高放废物地质处置系统核素迁移模型研究

高放废物地质处置系统核素迁移研究是高放废物安全处理和处置的重要内容.从整个系统的角度出发,把高放废物地质处置系统核素迁移过程分为三种模式:工程屏障中的释放-扩散模型;地质屏障中的对流-弥散模型和在生物圈中的分区传递模型.在分区传递模型中利用转移系数描述核素在各分区之间的迁移.通过对每种模型核素迁移机理的分析得出概化模型,并给出了相应的数学描述.     

高放废物深地质处置地下水流数值模拟方法研究进展

地下水流数值模型不仅是认识深部水动力场形成演化机制的有效工具,也是建立核素迁移数值模型的基础,因而是高放废物处置场选址和安全评价中重要的技术手段。高放废物深地质处置地下水流数值模拟方法较多,如何选择适当的方法也是值得关注的问题。针对高放废物深地质处置地下水流数值模拟技术展开研究,通过阅读大量国内外文献,文章系统阐述了目前常用的4 类地下水流数值模拟方法的研究进展、适用条件和实例应用;综述了深地质处置中常用的模型不确定性分析方法及研究成果,列表给出了适用于放射性废物地质处置的地下水流数值模拟软件及其在废物处置选择和安全评价中的应用。研究结果表明:等效连续介质模型适用于大区域、长序列、裂隙发育程度较高或较均匀的地区,该类模型方法成熟、所需的数据和参数易于获得,但是不能精确刻画裂隙介质中地下水的流动特征。离散裂隙网络模型适合解决处置场地、储罐尺度等需要精细刻画的地下水流问题,但由于需要大量裂隙及其连通性数据、相关参数等,该方法存在着工作量大、耗时多的缺点。双重介质模型主要用于解决区域尺度裂隙水流问题,但并不能表现出裂隙介质的各向异性、不连续性等特征,因而适用范围存在一定的限制。等效-离散耦合模型可以通过区域分解法对裂隙密度大的区域采用等效连续介质模型,对于裂隙密度较小的地区采用离散裂隙网络模型,从而更符合一般地质条件下裂隙渗流的特征,但也存在交换量难以确定、模型耦合技术问题。通过灵敏度分析,将不同敏感因子对模型敏感指标的影响程度进行排序,提高模型精度、减少参数不确定性分析的工作量。蒙特卡罗法是目前常用的一种模型不确定性方法,原理简单、易于实现。文章展望了数值模型在仿真性、不确定性分析、预测和多介质耦合等方面的研究前景。     

高放废物深地质处置地下水数值模拟应用综述

开展地下水数值模拟研究是高放废物处置场地安全评价的重要组成部分,然而深地质处置介质类型的复杂性、基岩深部资料的相对匮乏性导致模拟结果存在不确定性,如何刻画深部地下水动力场并评估可能引起的风险已成为高放废物处置安全评价中重点关注的问题。在大量文献调研的基础上,综述了世界典型国家高放废物深地质处置场地的地下水数值模拟与不确定性分析应用,并归纳总结该领域研究经验,得到以下认识：（1）深地质处置场深部构造、裂隙的发育与展布决定了地下水循环条件,探究适用于基岩裂隙地区新的水文地质试验方法是提高地下水数值模型仿真性的基础;（2）不同尺度模型融合是解决深地质处置地下水模拟的有效技术方法,区域尺度多采用等效连续介质法,场地尺度使用等效连续多孔介质和离散裂隙网络耦合模型,处置库尺度使用离散裂隙网络方法,其次需重点关注未来大时间尺度下放射性核素在地质体中的迁移转化规律,模拟预测场址区域地下水环境长期循环演变对核素迁移的潜在影响;（3）考虑到不同的处置层主岩岩性以及在多介质中发生的THMC（温度场—渗流场—应力场—化学场）过程,目前国内外常用的地下水模拟软件有：Porflow、Modflow、GMS及MT3DMS等用于模拟孔隙或等效连续介质,Connectflow、Feflow及FracMan等用于模拟地下水和核素在结晶岩、花岗岩等裂隙中的迁移,TOUGH系列软件主要应用于双重介质的水流、溶质及热运移模拟;（4）指导开展有针对性的模型和参数的不确定性分析工作,减少投入工作量,提高模型精度,并可针对处置库长期演变、废物罐失效、极端降雨等多情景预测模拟,为处置库安全评价及设计提供基础数据支撑;（5）针对我国深地质处置地下水数值模拟研究现状,下一步应加强区域地质、水文地质、裂隙测量以及现场试验等相关的调查及监测工作,多介质耦合、多场耦合模拟及不确定性分析研究将会是未来的研究重点。     

高放废物地质处置元数据设计与编辑模块开发

在对元数据的含义、作用、组成及对高放领域研究的数据内容和特点分析的基础上,对元数据编辑模块的设计进行了详细描述,并在VS2005平台下应用C#语言进行了模块的实际开发,最终实现了便于进行数据共享的XML格式存储功能。元数据编辑模块的应用将促进我国高放废物地质处置信息化工作的进一步深入。     

Study on the residence time of deep groundwater for high-level radioactive waste geological disposal

Residence time of deep groundwater is one of the most important parameters in safety and performance assessment for high-level radioactive waste geological disposal. In this study, we collected the deep groundwater samples of Jijicao in Gansu Beishan pre-selected region. The deep groundwater residence time at two depths estimated by Helium-4 accumulation method were 3.8 ka and 5.0 ka respectively upon measurement and calculation, which indicates that the deep groundwater is not derived from the deep crust circulation process. Hence, deep groundwater is featured with long residence time as well as slow circulation and update rate, and such features are conductive to the safe disposal of high-level radioactive waste.     

高放废物地质处置新场岩体三维地质模型构建与应用

我国高放废物地质处置经过30多年研究,已初步确定新场为地下实验室推荐场址。开展新场岩体三维地质建模研究,一方面能够充分利用已有资料准确地表达各种地质现象,直观再现地质单元的空间展布及其相互关系;另一方面可以挖掘隐含的地质信息,方便地质分析和工程决策,这在地下实验室研究阶段非常重要。在对新场已有资料综合分析和解译的基础上,建立了岩体的三维地质模型,直观地再现了新场岩体地质环境特征;并基于地质建模结果,开展了钻孔设计等工程应用,取得了较好的效果。本研究可为我国高放废物地质处置后续工作中地质分析与工程设计提供有益参考和技术支持。     

Thermal impact of waste emplacement and surface cooling associated with geologic disposal of high-level nuclear waste

This article is a study of the thermal effects associated with the emplacement of aged radioactive high-level wastes in a geologic repository, with emphasis on the following subjects: waste characteristics, repository structure, and rock properties controlling the thermally induced effects; thermal, thermomechanical, and thermohydrologic impacts, determined mainly on the basis of previous studies that assume 10-yr-old wastes; thermal criteria used to determine the repository waste loading densities; and technical advantages and disadvantages of surface cooling of the wastes prior to disposal as a means of mitigating the thermal impacts. Waste loading densities determined by repository designs for 10-yr-old wastes are extended to older wastes using the near-field thermomechanical criteria based on room stability considerations. Also discussed are the effects of long surface cooling periods determined on the basis of far-field thermomechanical and thermohydrologic considerations. Extension of the surface cooling period from 10 yr to longer periods can lower the near-field thermal impact but have only modest long-term effects for spent fuel. More significant long-term effects can be achieved by surface cooling of reprocessed high-level waste.     

高放射性核废物地质处置库场址预选和矿产资源勘查的关系

据1999-2007年资料的不完全统计,甘肃省地勘部门在北山地区一共投入4488.2万元人民币,矿产资源潜在价值估计为13.28亿元.一旦把甘肃省北山列为高放废物处置库的预选区,则潜在的经济损失将会很大,还可能影响西北地区的土地利用程度和经济发展.核试验场有多种围岩可供处置库地质选址选择,而且远离国境线与居民区,有利于高放废物处置库的安全管理.结合中国国情,在地质和社会务件有利的核试验军事禁区开展国家高放废物处置库的预选场址工作有独特的优势.提出了尽快在中国核试验场址开展高放废物地质处置库场址预选工作的建议.     

高放射性核废物地质处置库场址预选和矿产资源勘查的关系

据1999—2007年资料的不完全统计,甘肃省地勘部门在北山地区一共投入4488.2万元人民币,矿产资源潜在价值估计为13.28亿元。一旦把甘肃省北山列为高放废物处置库的预选区,则潜在的经济损失将会很大,还可能影响西北地区的土地利用程度和经济发展。核试验场有多种围岩可供处置库地质选址选择,而且远离国境线与居民区,有利于高放废物处置库的安全管理。结合中国国情,在地质和社会条件有利的核试验军事禁区开展国家高放废物处置库的预选场址工作有独特的优势。提出了尽快在中国核试验场址开展高放废物地质处置库场址预选工作的建议。     

高放射性核废物地质处置库场址预选和矿产资源勘查的关系

据1999—2007年资料的不完全统计,甘肃省地勘部门在北山地区一共投入4488.2万元人民币,矿产资源潜在价值估计为13.28亿元。一旦把甘肃省北山列为高放废物处置库的预选区,则潜在的经济损失将会很大,还可能影响西北地区的土地利用程度和经济发展。核试验场有多种围岩可供处置库地质选址选择,而且远离国境线与居民区,有利于高放废物处置库的安全管理。结合中国国情,在地质和社会条件有利的核试验军事禁区开展国家高放废物处置库的预选场址工作有独特的优势。提出了尽快在中国核试验场址开展高放废物地质处置库场址预选工作的建议。     

Lead isotope evidence for recent uranium mobility in geological formations of Brazil: implications for radioactive waste disposal

Lead–lead isotope data from whole rock samples are used to investigate the recent (last few million years) mobility of U and Th. The method is based on the comparison of the calculated present day U and Th concentrations required to yield the Pb isotope composition in the samples with the actual present day concentrations of U and Th obtained by direct measurement. The geological formations studied include the Neoproterozoic carbonate sediments of the Bambuı́ Group, Archean/Paleoproterozoic granite–greenstone terrain of the Contendas–Mirante Complex and a Proterozoic ortho-gneisses hosting U deposit in Lagoa Real. All these formations are in the São Francisco Craton, Brazil. The data show high U mobility in the carbonate sediments and in the deformed ortho-gneisses set in a ductile shear zone. Infiltration of groundwater through fault zones seems to have facilitated the U mobility. The Pb isotope approach is a useful technique complementing U-series disequilibrium studies and may be included for site characterization studies for radioactive waste disposal.     

MapGIS在东天山高放废物地质处置库选址中的应用

根据高放废物选址的要求,利用MapGIS对东天山地区不同时代岩体的空间位置、分布形态、出露面积,以及岩体与断裂构造、地震和矿床点等的空间关系进行了研究,对海量资料信息进行分析处理,可起到事倍功半的效果。利用MapGIS分析结果,初步筛选出阿奇山1号岩体、雅满苏北岩体作为高放废物地质处置库选址的有利岩体。     

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。     

Reversed mining and reversed-reversed mining: the irrational context of geological disposal of nuclear waste

Man does not only extract material from the Earth but increasingly uses the underground for storage and disposal purposes. One of the materials that might be disposed of this way is high-level nuclear waste. The development of safe disposal procedures, the choice of suitable host rocks, and the design of underground facilities have taken much time and money, but commissions in several countries have presented reports showing that — and how — safe geological disposal will be possible in such a way that definite isolation from the biosphere is achieved. Political views have changed in the past few years, however, and there is a strong tendency now to require that the high-level waste disposed of will be retrievable. Considering the underlying arguments for isolation from the biosphere, and also considering waste policy in general, this provides an irrational context. The development of new procedures and the design of new disposal facilities that allow retrieval will take much time again. A consequence may be that the high-active, heat-generating nuclear waste will be stored temporarily for a much longer time than objectively desirable. The delay in disposal and the counterproductive requirement of retrievability are partly due to the fact that earth-science organisations have failed to communicate in the way they should, possibly fearing public (and financial) reactions if taking a position that is (was?) considered as politically incorrect. Such an attitude should not be maintained in modern society, which has the right to be informed reliably by the scientific community.     

高放废物地质处置阿拉善预选区巴彦诺日公地段目标深度岩体质量预测

高放废物地质处置阿拉善预选区巴彦诺日公地段位于阿拉善地块东部,主要由二叠纪侵入的花岗岩构成,地壳次稳定。通过踏勘,确定了2个钻孔,布置了若干条物探剖面。以这2个钻孔为中心,在17km×17km范围内进行了工程地质测绘,获得了地表结构面分布特征。地表岩体质量以III级岩体为主,地表以下3m~4m处多为I级和II级岩体。根据钻孔岩芯编录和力学试验数据,对岩芯质量进行评价,岩芯整体质量较好,以Ⅰ级和Ⅱ级岩体为主。对比岩体质量和测井数据,发现岩体质量与岩体的物理参数具有明显的相关性。通过和CSAMT剖面上对应位置的对比,建立了岩体质量与电阻率的关系。结合地表岩体质量、钻孔岩芯质量和物探剖面,对目标深度岩体进行了预测：目标深度（600m深左右）岩体质量以Ⅰ级岩体为主,局部有Ⅱ级岩体和Ⅲ岩体。     

高放废物地质处置的岩体深部结构面特征研究——以甘肃北山高放废物地质处置地下实验室工程为例

岩体深部结构面是岩体工程质量评价、三维地质建模、钻孔水文地质试验和地下实验室工程设计等研究的重要影响因素.甘肃北山新场花岗岩地段已被确定为中国高放废物地质处置地下实验室的推荐场址.基于超声波钻孔电视技术和其他地质资料对场址岩体深部结构面特征开展研究,结果表明:场址内花岗岩体具有很好的完整性,有利于地下实验室的工程建造.场址周边断裂构造纵向延伸范围有限,断裂带规模和横向影响范围随深度增加而逐渐减小.结构面产状特征与区域构造特征相一致,为区域构造特征研究提供了佐证.研究成果为地下实验室工程的开挖设计提供了重要参考依据,并为区域基础地质研究提供参考资料.     

2000-2040年我国高放废物深部地质处置初探

本简要介绍了国内外高放废物地质处置研究概况，探讨了我国高放废物地质处置研究阶段的划分，各阶段的研究目标，任务和研究内容以及各研究阶段的大致时间安排，提出了我国高放废物地质处置研究在2000－2040年的远景规划设想。     

Rock alteration in alkaline cement waters over 15 years and its relevance to the geological disposal of nuclear waste

The interaction of groundwater with cement in a geological disposal facility (GDF) for intermediate level radioactive waste will produce a high pH leachate plume. Such a plume may alter the physical and chemical properties of the GDF host rock. However, the geochemical and mineralogical processes which may occur in such systems over timescales relevant for geological disposal remain unclear. This study has extended the timescale for laboratory experiments and shown that, after 15 years two distinct phases of reaction may occur during alteration of a dolomite-rich rock at high pH. In these experiments the dissolution of primary silicate minerals and the formation of secondary calcium silicate hydrate (C–S–H) phases containing varying amounts of aluminium and potassium (C–(A)–(K)–S–H) during the early stages of reaction (up to 15 months) have been superseded as the systems have evolved. After 15 years significant dedolomitisation (MgCa(CO₃)₂ + 2OH⁻ → Mg(OH)₂ + CaCO₃ + CO₃²⁻_(aq)) has led to the formation of magnesium silicates, such as saponite and talc, containing variable amounts of aluminium and potassium (Mg–(Al)–(K)–silicates), and calcite at the expense of the early-formed C–(A)–(K)–S–H phases. This occured in high pH solutions representative of two different periods of cement leachate evolution with little difference in the alteration processes in either a KOH and NaOH or a Ca(OH)₂ dominated solution but a greater extent of alteration in the higher pH KOH/NaOH leachate. The high pH alteration of the rock over 15 years also increased the rock’s sorption capacity for U(VI). The results of this study provide a detailed insight into the longer term reactions occurring during the interaction of cement leachate and dolomite-rich rock in the geosphere. These processes have the potential to impact on radionuclide transport from a geodisposal facility and are therefore important in underpinning any safety case for geological disposal.