高放废物处置北山预选区地表岩体结构与岩体质量相关性及其应用研究

岩体工程质量是影响高放废物地质处置（HLW）工程长期稳定性和安全性的关键因素,也是处置库场址比选的重要依据。在地表岩体节理调查统计的基础上,采用RMR(relative metabolic rate)分级方案,探讨北山高放废物处置预选区内以花岗岩为主体围岩的岩体质量与岩体结构的对应特征,建立结构面间距D与RMR岩体质量总评分值之间的定量关系,对北山预选区芨芨槽地表岩体质量分布进行研究。研究结果表明,RMR与D值的点群分布具有扇形发散的正相关特征,随D值的增大,RMR亦呈增长趋势,但低级序岩体结构与岩体质量比高级序岩体表现出更好的对应关系。研究认为,选用RMR与D的点群中心线对应的线性方程评价花岗岩候选区的岩体质量可达到快速评价岩体质量、查明各级岩体空间分布特征的目的,同时也便于对不同候选场区进行大范围岩体质量对比。分析结果显示,北山芨芨槽预选地段BS16钻孔周边3 km2范围内主要以Ⅰ、Ⅱ级岩体为主,岩体质量总体较好且分布相对较为均匀。     

中国高放废物处置库甘肃北山预选区水文地质研究进展

文章回顾了1993年至今在甘肃北山地区开展的水文地质调查和研究工作,概述了该区水文地质特征,总结了以往工作中的经验和存在的问题,为该区今后的水文地质研究工作提供借鉴。     

高放废物处置库甘肃北山预选区水文地质特征研究

在高放废物深地质处置中，地下不是核素迁移的重要媒介。因此，水文地质工作是处置库选址中的主要内容之一。本文依据几年来的野外调查及前人的部分资料，阐明了我国高放废物处置库甘肃北山预选区的基本水文地质概况，以及地下水的循环交替条件和化学特征。研究表明，弱含水、低渗透、慢流速是区内主要水文地质特征，蒸发浓缩形成的高矿化是地下水的主要化学面貌。这一认识，为处置库选址提供了重要依据。     

高放废物处置库北山预选区泉水成因分析

文章通过前人资料的分析,结合水文地质调查工作,探讨了北山地区泉水的成因,认为该区分布的泉大部分是下降泉,接受潜水补给;少部分为上升泉,接受盆地地下水或断裂带地下水补给;属于北山内部的地下水循环交替方式之一,与深大断裂关系不明显。     

高放废物处置库甘肃北山预选区同位素水文学研究及设想

甘肃省北山地区是我国高放废物处置库场址重要预选区之一,花岗岩是处置库候选围岩。10余年来,在北山地区开展了水文地质和同位素水文学调查、研究工作,为场址评价提供了重要的水文地质依据。今后,在深入开展预选区水文地质研究工作中,应进一步开展同位素水文学研究,示踪地下水的补给来源,揭示水循环过程,测定地下水滞留时间和流速等,以获得高放废物处置场址特性评价所需的水文地质参数资料。     

高放废物处置库甘肃北山预选区地下水位动态特征

阐明了甘肃北山预选区地下水位动态特征及其与当地大气降水的关系,并对其动态类型进行了剖析,由此得出北山地区地下水源自当地大气降水补给的认识。为处置库预选区场址评价提供了水文地质依据。     

高放废物处置库预选区新构造运动特征

新构造活动强烈程度是高放废物处置库场址评价的一个重要指标。本文阐述新构造研究的指导思想、方法及其在高放废物处置库选址中的应用。通过东天山地区南、北地段对比研究,选出了在新近纪时期构造环境相对稳定或新构造活动强度相对微弱的东天山南部地区,作为高放废物处置库基地。研究结果表明它对场址评价是有意义的。     

高放废物处置库北山预选区地下水同位素组成特征及其意义

在高放废物处置库选址中,场地水文地质条件的认识极为重要,因为任何从处置库释放出来的放射性物质都将通过地下水搬运向人类生存环境或生物圈迁移.甘肃北山地区是我国高放废物处置库的重要预选区之一,位于我国西北甘肃省西北部.为了认识预选区的水文地质条件,从水文地质角度评价其作为高放废物处置库场地的适宜性,在过去的10 a,在该区开展了同位素水文地质调查工作.野外调查和氢、氧稳定同位素分析结果表明,研究区地下水主要源自大气降水补给.浅部地下水主要由现代区内降水补给形成,而深部地下水则可能由地质历史时期降水补给形成;浅部地下水系统具有相对开放性特征,水循环交替能力较强,而深部地下水系统具有相对封闭性特征,水循环交替能力较弱.     

高放废物处置库预选场地地学信息库的建立

本文以高放废物处置库预选场地甘肃北山玉门镇地学信息库的建立为例,详细阐述了地理信息系统在高放废物地质处置中的应用,并在此基础上分析了其应用前景,为不同层次的管理、科研人员提供了全新思路;介绍了将地理信息系统技术引入图件和资料管理的优点。     

高放废物地质处置库花岗岩体预选研究

简要介绍了应用遥感技术结合地质研究,优选高放废物地质处置库花岗岩体的思路和方法。以北山外围地区为例,通过遥感数据处理,遥感影像解译,岩体地质特征分析,岩体预选准则的建立,在野外勘查的基础上,预选了若干有利的花岗岩体。为优选高放废物地质处置库场址提供决策依据。     

CFC在中国高放废物处置库预选区地下水研究中的应用

本文介绍了地下水测年的CFC方法及其原理,并将这种方法实际应用于我国高放废物处置库预选区--甘肃北山地区的水文地质研究,结果表明,研究区内沟谷洼地浅部地下水的CFC年龄在15~26 a,基岩裂隙浅部地下水多为不含CFC的老水与含CFC的新水的混合水.在描述了确定混合比方法的基础上,根据样品CFC含量计算了研究区地下水的混合比.与氚相比,CFC是目前年轻地下水测年更好的工具,具有更多的优越性.     

高放废物处置库芨芨槽预选场址深部地下水同位素研究

深地质处置是目前国际上普遍接受的高放废物安全处置方案.对于这种方案而言,安全处置高放废物的前提是选择适宜的场址,而场址的适宜性在很大程度上取决于其水文地质条件.高放废物处置库场址需要低渗透岩体作为处置库围岩,对于低渗透岩体而言,经典和传统的水文地质研究方法受到了很大的限制,而同位素技术与其他水文地质方法结合时,却能发挥出良好的作用.本文以目前我国高放废物处置库预选场址之一的芨芨槽场址为例,重点讨论了同位素方法在花岗岩体场址水文地质研究中的应用.根据钻孔不同深度的地下水环境同位素(δD、δ18O、3H和14C)组成特征,结合场址水文地质条件,识别了区内地下水的来源,揭示了控制地下水运移交替速率的主要因素.结果表明,该区深部地下水14C年龄高达8000 a左右,说明其交替、运移十分缓慢,但同时也含有少量的氚,说明地下水以侧向补给的“老水”为主,接受当地大气降水入渗补给的“新水”所占比例很小.此外,通过地下水14C年龄与取样段岩芯采取率的对比,认识到对于区内的花岗岩体而言,决定地下水交替、运移速率的主要因素是裂隙的发育程度,而不是深度.     

高放废物地质处置研究中的矿物学问题

在高放废物地质处置研究中的一些矿物学问题应引起矿物学家的注意 。高放废物地 质处置库的缓冲/回填材料是选择以钠质蒙脱石为主要成分的钠基膨润土,还是以钙质蒙脱 石为主的钙基膨润土?怎样选择对99Tc、129I有较好吸附能力的硒汞矿、脆 硫锑铅矿和辉锑矿的替代物来作缓冲/回填材料中的添加剂,以能阻滞99Tc和129 I的迁移?沸石对某些放射性核素的吸附特征也需进一步研究。     

Thermo-mechanical Stability Analysis for a Multi-level Radioactive Waste Disposal Concept

To dispose of the spent fuels generated from the Korean nuclear power plants in an underground repository, a large area of about 4 km² is required. This could be a constraint for selecting an adequate repository site and it is required to investigate the possibility of a multi-level repository design. In this study different parameters related to the multi-level repository design such as the level distance, waste type disposed of at each level, and the time interval between the operations at the levels, were investigated using the three-dimensional code, FLAC3D. For obtaining more reliable results, rock properties measured from deep boreholes were used. From the analysis, it was possible to conclude that a multi-level repository concept could be an attractive alternative to reduce the underground area as well as to dispose of the spent fuels from Pressurized Water Reactors (PWR) and Canadian Deuterium Uranium (CANDU) reactors at different levels with different time schedules.     

Selection and Basic Properties of the Buffer Material for High-Level Radioactive Waste Repository in China

Radioactive wastes arising from a wide range of human activities are in many different physical and chemical forms, contaminated with varying radioactivity. Their common features are the potential hazard associated with their radioactivity and the need to manage them in such a way as to protect the human environment. The geological disposal is regarded as the most reasonable and effective way to safely disposing high-level radioactive wastes in the world. The conceptual model of geological disposal in China is based on a multi-barrier system that combines an isolating geological environment with an engineered barrier system. The buffer is one of the main engineered barriers for HLW repository. It is expected to maintain its low water permeability, self-sealing property, radio nuclides adsorption and retardation properties, thermal conductivity, chemical buffering property, canister supporting property, and stress buffering property over a long period of time. Bentonite is selected as the main content of buffer material that can satisfy the above requirements. The Gaomiaozi deposit is selected as the candidate supplier for China＇s buffer material of high level radioactive waste repository. This paper presents the geological features of the GMZ deposit and basic properties of the GMZ Na-bentonite. It is a super-large deposit with a high content of montmorillonite （about 75 %）, and GMZ-1, which is Na-bentonite produced from GMZ deposit is selected as the reference material for China＇s buffer material study.     

Mechanisms and Models for Bentonite Erosion Used for Geologic Disposal of High Level Radioactive Waste: A Review

The performance of the bentonite buffer in nuclear waste repository concept relies to a great extent on the buffer surrounding the canister having sufficient dry density. Loss of buffer material caused by erosion remains as the most significant process reducing the density of the buffer. In the worst case, the process is assumed to last as long as the free volume between the pellets in the pellets filled regions is filled with groundwater. Erosion rate and mass erosion are calculated based on the erosion model, and the measures are presented to prevent the geological disaster due to bentonite erosion. The groundwaters may solubilise the smectite particles in the bentonite and carry them away as colloidal particles. A dynamic model is developed for sodium gel expansion in fractures where the gel soaks up groundwater as it expands. The model is based on a force balance between and on smectite particles, which move in the water. Attractive van der Waals forces, repulsive electric diffuse layer (DDL) forces, gravity and buoyancy forces and forces caused by the gradient of chemical potential of the particles act to move the particle in the water. The effect of the fracture width and the frictions between particles and water and surrouding rock is analysed based on erosion model. The DDL forces strongly depend on the type of clay minerals and the type of ion and concentration in the water surrounding the particles. In the designed safe use of nuclear waste disposal (tens of thousands of years to hundreds of thousands of years), the safety of nuclear waste disposal is affected by the hydrodynamic and chemical effects, and bentonite erosion. Due to the bentonite erosion, the buffer/backfill layers become loose, and their permeability increases, which causes the nuclear element diffusion and convection, and even the nuclear disaster. In this paper, the mechanisms, models, experiments and control measures of bentonite erosion were systematically summarized. The current deficiencies of bentonite erosion were pointed out, and new methods were put forward to carry out the research for bentonite erosion. The measures were presented to prevent the geological disaster due to bentonite erosion through changes. The project is not only academic innovation, but also has a large practical significance. The research results of this project can be widely applied to the design, construction and maintenance of the bentonite buffer in nuclear waste repository.     

我国固体废物处理处置现状及对策

在分析我国固体废物产生及处理处置现状的基础上,阐述了固体废物处理处置的基本原则,提出了适合我国国情的综合治理措施。