高放废物处置库花岗岩热-力耦合模拟研究

根据典型高放废物处置库概念模型,应用FLAC3D有限差分程序模拟计算了数百年内热-力耦合(TM)条件下高放废物地质处置库围岩的温度场、应力场和变形场的变化特征,初步得到在一定废物罐热源强度及衰变函数条件下花岗岩体的热力学特征及处置巷道工程设计的合理间距.模拟结果表明:在-500 m水平建造处置库,按设定的释热强度,处置坑合理间距为8～12 m,废物罐表面温度为130 ℃,处置坑中线岩体最高温度为40 ℃,并保持数百年左右.     

我国高放废物深钻孔处置热学分析

深部钻探技术的发展使得高放废物深钻孔处置逐渐再次受到国际上的广泛关注。针对我国高放废物深钻孔处置概念设计,采用ANSYS软件建立了深钻孔处置热学计算模型,对处置后高放废物罐及其周边围岩温度场演变规律进行分析。结果表明:1)高放废物罐进行深钻孔处置后,其表面温度在几年内达到峰值;2)废物罐暂存时间对处置区达到峰值温度的时间和峰值温度大小有重要影响,为控制处置区峰值温度,延长废物罐暂存时间是可行的;3)围岩温度升高速度与其距废物罐的距离成负相关关系,距废物罐越远,温度升高速度越慢。     

基于损伤预测的粘土围岩深地质处置库硐距分析

粘土岩作为我国高放废物深地质处置库建设的预选围岩类型之一,其地下处置库硐距的优化对处置库的设计施工及核素迁移安全具有重大意义。本文基于塔木素粘土岩高放废物深地质处置预选地区天然地应力现场测量及室内岩石力学试验结果,采用弹性力学柯西问题理论分析与有限差分数值模拟相结合的方法,对处置库硐室开挖过程形成的损伤区范围进行预测。通过对比单硐与双硐开挖时不同硐室间距下开挖所形成的损伤区影响范围,来进行处置库硐距的优化,通过对比不同硐距下开挖损伤区的变化,分析当前应力水平下,硐室开挖后重分布应力随与中间岩柱中心点距离的变化趋势。结果表明,d=8~10 m是粘土围岩高放废物处置库的合理的硐距,此时开挖后的相邻硐室间损伤区没有产生明显交圈效应,当硐距大于10 m后,相邻硐室间的影响将逐渐减小,接近单硐开挖情况。该方案可为粘土岩预选区建造高放废物处置库提供参考依据。     

非饱和花岗岩气体相对渗透率试验研究

围岩气体渗透特性是影响高放废物处置库长期安全性的重要因素。以中国高放废物地质处置首选预选区——甘肃北山预选区的黑云母二长花岗岩为研究对象,开展了不同饱和度条件下的气体渗透率试验研究。首先利用真空饱和法获得了饱和试样,之后在6种不同相对湿度环境下完成了饱和花岗岩失水过程的监测,并测试了不同饱和度条件下的气体渗透率。随后分别在高放废物地质处置工程围岩预设最高温度90 ℃及沸点以上105 ℃条件下完成试样干燥过程,同时测试了干燥条件下的气体渗透率。基于测试结果,计算获得了花岗岩水分特征曲线,并分析了饱和度与气体相对渗透率的对应关系,并提出了数学描述模型。     

缓冲材料热-水-力耦合模型试验研究

高放废物深地质处置采用多重屏障设计体系,缓冲材料是位于废物罐和围岩之间的一道重要的人工屏障。在放射性衰变热、地下水入侵和围岩应力等作用下,缓冲材料经历复杂的热-水-力耦合过程,评价其长期性能对高放废物地质处置库的稳定运行至关重要。缓冲材料模型试验是研究膨润土在多场耦合环境下性能变化的重要途径。中型实验台架是大型实验台架(China-Mock-up)的重要补充,用来模拟与大型实验台架边界相同的环境下,即热量和水分别从缓冲材料的不同侧向另一侧传递和渗透的条件下膨润土的行为特征。通过实时监测缓冲材料在长期加热和加水条件下的温度、相对湿度、力学等特征参数,揭示了在热-水-力耦合条件下缓冲材料的性能变化规律,同时对台架进行了拆解,对拆解样品的含水量、干密度和微观结构等进行了分析测试,研究结果可为高放废物处置库缓冲材料的工程设计提供参数支持。     

高放废物处置中的THM耦合理论及分析

 高放废物处置研究是非常重要和必要的，其处置形式的选择是处置安全的重要因素之一，相应处置结构的物理力学特性研究是决定高放废物处置形式的重要依据。在介绍高放废物处置形式的基础上，提出高放废物处置的相关研究课题，紧接着阐述高放废物处置中THM耦合理论，膨润土的土水特征曲线不仅相关于外部施加应力、蒸汽压力、水压力，而且也相关于温度；在考虑气体在压力作用下的传播、气体在水中的溶解和气体的凝固等影响下，建立气体和液体中的水量守恒方程；在考虑敏感热流和潜热流影响下，建立能量守恒方程；将所有的方程写成有限元和有限差分计算格式；最后编制一维计算程序。计算结果对在花岗岩体中决定高放废物储存洞室之间间距具有借鉴作用。     

新疆阿奇山地段岩体节理特征研究

我国高放废物处置库新疆预选区的阿奇山地段是有利候选地段之一。本次在阿奇山地段进行详细的地质节理调查,以地表露头及采石坑内的节理为主要对象,通过现场节理调查取得节理数据,共测得3680条节理数据。进行节理几何特征的概率分析,对岩体赋存的结构条件进行有效、准确的描述和定量分析,准确地确定岩体节理的分布。由结果可以看出阿奇山地段的岩体节理以陡倾角的剪节理为主,且节理倾向和倾角符合正态分布规律,节理间距用负指数分布规律很好表示,阿奇山地段各区域的节理间距属于宽间距,由此表明此地段岩体完整性较好。本次研究得到阿奇山地段岩体节理基本特征参数,为高放废物深地质处置库的选址、概念库设计以及进行核素迁移规律研究提供翔实的资料。     

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。     

高放废物地质处置库中非饱和缓冲层的热-水-力耦合数值模拟

作为高放废物地质处置库中的缓冲/回填材料,膨润土在核废料放出的热量和周围天然岩体中地下水共同作用下,其热-水-力耦合作用效果对处置库的稳定性、安全性有着极为重要的影响。以非饱和土多场耦合理论为基础,基于ABAQUS有限元分析平台,建立二维轴对称模型,对高放废物地质处置库中膨润土缓冲层的热-水-力耦合过程开展了有限元模拟,给出了处置库近场缓冲层中不同位置的温度、饱和度、竖向应力及位移、孔隙水压力及吸力的分布及变化规律,并重点分析了温度场的影响,通过与已有研究成果的对比,证实了所计算结果的合理性。     

盐溶液中膨润土峰值剪切强度的计算方法

膨润土作为高放废物地质处置库的工程屏障材料,在高放废物储存罐与围岩间起缓冲作用,与地下围岩裂隙水接触,膨润土的剪切强度产生变化,危及核废物处置库缓冲层的安全。因此,计算盐溶液中膨润土的剪切强度对保障核废物处置库缓冲层安全具有十分重要的意义。利用双电层理论,从微观角度定性地解释了盐溶液浓度对膨润土峰值剪切强度影响的机理;根据膨润土在盐溶液中的应力平衡,提出考虑盐溶液的渗透吸力影响的修正有效应力概念,反映盐溶液浓度对膨润土强度的影响;基于膨润土表面的分形模型,导出与渗透吸力对应的修正有效应力的表达式,盐溶液的渗透吸力采用修正的Debye-Hückel公式计算;根据Mohr-Coulomb准则,膨润土在盐溶液中的峰值剪切强度(■)由修正有效应力(p~e)表示为统一线性关系:■。     

Numerical analysis of thermal process in the near field around vertical disposal of high-level radioactive waste简

For deep geological disposal of high-level radioactive waste (HLW) in granite, the temperature on the HLW canisters is commonly designed to be lower than 100 °C. This criterion dictates the dimension of the repository. Based on the concept of HLW disposal in vertical boreholes, thermal process in the near field (host rock and buffer) surrounding HLW canisters has been simulated by using different methods. The results are drawn as follows: (a) the initial heat power of HLW canisters is the most important and sensitive parameter for evolution of temperature field; (b) the thermal properties and variations of the host rock, the engineered buffer, and possible gaps between canister and buffer and host rock are the additional key factors governing the heat transformation; (c) the gaps width and the filling by water or air determine the temperature offsets between them.     

Numerical analysis of thermal process in the near field around vertical disposal of high-level radioactive waste

For deep geological disposal of high-level radioactive waste(HLW)in granite,the temperature on the HLW canisters is commonly designed to be lower than100fiC.This criterion dictates the dimension of the repository.Based on the concept of HLW disposal in vertical boreholes,thermal process in the nearfield(host rock and buffer)surrounding HLW canisters has been simulated by using different methods.The results are drawn as follows:(a)the initial heat power of HLW canisters is the most important and sensitive parameter for evolution of temperaturefield;(b)the thermal properties and variations of the host rock,the engineered buffer,and possible gaps between canister and buffer and host rock are the additional key factors governing the heat transformation;(c)the gaps width and thefilling by water or air determine the temperature offsets between them.     

甘肃北山旧井地段高放废物处置库深度初步探讨

 在对高放废物地下深地质处置库深度确定基本要求的概述基础上，结合甘肃北山旧井地段的地质特征、水文地质特征、岩石力学特征、地应力场特征等方面的情况，分析初始地应力场和二次开挖地应力，对开挖稳定性和发生岩爆的可能性进行计算和预测。研究结果表明，研究区岩体较完整，深度大于400 m时地下水补给匮乏且为还原环境，岩石单轴抗压强度较高，总体质量较好；深度小于700 m地应力为一般应力场，二次开挖稳定性分析和岩爆分析结果表明在此范围内岩爆发生的可能性不大，依据处置库深度确定的基本要求，初步认为旧井地段处置库的设计深度和地下工程布局应在400～700 m范围内进行。     

比利时高放废物处置库设计及与基岩和工程屏障体系的热-水-力性状的相关研究

在比利时，泥岩中地质处置是高放废物最终处置的首选，处置库在高放废物与生物圈之间的多重屏障基础上设计的，而Boom泥岩作为基岩的研究已有20多年历史，1980年比利时做出重大决定，建立名为HADES的地下研究机构，以研究Boom泥岩在地下223m处的力学性质，并调查和论证处置的可行性，为处置库屏障（天然和人工）提供可靠数据，在HADES的众多现场试验中很多试验用来对基岩和工程屏障体系（包括封口和回填的可行性）热-水-力性状进行研究，包括CACTUS，ATLAS，BACCHUS和RESEAL等项目。自1995年以来，研究开发计划向大型和示范性试验方向发展。最主要成果是运用工业技术建立地下研究设施（竖井和井巷）可行性得到了验证，且这种工业技术给研究提供一个较好机会，便于进一步认识基岩泥岩（CLIPEX方案）的水-力性状及了解隧道开挖工程（SELFRAC课题）对挖掘破坏区的影响，另一个重大成果是成功地实现对一种称为“OPHELE”的预掉膨润土（人工屏障材料）加热和水化地面大型试验。下一步工作内容包括实现大尺寸现场加热器试验（PRACLAY试验），此试验预计于2006年开始，并可持续10a之久，据此，首先简要描述比利时高效废物处置库设计，然后回顾Boom泥岩和工程屏障体系的热-水-力性状相关试验，最后介绍下一步大规模PRACLAY试验。     

Influence of heating and water-exposure on the liquid limits of GMZ01 and MX80 bentonites

Bentonite has been considered as a buffer material for embedding canisters with high-level radioactive waste（HLW） in deep geological repositories.GMZ bentonite deposit,located in Xinghe County,Inner Mongolia Autonomous Region,China was proposed as a buffer/backfill material for HLW repository in China.The liquid limits of natural Na-bentonite GMZ01 and commercial Na-bentonite MX80,which are previously heated at 80 ℃ and 95 ℃,respectively,and exposed to water for different times are measured.It is observed that the liquid limit of GMZ01 increases slightly at the beginning,and then decreases as the heating time increases,while the liquid limit of MX80 decreases with the heating time.The liquid limits of both GMZ01 and MX80 decrease with increasing water-exposure time.After the samples are heated at 80℃and 95 ℃ for several months,the mineralogical composition of GMZ01 does not exhibit evident change,whereas MX80 experiences some changes.In addition,the chemical composition,cation exchange capacity（CEC） and exchangeable cation of all the samples do not change significantly.     

Modelling of thermal rock mass properties at the potential sites of a Swedish nuclear waste repository

A repository for spent nuclear fuel will generate heat. For the SKB KBS-3 repository with some 6000 waste canisters positioned at 500 m depth in crystalline rock, the layout together with the thermal properties of the host rock will control the temperature evolution in the near-field and in the far-field. The canister spacing will be determined by thermal design criteria, which place limits on the maximum temperature that can be allowed in the bentonite buffer surrounding the canisters. Since the rock volume available for deposition may be limited, there may also be a need for optimizing the layout of the repository.In this paper the simulation model used to define canister spacing guidelines for SKB's repository layout is presented and discussed. Heat transport properties of the rock are shown to be key factors for the repository layout. It is shown how results from measurements of temperatures at different points in the interior of KBS-3 type deposition holes in the Prototype Repository in Äspö HRL, southern Sweden, are used to find values of buffer and canister heat transport parameters to be used as input in the model. A brief summary of the data and model uncertainties is given.The methodology employed for thermal modelling in the SKB site investigations is presented. Thermal properties are mainly measured in the laboratory or calculated from mineral composition. Both determination methods are applied to small volumes (cm scale), but thermal conductivity values are required at a scale relevant for the canisters. A methodology for upscaling has been established. In order to describe the thermal properties of large volumes of rock the site is divided into a number of rock domains, each with a characteristic geology.     

Design and development of large-scale in-situ PRACLAY heater test and horizontal high-level radioactive waste disposal gallery seal test in Belgian HADES

In Belgium,the Boom clay was selected as a potential host formation for the disposal of high-level radioactive waste（HLW）.To demonstrate the suitability of Boom clay for bearing thermal load induced by the HLW,a large-scale in-situ heater test,called PRACLAY heater test,will be conducted in the underground research laboratory（URL） in Mol.Owing to the limitations of the test（a short period of time compared with that considered in a real repository,different boundary conditions,etc.）,the test is designed to simulate,in a conservative way,the most critical state and phenomena that could occur in the host rock.The PRACLAY gallery was excavated at the end of 2007;the heating phase will begin in 2010 and will last for at least 10 years.The PRACLAY gallery itself leaves an opportunity to study the possibilities of sealing a disposal drift in Boom clay and testing the feasibility of hydraulic cut-off of any preferential pathway to the main access gallery through the excavation damage zone（EDZ） and the lining with a seal in a horizontal drift（horizontal seal）.Indeed,this is a generic problem for all deep geological disposal facilities for HLW.An annular seal made of compacted swelling bentonite will be installed in the front of the heated part of the PRACLAY gallery for these purposes.This paper provides detailed considerations on the thermo-hydro-mechanical（THM） boundary conditions for the design of the PRACLAY heater test and the seal test with the support of numerical calculations.It is believed that these important items considered in the PRACLAY heater test design also constitute key issues for the repository design.The outcome of the PRACLAY heater test will be an important milestone for the Belgian repository design.     

高放废物处置库中COx黏土岩回填材料压缩特性研究

 高放废物处置库中回填材料需要预先压缩到一定密实度,其压缩特性对处置库的设计和安全性有重要影响。目前,粉碎后的Callovo-Oxfodian(COx)黏土岩(法国)被考虑为可选的回填材料之一。通过开展一维压缩试验,研究2种不同粉碎工艺下获得的粗/细COx土样的压缩特性,结果表明：压缩曲线受粒度成分的影响非常明显,为获得同等压实度,细粒土所需的压实功能较粗粒土高,除此之外,细粒土的压缩指数也高于粗粒土,表现出较强的压缩性;随着土样压实密度的增加,粗/细土样的压缩曲线逐渐靠拢,粒度成分对压实功能影响逐渐减弱;土样卸荷时回弹指数随干密度的增加而增加,受粒度成分的影响不明显;高压实(rd = 2.0 g/cm3)粗粒土样在7 MPa的轴向应力下饱和时,体积发生明显的塌陷现象,饱和后土样的压缩指数小于饱和前,而回弹指数则较饱和前高。