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。     

原型处置库

论述高放废物地质处置研究中的原型处置库的概念、建造目的和研究的主要内容,以及它在处置库系统性能评价中的作用。原型处置库的研究工作,可以在普通地下实验室中进行（如瑞典的魧sp觟地下实验室）,也可以在特定场址地下实验室中进行（如美国尤卡山的ESF坑道）,它是以往20多年前地下实验室研究中演示阶段的扩展和延伸,是高放废物地质处置研究中最终确认处置库场址的一个必不可少的研究步骤,同时也为处置库地下工程的详细设计提供最接近于当地建库实际的各类技术参数。     

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.     

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。     

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。     

世界高放废物地质处置库选址研究概况及国内进展

高放废物是核能事业发展的必然产物。它的安全处置是核能事业持续发展的前提 ,已受到世界各国的高度重视。文中阐述了高放废物深地质处置的一般概念。同时重点介绍了世界上一些国家处置库选址研究的主要内容和研究进展 ,例如 ,美国把处置库建造过程分为场地推荐、场地的特征评价、处置库场地的选择和批准、领取场地执照和处置库建造设计的审批、处置库的建造 5个阶段 ;德国的选址研究工作包括地电和地热研究 ,重力、地震、地球化学、水文地质、同位素地球化学及微生物研究等 ;瑞典在花岗岩中建成了地下实验室 ,并制定了实验室的总体研究目标等等。另外也介绍了中国在甘肃省北山进行的高放废物地质处置库选址工作的情况 ,研究表明北山地区为一地壳稳定区 ,也是地下水贫水区且地下水流速缓慢 ,有利于处置库的建造 ,进一步的地面地质、水文地质勘察工作及钻探工程工作正在进行中。伴随着这些工作的完成 ,中国将大大缩短在高放废物地质处置研究方面与发达国家的距离。     

高放废物深地质处置及国内研究进展

核能在产生电力造福社会的同时 ,也留下了放射性废物。我们有责任对这些废物实施安全和正确的管理。本文阐述了高放废物深地质处置的一般概念及处置库选址研究中的若干问题 ,同时介绍了国内高放废物深地质处置研究的进展.     

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。     

关于地下实验室分类的讨论

论述了现有的地下实验室的分类,对普通地下实验室与特定场址地下实验室的主要特征进行了对比分析,论述了各国地下实验室的研究概况,对特定场址地下实验室的概念进行了讨论。鉴于在现行的地下实验室分类中,对特定场址地下实验室的定义似乎界定过宽,因为有些该类型的地下实验室,缺乏明确的历史定位,最终没有起到特定场址地下实验室应起的作用。笔者建议,只有建在经本国政府批准的最终处置库场址上的地下实验室,才可称作为特定场址地下实验室,如美国的WIPP和ESF以及芬兰的ONKALO。因为只有这类地下实验室,才能真正起到论证处置库场址适宜性和高放废物处置方案可行性的作用。     

Subterranean microorganisms and radioactive waste disposal in Sweden

In 1987, microbiology became a part of the Swedish scientific program for the safe disposal of high level nuclear waste (HLW). The goal of the microbiology program is to understand how subterranean microorganisms will interact with the performance of a future HLW repository. The Swedish research program on subterranean microbiology has mainly been performed at two sites in granitic rock aquifers at depths ranging from 70 m down to 1240 m, the Stripa research mine in the middle of Sweden and the Äspö Hard Rock Laboratory (HRL) situated on the south eastern coast of Sweden. Some work has also been performed in cooperation with other national or international research groups in Sweden, Canada and at the natural analogue sites Oklo in Gabon and Maqarin in Jordan. The following conclusions are drawn. There is a very high probability of the existence of a deep subterranean biosphere in granitic rock. The documented presence of a deep biosphere implies that relevant microbial reactions should be included in the performance assessment for a HLW repository. A HLW repository will be situated in a subterranean biosphere that is independent of solar energy and photosynthetically produced organic carbon. The ultimate limitation for an active microbial life will be the availability of hydrogen as energy source over time, and hydrogen has indeed been found in most deep groundwaters. Sulphide producing microorganisms are active in environments typical for a Swedish HLW repository, and the potential for microbial corrosion of the copper canisters must be considered. The bentonite buffer around the copper canisters will be a hostile environment for most microbes due to the combination of radiation, heat and low water availability. Discrete microbial species can cope with each of these constraints, and it is theoretically possible that sulphide producing microbes may be active inside a buffer, although the experiments conducted thus far have shown the opposite. Microorganisms have the capability to enzymatically recombine radiolysis oxidants formed by radiation of water. It has earlier been concluded that the migration of radionuclides due to sorption on microorganisms can be neglected. The influence of microbially produced complexing agents remains to be studied at realistic conditions in deep groundwater. Microorganisms have been found in natural alkaline groundwaters, but it could not be conclusively demonstrated that they were in situ viable and growing, rather than just transported there from neutral groundwater. A possible hypothesis based on the obtained results from investigations of natural alkaline groundwaters is that fresh concrete may be a bit too extreme for active life even for the most adaptable microbe – but this remains to be demonstrated.     

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。     

中国高放废物处置库选址中灵敏地质特征的初步确认

本文首先根据中国、瑞士和日本3国高放废物处置概念的相似性，建立中国第一处置库系统性能评价模型；然后通过对9个地质变量在8个事件中的灵敏度分析，初步确认出3个灵敏地质物征。此项研究对中国目前高放废物处置库选址工作有一定的指导意义。     

Modelling of uranium and neptunium chemistry in a deep rock environment

According to the present concept for final storage of spent nuclear fuel in Sweden, the spent fuel, encapsulated in copper or copper/steel canisters, will be placed in tunnels in a deep rock formation. The canisters will be surrounded by compacted bentonite clay acting as a buffer material. In connection with a safety analysis of such a storage facility, the total solubility of certain elements (e.g., uranium) as well as the transport properties (e.g., retardation due to sorption on mineral surfaces) of the long-lived radionuclides released from the canister have to be predicted or measured. The chemical conditions, governing the solubility and speciation of trace elements encountered in and around the repository depend on interactions between the ground water and the engineering materials in the repository and a production of oxidants due to radiolysis in the spent fuel. In the present study the speciation and solubility of uranium and neptunium in a bentonite-ground water system and in ground waters with compositions measured at a site at äspö, SE Sweden, have been calculated. The calculations have been carried out using a recent version of the geochemical computer code PHREEQE and the database HATCHES 5.0. Predictions of the uranium and neptunium concentrations in the ground water in the vicinity of a damaged high level waste repository have also been performed. The uranium concentration in the water in the bentonite barrier is predicted to be of the same order of magnitude or lower than that found in some granitic ground waters. For neptunium the calculations are uncertain due to the small amount of experimentally determined thermodynamic data and few verifications under the conditions (pH - Eh - carbonate concentration) considered. The predicted concentrations (ca 10^–12 m, corresponds to ca 0.006 Bq/l) may be regarded as high, considering the high toxicity of neptunium and its long half-life.     

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。     

我国高放废物地质处置库场址筛选总体技术思路探讨

综合对比瑞典、加拿大、芬兰和美国等国高放废物地质处置库场址筛选技术思路,分析国外高放废物地质处置库场址筛选过程中取得的经验、教训,总结了我国处置库选址工作取得的成果和存在的问题。在综合研究基础上,分析提出我国高放废物地质处置库场址筛选总体技术思路,包括应遵循的原则、工作范围、目标和总体技术步骤等,以利于今后处置库选址工作更系统、规范和统一。     

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。     

Understanding groundwater chemistry using mixing models

For the last 15 a, SKB (the Swedish Nuclear Fuel and Waste Management Company) has been using the Äspö Hard Rock Laboratory (HRL) as the main test site for the development of suitable tools and methods for the final disposal of spent nuclear fuel. Major achievements have been made in the development of a new groundwater modelling technique. The technique described in this paper is used within the ongoing site investigations of Forsmark and Simpevarp in Sweden.     

高放废物地质处置库预选缓冲材料压缩性能研究

缓冲材料是高放废物深地质处置多重屏障系统中非常重要的一道人工屏障，内蒙古高庙子钠基膨润土被确定为我国高放废物深地质处置缓冲材料的首选基料。通过研究该钠基膨润土（GMZ01）在不同含水量条件下的压实成型性、不同压实干密度和不同含水量压实样品的无侧限压缩性能，认为：含水量为15％的高庙子天然钠基膨润土压实成型性最好，压实干密度越大，无侧限抗压强度越大；在无侧限压缩实验时，含水量为15％的高密度压实膨润土样品比含水量为10％和20％的样品的抗压强度大，变形小。