们的研究表明,在批处理和对流断裂传输之间吸附行为的一致性。结果表明,对于与胶体具有极高亲和力的放射性核素,胶体促进的放射性核素迁移将增强裂缝白垩中的放射性核素迁移。