Parameter Sensitivity Analysis for Long-Term Nuclide Migration in Granite Barriers Considering a 3D Discrete Fracture–Matrix System

Yingtao Hu, Wenjie Xu, Ruiqi Chen, Liangtong Zhan, Shenbo He, Zhi Ding
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Abstract

As a geological barrier for high-level radioactive waste (HLW) disposal in China, granite is crucial for blocking nuclide migration into the biosphere. However, the high uncertainty associated with the 3D geological system, such as the stochastic discrete fracture networks in granite, significantly impedes practical safety assessments of HLW disposal. This study proposes a Monte Carlo simulation (MCS)-based simulation framework for evaluating the long-term barrier performance of nuclide migration in fractured rocks. Statistical data on fracture geometric parameters, on-site hydrogeological conditions, and relevant migration parameters are obtained from a research site in Northwestern China. The simulation models consider the migration of three key nuclides, Cs-135, Se-79, and Zr-93, in fractured granite, with mechanisms including adsorption, advection, diffusion, dispersion, and decay considered as factors. Subsequently, sixty MCS realizations are performed to conduct a sensitivity analysis using the open-source software OpenGeoSys-5 (OGS-5). The results reveal the maximum and minimum values of the nuclide breakthrough time Tt (12,000 and 3600 years, respectively) and the maximum and minimum values of the nuclide breakthrough concentration Cmax (4.26 × 10−4 mSv/a and 2.64 × 10−5 mSv/a, respectively). These significant differences underscore the significant effect of the uncertainty in the discrete fracture network model on long-term barrier performance. After the failure of the waste tank (1000 years), nuclides are estimated to reach the outlet boundary 6480 years later. The individual effective dose in the biosphere initially increases and then decreases, reaching a peak value of Cmax = 4.26 × 10−4 mSv/a around 350,000 years, which is below the critical dose of 0.01 mSv/a. These sensitivity analysis results concerning nuclide migration in discrete fractured granite can enhance the simulation and prediction accuracy for risk evaluation of HLW disposal.
考虑三维离散断裂-基质系统的花岗岩屏障中核素长期迁移的参数敏感性分析
作为中国高放射性废物(HLW)处置的地质屏障,花岗岩对于阻止核素迁移到生物圈至关重要。然而,与三维地质系统相关的高不确定性,如花岗岩中的随机离散断裂网络,极大地阻碍了高放射性废物处置的实际安全评估。本研究提出了一个基于蒙特卡罗模拟(MCS)的模拟框架,用于评估核素在断裂岩石中长期迁移的屏障性能。研究人员从中国西北某研究基地获得了有关断裂几何参数、现场水文地质条件和相关迁移参数的统计数据。模拟模型考虑了 Cs-135、Se-79 和 Zr-93 三种关键核素在断裂花岗岩中的迁移,并考虑了吸附、平流、扩散、弥散和衰变等机制因素。随后,利用开源软件 OpenGeoSys-5 (OGS-5) 进行了 60 次 MCS 实测,以进行敏感性分析。结果显示了核素突破时间 Tt 的最大值和最小值(分别为 12,000 年和 3600 年),以及核素突破浓度 Cmax 的最大值和最小值(分别为 4.26 × 10-4 mSv/a 和 2.64 × 10-5 mSv/a)。这些重大差异凸显了离散断裂网络模型的不确定性对长期阻隔性能的重大影响。据估计,在废物槽失效后(1000 年),核素将在 6480 年后到达出口边界。生物圈中的单个有效剂量最初增加,然后减少,在 35 万年左右达到峰值 Cmax = 4.26 × 10-4 mSv/a,低于临界剂量 0.01 mSv/a。这些关于离散断裂花岗岩中核素迁移的敏感性分析结果可以提高对高放射性废物处置风险评估的模拟和预测精度。
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