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。     

Investigation on healing behavior of unsaturated GMZ bentonite pellet mixture based on compressibility

Acta Geotechnica - Bentonite pellet mixture has been considered as an important candidate buffer/backfill material in deep geological repository for disposal of high-level radioactive waste. During...     

A coupled non-isothermal reactive transport model for long-term geochemical evolution of a HLW repository in clay

A numerical model of coupled saturated/unsaturated water flow, heat transfer and multi-component reactive solute transport is presented to evaluate the long-term geochemical evolution in bentonite, concrete and clay formation for a potential geological radioactive waste repository. Changes in formation porosity caused by mineral dissolution/precipitation reactions are taken into account. Simulations were carried out with a general-purpose multicomponent reactive transport code, CORE^2D V4. Numerical results show that pH in the bentonite porewater can vary from neutral to up to 13 over a time scale of 1 Ma although dissolution of silica minerals and precipitation of secondary calcium silicate hydrate (CSH) minerals in bentonite buffer the effect of the hyperalkaline plume. Mineral precipitation reduces the volume of pore space in bentonite close to the bentonite–concrete interface due to the precipitation of CSH minerals. Model results indicate that bentonite porosity decreases less than 25%. The hyperalkaline plume from the concrete only extends to a distance of 0.7 m in the clay formation over the time range of 1 Ma.     

考虑膨胀效应UH模型的有限元实现

高庙子膨润土已被确定为我国高放废物地质处置的首选缓冲/回填材料,进行其力学特性及应用模拟研究对合理设计处置库具有十分重要的意义。考虑膨胀效应的UH模型是在超固结非饱和土本构模型（非饱和土UH模型）的基础上提出的,因引入了土体团粒的吸水膨胀作用,使其适用于非饱和膨润土。基于有限元软件ABAQUS的二次开发平台,利用Fortran语言编制模型的UMAT（user-difined material）材料子程序,进行了考虑膨胀效应UH模型的有限元实现。然后针对高放废物处置概念模型,利用编制的模型子程序对高放废物处置系统进行了三维有限元模拟,并对渗流场和应力场的演化规律进行了初步探究。模拟结果显示处置系统中膨润土的内应力增加,土体的稳定性较好,说明选择高庙子膨润土作为缓冲/回填材料的合理性,也同时验证了程序的正确性。     

盐溶液法测定非饱和膨润土的水分特征曲线

对于高放废物的最终处置，深地质处置被国内外公认为最合适的方法，而膨润土也被认为是高放废物处置库缓冲回填材料的良好基质。鉴于膨润土各项性质研究的重要性。本文介绍了利用盐溶液法进行非饱和膨润土水分特征曲线的测定工作，发现盐溶液法适合测定吸力极高的非饱和土，是一种值得推广的方法。     

Modelling of bentonite–granite solutes transfer from an in situ full-scale experiment to simulate a deep geological repository (Grimsel Test Site, Switzerland)

The FEBEX experiment is a 1:1 simulation of a high level waste disposal facility in crystalline rock according to the Spanish radwaste disposal concept. This experiment has been performed in a gallery drilled in the underground laboratory Grimsel Test Site (Switzerland). Two boreholes parallel to the FEBEX drift were drilled 20 and 60 cm away from the granite–bentonite interface to provide data on potential bentonite–granite solutes transfer. Periodic sampling and analysis of the major ions showed: (a) the existence of solutes transfer from the bentonite porewater towards the granite groundwater, explaining the Cl⁻ and Na⁺ contents of the latter; (b) that the concentration of the natural tracers coming into the granite groundwater from the bentonite porewater increased over time. This bentonite–granite solutes transfer was modelled in order to predict the increase in the Cl⁻ and Na⁺ concentrations of the granite groundwater. The modelled results seem to confirm that the mechanism of solute migration in this scenario is that of diffusive transport. An effective diffusion coefficient of D_e = 5 × 10⁻¹¹ m²/s was that which best fitted the data obtained.     

Reactive transport modelling of the long-term interactions of corrosion products and compacted bentonite in a HLW repository in granite: Uncertainties and relevance for performance assessment

Here we present a long-term nonisothermal reactive transport model for the interactions of the corrosion products of a carbon-steel canister and the compacted bentonite of the engineered barrier of a high-level radioactive waste repository in granite. Canister corrosion causes an increase in the pH and the concentration of dissolved Fe²⁺ of the bentonite porewater. Iron precipitates as magnetite and siderite and sorbs via cation exchange and surface complexation on weak sites. Magnetite precipitation reduces significantly the porosity of the bentonite near the canister. The thickness of the zone of reduced porosity is 7 cm at t = 1 Ma. This thickness increases significantly when the dependence of the corrosion rate on the chemical conditions is considered and decreases 3 cm when smectite dissolution and analcime precipitation are taken into account. Model results are not significantly sensitive to the thermal transient and the effect of temperature on the corrosion rate. The conclusions of our simulations are consistent for the most part with those reported by others for engineered barrier systems at similar chemical conditions.     

高放废物深地质处置：回顾与展望

文章对我国高放废物地质处置研究的历史进行了回顾,并对未来发展进行了展望。我国的高放废物深地质处置研究开发从1985年开始,迄今为止可初步分为3个阶段：①起步和跟踪研究阶段（1985～1998）;②逐步发展阶段（1999～2005）;③政府规划指导阶段（2006至今）。20多年来,我国在国家法律法规、战略规划、选址、工程屏障、核素迁移研究等方面取得了显著进展。我国已经提出在2020年前建成地下实验室、21世纪中叶建成高放废物处置库的目标。研究开发和处置库工程建设分成3个阶段：试验室研究开发和处置库选址阶段（2006～2020）;地下现场试验阶段（2021-2040）和处置库建设阶段（2041～本世纪中叶）。经过全国筛选对比,已初步选定甘肃北山地区为重点预选区,系统的场址评价工作正在进行。已确定采用膨润土作为处置库的回填材料,并初步确定内蒙古高庙子膨润土为我国高放废物处置库的首选缓冲回填材料。工程设计、核素迁移研究和安全评价也取得了一定进展。1999年起与国际原子能机构开展了3期高放废物地质处置技术合作项目,对提高我国的技术水平起到了积极作用。20多年的研究开发工作为我国在21世纪完成高放废物地质处置任务奠定了基础。     

Porewater chemistry in compacted bentonite: Application to the engineered buffer barrier at the Olkiluoto site

Compacted bentonite is used as sealing and buffer material in engineered barrier systems (EBS) of high-level radioactive waste repositories. The chemical characteristics of this clay and its porewater affect the migration of radionuclides eventually released from the waste. They also determine the integrity and long-term performance of the clay barriers. Key features are the structural negative charge and the large proportion of structural (interlayer) water of the main mineral montmorillonite, which leads to exclusion of anions and a surplus of cations in a large part of the porosity space. The objective of this contribution was to assess the impact of different porosity model concepts on porewater chemistry in compacted bentonite in the context of the planned Finnish spent nuclear fuel repository at Olkiluoto. First, a structural model based on well-established crystallographic and electrostatic considerations was set up to estimate the fractions of the different porosity types. In view of the uncertainty related to the chemical properties of the interlayer water, two very different model concepts (anion-free interlayer, Donnan space), together with a well-established thermodynamic model for bentonite, were applied to derive the porewater composition of the bentonite buffer at Olkiluoto. The simulations indicate very similar results in the “free” water composition for the two models and thus support the validity of the reference porewater concept commonly used in performance assessment of waste repositories. Differences between the models are evident in the composition of the water affected by the surface charge (i.e. diffuse double layer and interlayer). These reflect the conceptual uncertainty in current multi-porosity diffusion models.     

新疆地区选建高放射性核废物处置库的可能性

高放废物选址是一项万年大计工程,需要多个预选场地的综合比较,决策废物处置库的具体选建场地。论述了高放废物处置库选址过程中需要考虑的主要问题,然后针对新疆的自然环境,水资源、花岗岩体和缓冲/回填材料的分布,以及区域地壳稳定性等因素,讨论了在新疆选建高放废物地质处置库的可能性,并提出了选址方法。     

中国高放废物地质处置缓冲材料大型试验台架和热-水-力-化学耦合性能研究

缓冲材料作为高放废物深地质处置库中一道重要的人工屏障,与高放废物容器和处置库围岩直接接触,在高放废物衰变热、辐射作用和地下水等影响下产生复杂的热-水-力-化学耦合作用,为了验证缓冲材料是否能长期有效地发挥其屏障材料的作用,核工业北京地质研究院利用高庙子钠基膨润土组装并运行了模拟中国高放废物地质处置室 尺寸的大型缓冲材料膨润土试验台架（China-Mock-Up）。建立了缓冲材料试验台架的安装和试验方法,依据实测数据和理论分析,揭示了热-水-力-化学耦合作用条件下膨润土中的相对湿度是在加热器的热效应和外部供水的湿效应共同作用下发生变化的,压实膨润土中应力的变化主要是由于膨润土遇水膨胀和加热器的热效应引起的,试验验证了模拟高放废物地质处置室内加热器（废物罐）运行初期的位移过程,为缓冲材料和高放废物地质处置库的设计提供了重要的工程参数和理论依据。     

中国高放废物深地质处置的缓冲材料选择及其基本性能

人类的许多生产、生活活动均可能产生不同活度的放射性废物,其中高放废物的安全处置倍受全球科学家和广大公众所重视。目前深地质处置被国际上公认为处置高放废物的最有效可行的方法。借鉴国外成熟的技术和经验,我国采用多重工程屏障系统(包括废物固化体、废物容器及其外包装和缓冲/回填材料)和适宜的围岩地质体共同作用,来确保高放废物与生物圈的安全隔离。膨润土由于具有极低的渗透性和优良的核素吸附等性能而被国际上选作缓冲材料的基础材料。经过全国膨润土矿床筛选,我国高放废物深地质处置库缓冲材料的研究以产自高庙子膨润土矿床深部的钠基膨润土作为基本组成材料。本文介绍了高庙子膨润土矿床的地质特征以及高庙子钠基膨润土的基本特征。该膨润土与国外同类型材料相比具有蒙脱石含量高(75%左右)、杂质矿物相对较少的特点,该材料的系统和深入研究对于开发我国缓冲回填材料技术、确保高放废物的安全有效处置有重要意义。     

极低放废物处置方法分析

对于放射性活度浓度很低,但又不得不管理的极低放废物,目前国际上对此并没有明确的可操作性定义,对极低放废物的处置方式也还在探索中。由于极低放废物含有一定量具有物理性和生物性的放射性核素,考虑到政治、社会及公众接受心理等因素,在参考低中废物管理模式基础上,按危险废物处置标准处置建造专门的处置库处置极低放废物是可行的。     

高放废物处置库选址中低渗透介质地质研究的几个问题

低渗透介质是阻碍有害物质在地下迁移良好的天然屏障, 因此成为高放废物处置库围岩类型的首选。本文通过对高放废物处置库选址中地质研究的回顾, 阐述了低渗透介质地质研究的特点, 对地质参数测定、取样、水流模拟、地球化学模拟进行了重点介绍。     

膨润土颗粒混合物的堆积性质与水-力特性研究进展

膨润土颗粒混合物是高放废物深地质处置库中的一种缓冲/回填材料,掌握其堆积性质与水-力特性是开展处置库安全性能评估的关键基础。本文全面回顾和总结了近年来国内外学者对膨润土颗粒混合物的堆积性质、持水特性、结构特征、渗透特性、胀缩特性及本构模型等方面的研究进展与取得的成果,展望了几个值得进一步研究的问题。结果表明,颗粒混合物的堆积性质与粒径级配密切相关;湿化过程中,颗粒混合物由初始松散结构逐渐转变为胶结融合结构,孔隙结构逐渐趋于均一化,并伴随着颗粒破碎和错动,进而影响其水-力特性。考虑到处置库实际运营环境的复杂性,颗粒混合物的原位填充技术以及多场(热-水-力-化)耦合条件下颗粒混合物的水-力特性是今后值得深入研究的方向。     

Investigating the hydromechanical behaviour of bentonite pellets by swelling pressure tests and discrete element modelling

Acta Geotechnica - Bentonite pellet mixtures are candidate material for the sealing of galleries in radioactive waste disposals. The hydromechanical behaviour of assemblies of bentonite pellets is...     

铀矿床作为高放废物处置库天然类似物的国内外研究进展

铀矿床具有目前国际上开发的高放废物深地质处置概念的相似特征，对其开展天然类比研究，是认识核素在地质环境中迁移行为的一种有效方法。本文阐述了高放废物深地质处置库天然类似物的一般概念及天然类比研究拟解决的科学问题。重点介绍了30年来国内外在天然类比研究中取得的主要成果、认识以及国内外研究进展。     

Geoscientific R&D for high level radioactive waste disposal in Sweden — current status and future plans

SKB (Svensk Kärnbränslehantering AB) is responsible for all handling, transport and storage of the nuclear wastes outside the Swedish nuclear power stations. According to Swedish law, SKB is responsible for an R&D-programme needed to take care of the radwastes. The programme comprises, among others, a general supportive geo-scientific R&D and the Äspö Hard Rock Laboratory (HRL) for more in-situ specific tasks.

Sweden is geologically located in the Fennoscandian shield which is dominated by gneisses and granitoids of Precambrian age. The Swedish reference repository concept thus considers an excavated vault at ca. 500 m depth in crystalline rocks. In this concept (KBS-3), copper canisters with high level waste will be emplaced in deposition holes from a system of tunnels. Blocks of highly compacted swelling bentonite clay are placed in the holes leaving ample space for the canisters. At the final closure of the repository, the galleries are backfilled with a mixture of sand and bentonite. This repository design aims to make the disposal system as redundant as possible. Although the KBS-3 concept is the reference concept, alternative concepts and/or repository lay-outs are also studied. The main alternative, currently under development at SKB, is disposal in boreholes with depths of 4–5 km. The geoscientific research will to a great extent be guided by the demands posed by the performance and safety assessments, as well as the constuctability issues. Some main functions of the geological barrier are fundamental for the long-term safety of a repository. These are: bedrock mechanical stability, a chemically stable environment as well as a slow and stable groundwater flux. The main time-table for the final disposal of long-lived radioactive waste in Sweden foresees the final selection of the disposal system and site during the beginning of next decade.     

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.