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处置低中水平放射性废物场地条件评估:中国南方案例研究。

Assessment of site conditions for disposal of low- and intermediate-level radioactive wastes: a case study in southern China.

机构信息

Guangdong Electric Power Design Institute, Guangzhou 510663, China.

出版信息

Sci Total Environ. 2012 Jan 1;414:624-31. doi: 10.1016/j.scitotenv.2011.10.060. Epub 2011 Nov 25.

Abstract

Near surface disposal of low- and intermediate-level radioactive wastes (LILW) requires evaluating the field conditions of the candidate site. However, assessment of the site conditions may be challenging due to the limited prior knowledge of some remote sites, and various multi-disciplinary data requirements at any given site. These situations arise in China as in the rest of the industrialized world, particularly since a regional strategy for LILW disposal has been implemented to protect humans and the environment. This paper presents a demonstration of the site assessment process through a case study focusing mainly on the geologic, hydrogeologic and geochemical characteristics of the candidate site. A joint on-site and laboratory investigation, supplemented by numerical modeling, was implemented in this assessment. Results indicate that no fault is present in the site area, although there are some minor joints and fractures, primarily showing a north-south trend. Most of the joints are filled with quartz deposits and would thus function hydraulically as impervious barriers. Investigation of local hydrologic boundaries has shown that the candidate site represents an essentially isolated hydrogeologic unit, and that little or no groundwater flow occurs across its boundaries on the north or east, or across the hilly areas to the south. Groundwater in the site area is recharged by precipitation and discharges primarily by evapo-transpiration and surface flow through a narrow outlet to the west. Groundwater flows slowly from the hilly area to the foot of the hills and discharges mainly into the inner brooks and marshes. Some groundwater circulates in deeper granite in a slower manner. The vadose zone in the site was investigated specially for their significant capability for restraining the transport of radionuclides. Results indicate that the vadose zone is up to 38m in thickness and is made up of alluvial clay soils and very highly weathered granite. The vadose zone has low saturated hydraulic conductivities on the order of 10(-5)cm/s and in this respect is well-suited for the disposal of LILW. The saturated formations are primarily made up of silt and moderately-to-slightly weathered granite, which exhibit even lower hydraulic conductivities, on the order of 10(-6)cm/s, also favorable for restraining the transport of radionuclides. Chemical analyses indicate that the groundwaters at the site are of the HCO(3)-Na · Ca and HCO(3) · SO(4)-Na · Ca types and are weakly corrosive to concrete and steel. Geochemical analyses indicate that the rock and soil materials (particularly weathered granite) at the site contain very small fractions of colloidal particles and exhibit low Cation Exchange Capacities (CEC), and would therefore have limited capacity for sorption of radionuclides. Groundwater flow and solute transport models of the candidate site have been developed using MODFLOW and MT3DMS, incorporating the data obtained during the assessment program. Calibration was based on the available measured groundwater level fluctuations and tracer concentrations from in situ dispersion tests. The longitudinal dispersion coefficient as determined in calibration is equal to 5.0 × 10(-3) m(2)/d. Numerical sensitivity analyses indicate that the hydraulic conductivity and the longitudinal dispersion coefficient are the key parameters controlling the transport of radionuclides, while the numerical model is not sensitive to changes in the effective porosity and the specific yield. Preliminary predictions have been performed with the calibrated model both for the natural setting of the site and the graded site in which the valleys of the site are backfilled with low permeable materials. Results indicate that the proposed site grading increases the safety of the site for disposal of LILW by reducing both the groundwater level and the hydraulic gradient and that radionuclide transport would not likely be a problem or cause groundwater contamination. Although there are some problems remaining to be addressed in future work, the conclusion of the assessment is that the conditions at this site are appropriate for LILW disposal. This study provides an example of the procedures necessary in an assessment of site conditions relevant to the safe disposal of LILW. Such an assessment is crucial to the site selection process and to subsequent environmental impact assessment.

摘要

近地表处置低中水平放射性废物(LILW)需要评估候选场址的现场条件。然而,由于一些偏远场址的先验知识有限,以及任何给定场址都需要各种多学科数据,因此评估场址条件可能具有挑战性。在中国和其他工业化国家都存在这种情况,特别是因为已经实施了 LILW 处置的区域战略,以保护人类和环境。本文通过一个主要侧重于候选场址地质、水文地质和地球化学特征的案例研究,展示了场址评估过程。在这项评估中,实施了现场和实验室联合调查,并辅以数值模拟。结果表明,尽管存在一些主要呈南北走向的小节理和裂隙,但场址区域不存在断层。大多数节理都被石英矿床填充,因此在水力方面起到了不透水屏障的作用。对当地水文边界的调查表明,候选场址代表了一个基本孤立的水文地质单元,其北部或东部边界以及南部丘陵地区的地下水流动很少或没有。该地区的地下水由降水补给,主要通过蒸发蒸腾和通过狭窄的出口向西的地表径流排泄。地下水从丘陵地区缓慢流向山脚下,主要排入内部小溪和沼泽。一些地下水在更深的花岗岩中以较慢的速度循环。特别研究了场址的包气带,以评估其对放射性核素迁移的显著抑制能力。结果表明,包气带厚达 38m,由冲积粘土土壤和高度风化的花岗岩组成。包气带的饱和水力传导率很低,约为 10(-5)cm/s,非常适合 LILW 的处置。饱和地层主要由粉土和中度至轻度风化的花岗岩组成,其水力传导率甚至更低,约为 10(-6)cm/s,也有利于抑制放射性核素的迁移。化学分析表明,该场址的地下水为 HCO(3)-Na·Ca 和 HCO(3)·SO(4)-Na·Ca 类型,对混凝土和钢具有弱腐蚀性。地球化学分析表明,该场址的岩土材料(特别是风化花岗岩)含有非常小的胶体颗粒分数,表现出较低的阳离子交换容量(CEC),因此对放射性核素的吸附能力有限。使用 MODFLOW 和 MT3DMS 开发了候选场址的地下水流动和溶质运移模型,结合了评估计划中获得的数据。校准基于可用的地下水水位波动和原位弥散试验的示踪剂浓度测量值。在校准中确定的纵向弥散系数等于 5.0×10(-3)m(2)/d。数值敏感性分析表明,水力传导率和纵向弥散系数是控制放射性核素迁移的关键参数,而数值模型对有效孔隙度和比产率的变化不敏感。使用校准后的模型对天然场址和用低渗透性材料回填场地山谷的分级场地进行了初步预测。结果表明,建议的场地分级通过降低地下水位和水力梯度,增加了 LILW 处置的场地安全性,并且放射性核素迁移不太可能成为问题或导致地下水污染。尽管未来的工作中仍有一些问题需要解决,但评估的结论是,该场地的条件适合 LILW 处置。本研究提供了安全处置 LILW 相关场地条件评估所需程序的示例。这种评估对于场地选择过程和随后的环境影响评估至关重要。

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