Corrosion techniques and strategies for used fuel containers with copper corrosion barriers under deep geological disposal conditions:A review

Safe emplacement of high-level nuclear waste(HLNW)arising from the utilization of nuclear power is a frequently en-countered and considerably challenging issue.The widely accepted and feasible approach for the permanent disposal of HLNW involves housing it in a corrosion-resistant container and subsequently burying it deep in a geologic repository.The focus lies on ensuring the dur-ability and integrity of the container in this process.This review introduces various techniques and strategies employed in controlling the corrosion of used fuel containers(UFCs)using copper(Cu)as corrosion barrier in the context of deep geological disposal.Overall,these corrosion prevention techniques and methods have been effectively implemented and employed to successfully mitigate the corrosion challenges encountered during the permanent disposal of Cu containers(e.g.,corrosion mechanisms and corrosion parameters)in deep geologic repositories.The primary objective of this review is to provide an extensive examination of the alteration in the corrosion envir-onment encountered by the UFCs when subjected to deep geologic repository conditions and focusing on addressing the potential corro-sion scenarios.

Active source seismic imaging on near-surface granite body:case study of siting a geological disposal repository for high-level radioactive nuclear waste

In order to research whether it is suitable to set a geological disposal repository for high-level radioactive nuclear waste into one target granite body,two active source seismic profles were arranged near a small town named Tamusu,Western China.The study area is with complex surface conditions,thus the seismic exploration encountered a variettraveltimey of technical difculties such as crossing obstacles,de-noising harmful scattered waves,and building complex near-surface velocity models.In order to address those problems,techniques including cross-obstacle seismic geometry design,angle-domain harmful scattered noise removal,and an acoustic wave equation-based inversion method jointly utilizing both the and waveform of frst arrival waves were adopted.The fnal seismic images clearly exhibit the target rock’s unconformable contact boundary and its top interface beneath the sedimentary and weathered layers.On this basis,it could be confrmed that the target rock is not thin or has been transported by geological process from somewhere else,but a native and massive rock.There are a few small size fractures whose space distribution could be revealed by seismic images within the rock.The fractures should be kept away.Based on current research,it could be considered that active source seismic exploration is demanded during the sitting process of the geological disposal repository for nuclear waste.The seismic acquisition and processing techniques proposed in the present paper would ofer a good reference value for similar researches in the future.

The Beishan underground research laboratory for geological disposal of high-level radioactive waste in China:Planning, site selection,site characterization and in situ tests

With the rapid development of nuclear power in China, the disposal of high-level radioactive waste（HLW） has become an important issue for nuclear safety and environmental protection. Deep geological disposal is internationally accepted as a feasible and safe way to dispose of HLW, and underground research laboratories（URLs） play an important and multi-faceted role in the development of HLW repositories. This paper introduces the overall planning and the latest progress for China＇s URL. On the basis of the proposed strategy to build an area-specific URL in combination with a comprehensive evaluation of the site selection results obtained during the last 33 years, the Xinchang site in the Beishan area,located in Gansu Province of northwestern China, has been selected as the final site for China＇s first URL built in granite. In the process of characterizing the Xinchang URL site, a series of investigations,including borehole drilling,geological mapping, geophysical surveying,hydraulic testing and in situ stress measurements, has been conducted. The investigation results indicate that the geological,hydrogeological, engineering geological and geochemical conditions of the Xinchang site are very suitable for URL construction. Meanwhile, to validate and develop construction technologies for the Beishan URL, the Beishan exploration tunnel（BET）, which is a 50-m-deep facility in the Jiujing sub-area, has been constructed and several in situ tests, such as drill-and-blast tests, characterization of the excavation damaged zone（EDZ）, and long-term deformation monitoring of surrounding rocks, have been performed in the BET. The methodologies and technologies established in the BET will serve for URL construction.According to the achievements of the characterization of the URL site, a preliminary design of the URL with a maximum depth of 560 m is proposed and necessary in situ tests in the URL are planned.

On area-specific underground research laboratory for geological disposal of high-level radioactive waste in China

Underground research laboratories （URLs）, including ＂generic URLs＂ and ＂site-specific URLs＂, are un- derground facilities in which characterisation, testing, technology development, and/or demonstration activities are carried out in support of the development of geological repositories for high-level radioactive waste （HLW） disposal. In addition to the generic URL and site-specific URL, a concept of ＂areaspecific URL＂, or the third type of URL, is proposed in this paper. It is referred to as the facility that is built at a site within an area that is considered as a potential area for HLW repository or built at a place near the future repository site, and may be regarded as a precursor to the development of a repository at the site. It acts as a ＂generic URL＂, but also acts as a ＂site-specific URL＂ to some extent. Considering the current situation in China, the most suitable option is to build an ＂area-specific URL＂ in Beishan area, the first priority region for China＇s high-level waste repository. With this strategy, the goal to build China＇s URL by 2020 mav be achieved, but the time left is limited.

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.

High-level radioactive waste disposal in China: update 2010

For geological disposal of high-level radioactive waste （HLW）, the Chinese policy is that the spent nuclear fuel （SNF） should be reprocessed first, followed by vitrification and final disposal. The preliminary repository concept is a shaft-tunnel model, located in saturated zones in granite, while the final waste form for disposal is vitrified high-level radioactive waste. In 2006, the government published a long-term research and development （R＆D） plan for geological disposal of high-level radioactive waste. The program consists of three steps： （1） laboratory studies and site selection for a HLW repository （2006-2020）; （2） underground in-situ tests （2021-2040）; and （3） repository construction （2041-2050） followed by operation. With the support of China Atomic Energy Authority, comprehensive studies are underway and some progresses are made. The site characterization, including deep borehole drilling, has been performed at the most potential Beishan site in Gansu Province, Northwestern China. The data from geological and hydrogeological investigations, in-situ stress and permeability measurements of rock mass are presented in this paper. Engineered barrier studies are concentrated on the Gaomiaozi bentonite. A mock-up facility, which is used to study the thermo-hydro-mechano-chemical （THMC） properties of the bentonite, is under construction. Several projects on mechanical properties of Beishan granite are also underway. The key scientific challenges faced with HLW disposal are also discussed.

High-Level Nuclear Wastes and the Environment: Analyses of Challenges and Engineering Strategies

The main objective of this paper is to analyze the current status of high-level nuclear waste disposal along with presentation of practical perspectives about the environmental issues involved. Present disposal designs and concepts are analyzed on a scientific basis and modifications to existing designs are proposed from the perspective of environmental safety. A new concept of a chemical heat sink is introduced for the removal of heat emitted due to radioactive decay in the spent nuclear fuel or high-level radioactive waste, and thermal spikes produced by radiation in containment materials. Mainly, UO2 and metallic U are used as fuels in nuclear reactors. Spent nuclear fuel contains fission products and transuranium elements which would remain radioactive for 104 to 108years. Essential concepts and engineering strategies for spent nuclear fuel disposal are described. Conceptual designs are described and discussed considering the long-term radiation and thermal activity of spent nuclear fuel. Notions of physical and chemical barriers to contain nuclear waste are highlighted. A timeframe for nuclear waste disposal is proposed and time-line nuclear waste disposal plan or policy is described and discussed.

Current status of the geological disposal programme and an overview of the safety case at the pre-siting stage in Japan

In Japan,high-level radioactive waste and specific low-level radioactive waste which includes long-lived radionuclides are planned to be disposed of in the geological formations at depths greater than 300 m.The disposal site will be selected through a stepwise site investigation process that consists of a Literature Survey,Preliminary Investigation,and Detailed Investigation phases.In October 2020 a Literature Survey was launched in Japan at two municipalities in Hokkaido for the first time since NUMO initiated a nationwide call for volunteer municipalities in 2002,and the outcomes are currently being compiled.To enhance the public’s understanding of how to implement safe geological disposal in Japan based on the latest scientific knowledge and technology,NUMO,as the implementing organisation,developed and published a safety case for geological disposal at the pre-siting stage.This safety case provides multiple lines of arguments and evidence to demonstrate the feasibility of the geological disposal and a basic structure for a safety case that will be applicable to any potential sites in Japan.The safety case also presented some R&D challenges to enhance the technical confidence of the project,including the R&D topics related to rock mechanics.This report presents the current status of the geological disposal programme in Japan,together with the status of the Literature Survey phase and an overview of the NUMO safety case.

基于离散裂隙网络模型的地下水流并行模拟方法

裂隙水表现为强烈的非均匀性和各向异性,而离散裂隙网络模拟方法是目前国际上公认描述裂隙水流动规律最为合理、有效的方法之一。以我国高放废物地质处置地下实验室花岗岩场址为研究对象,借助高性能数值计算服务器集群及并行程序,提出了场址岩体离散裂隙网络渗流并行模拟方法。结果表明,该方法可实现千万级别模型网络单元离散裂隙网络渗流精细化模拟,提升了程序处理复杂问题的计算效率及能力;建立了离散裂隙网络模型结构优化与实际情景条件下边界参数赋值方法,保障了场址水文地质评价过程中不同尺度模型水位信息的有效传递;模拟区域地下水位沿着裂隙呈网状结构分布,呈现从南向北流动的趋势,连通裂隙间的水位呈现从高到低的连续变化,非连通裂隙的水位是非连续的;地下水是沿着导水裂隙流动,裂隙网络的连通性及渗透性对地下水流动特性影响明显。离散裂隙网络渗流并行数值模拟可以更为精细反映裂隙地下水动力场特征,进一步提升裂隙介质渗流模拟预测能力,这对深化裂隙水流动规律的认识具有重要意义。

基于逆康普顿散射源核废物成像技术的研究进展及仿真模拟

高放射性水平废物具有放射性核素浓度高、毒性大、持续释放衰变热和衰变时间长等特性,使其处置的难度和风险极高。核废物的精准检测和评估对深地质处置的安全有着重要意义。以核共振荧光方法与三维透射成像相结合的核废物检测方法近年来开始逐步发展并被认为是最有潜力的发展方向。紧凑型逆康普顿散射X/γ射线源是核共振荧光技术应用的核心装置,能够满足工程现场应用和精准无损检测的需求。介绍了国内这类先进辐射源的发展应用情况和相关研究现状。基于紧凑型伽马射线源装置,结合蒙特卡洛模拟,揭示了核废物、废物罐及其外围膨润土的响应机制,实现了对交界区域的成像分析。相关表征数据可作为输入参数,提高屏蔽材料多场耦合的数值模拟精度,预测关键放射性核素的迁移规律,评价屏障系统的可靠性和核废物的泄露风险,为核废物深地质处置的核素识别、检测和安全评估提供有效的技术支撑。

基于离散元法的高放核废料储罐静动力稳定性初步研究

核废料储罐是核废料处理工程屏障的核心部分,其静动力学稳定性至关重要。基于碳化硅材料的核废料储罐,考虑深部岩石—储罐的相互作用特点,采用试验与模拟相结合的方法开展研究。首先对碳化硅的抗拉强度特征进行了研究,分析了深埋条件下的储罐受力特点和规律;其次,研究了自由落体与岩石撞击条件下储罐的动态受力规律和基本破坏形式,并考虑岩石破碎所带来的影响。结果显示:碳化硅是相对脆性材料,其抗拉强度存在一定变化区间;在深埋条件下,埋深、水平与竖向地应力比对储罐受力有较大的影响;运输时自由跌落的高度和倾角对储罐局部集中拉应力有较大的影响;岩石撞击时储罐内的拉应力受岩石质量和撞击发生时岩石—储罐接触类型的控制,考虑岩石撞击破碎会大幅削弱撞击附加应力,岩块间黏聚力和内摩擦角越大,岩石撞击力也越大,岩块间抗拉强度对撞击力的影响相对较小。虽然在自由跌落与岩石撞击的工况下会发生局部破坏,但通过外附一定厚度缓冲层并合理安置,可保证储罐的静动力稳定性。

高放废物深地质处置及其研究概况

简要介绍了高放废物深地质处置的概念及其关键技术问题、高放废物工程屏障及其研究概况、高放废物处置库的选址因素及选址过程、处置库的主要岩石力学问题与候选主岩、地下实验室核素迁移示踪研究概况,最后,简要介绍了美、法、俄、韩、中等国在高放废物处置方面的研究计划与进展。

高分辨率声波钻孔电视及其在核废物地质处置深部岩体研究中的应用

声波钻孔电视测量是最早能获得钻孔直观图像的地球物理测井方法,新一代声波钻孔电视探头采用了先进的声波束聚焦技术、数字记录技术和数字化数据处理技术,具有精度高、分辨率高和测井速度快等特点。在高放废物深地质处置库场址预选和场址评价研究中,深部岩体的节理裂隙特征参数是场址性能评价的基础数据之一。利用高分辨率声波钻孔电视测井技术,可获得钻孔孔壁直观图像和孔壁各点的三维磁坐标和倾斜坐标参数。利用这些参数,计算钻孔的偏移量、进行钻孔裂隙统计分析、岩芯定向排列和评价局部范围内深部岩体节理裂隙和断裂构造的延伸特征等。声波钻孔电视是一种方便、快捷、精度高的深部岩体裂隙测量工具。

盐岩矿床内油气储备和核废料处置

在对盐岩矿床内油气储备和核废料处置现状分析研究的基础上,提出了在盐岩矿床内进行储库建造应重点解决的储库长期稳定性,储库结构及建造等的研究问题及解决方法,对我国盐岩矿床内建造油气储库和核废料处置具有重要的指导意义。

黏土岩水力耦合特性试验研究

对于高放废物地质处置工程,地质屏障系统是放射性有害物质进入环境的最后一道屏障,也是一条重要防线。黏土岩由于其低渗透性、渗透损伤自修复以及较强的吸附能力等特性,被认为是一种合理的高放废物处置地质屏障。结合比利时正开展的黏土岩高放废物地质处置相关研究课题,通过一系列室内试验研究黏土岩的水力耦合机制及长期蠕变特性。三轴压缩试验表明,黏土岩压缩强度、超孔隙水压力与围压正相关。渗透试验表明,黏土岩渗透性呈现显著的各向异性特征,围压增大使黏土岩渗透性显著降低。蠕变试验表明,黏土岩蠕变变形、蠕变变形速率与载荷密切相关,即:载荷越大,黏土岩蠕变变形越显著,蠕变变形速率达到稳定所需的时间越长,且相应的稳态蠕变速率越大;根据应力阈值和等时曲线法初步确定该黏土岩长期强度在1.0~1.2 MPa。研究结果将为我国未来黏土岩高放废物处置库的选址和安全性评估提供重要科学依据。

核废料地下处置过程中相关动力学问题及控制措施

深地层地下处置是目前首选的核废料处置方案。由于放射性核素的长期的衰变和辐射导致的某些不可预见性因素,综合评估和预测核废料处置场的安全性是至关重要的。本文从理论上分析了核废料地下处置过程中温度场、应力场、渗流场三场相互影响、相互作用的力学机理,并提出了核废料泄漏的防治措施,为核废料地下处置过程中环境评价提供了基础理论依据。

由工程事故反思论及“生态地质工程学”

在全球气候变暖、异常天气频发、全球性自然灾害严重和日益加剧的形势下,我国众多水电、核电等大工程快速上马的同时,也面临着生态环境影响、安全运营风险管理等诸多问题和挑战。这是一个极需深入思考、有待联合攻关解决的重大课题。需要从全国乃至全球角度出发,全方位、多层次、多学科,而不仅局限在某一部门或行业内,进行反复论证,以实现工程—经济—社会—环境—能源和资源复杂巨系统的和谐调控和可持续发展。在对众多地质工程事故及其有关灾害反思基础上,作者认为有必要从全球变化和可持续发展角度,系统总结以往工程失败或事故教训,建立交叉学科"生态地质工程学",推动复杂巨系统的理论研究和工程应用。这样才能超出单纯工程选址安全性和岩土体稳定性评价的狭隘工程安全理念,更好地实现工程建设—生态环境保护—经济可持续发展的长远目标。

考虑溶质浓度影响的热-水-应力-迁移耦合模型及数值模拟

高放射性核废料地质处置库围岩中地下水的密度因溶质浓度不同而发生变化,这将影响到饱和-非饱和孔隙介质中近场和远场的热-水-应力耦合过程,同时温度场、应力场也要对地下水中的核素及矿物质迁移产生作用。考虑这两个因素,建立和引入了相关的应力平衡方程、水连续性方程、能量守恒方程和渗透迁移方程,并研制出了对应分析孔隙介质中热-水-应力-迁移耦合问题的二维有限元程序。通过对一个假定的核废料地下处置库在核素泄漏后多场耦合过程的数值计算,考察了近场围岩中的温度、应力、孔隙水压力、核素浓度的分布及随时间的变化。结果初步显示了所建模型及程序可模拟热-水-应力-迁移耦合现象,因而具有一定的实用性。

核废物地质处置中热-水-应力耦合对迁移影响的三维有限元模拟

将所建立的热-水-应力-迁移耦合模型及开发的有限元程序,由二维分析拓展到三维分析,并从方法论研究的角度,以一个简单的核废物地质处置模型为算例,进行热-水-应力-迁移耦合过程的三维数值模拟,考察了近场的温度、饱和度、核素浓度、孔隙水压力、位移、正应力、流速等的分布与变化,认为计算结果符合规律,得出了若干结论:为了精确地模拟放射性核素迁移,就必须将温度场、渗流场、应力场和核素浓度场进行耦合分析;核废物埋存若干年后将在处置孔壁附近产生较高的压应力;缓冲层内各点的核素浓度达到相对稳定的时间要比温度和饱和度达到相对稳定的时间长得多。

化学种态分析软件CHEMSPEC最新进展

我国高放废物地质处置研发工作已经步入建造地下实验室阶段。地下实验室建造安全评价和未来的处置库性能评价中均需要关键放射性核素在相应深部地质条件下的扩散和迁移参数,而关键核素的扩散和迁移参数与核素在相应水岩体系中的化学种态密切相关。为满足我国核设施退役治理工作的需要,尤其是我国高放废物地质处置相关安全评价的需要,北京大学核环境化学课题组于2008年开始编写具有完全著作权的化学种态分析软件CHEMSPEC。经过多次修改和完善,目前已经具备了较好的计算功能。本文介绍该软件在表面配合模型、数据库补充和程序优化方面的最新进展,以实例形式介绍该软件的新性能,以期为我国相关实验研究者使用该软件提供参考。