考虑细观等效热学参数的高放废物处置库围岩应力−渗流−温度耦合模拟方法

高放废物处置库中乏燃料持续释放的热量对围岩的应力场和渗流场及其长期稳定性具有重要影响。围岩的热学参数依赖于岩石矿物组成、孔隙率和孔隙流体等因素,准确取值是进行高放废物地质处置库多场耦合分析的前提。通过细观力学分析,建立了围岩等效热学参数（热容、热传导系数、热膨胀系数）取值方法,并基于Biot孔隙介质理论,建立应力?温度?渗流三场耦合模型,进而提出了高放废物处置库围岩应力?渗流?温度耦合数值模拟方法。最后通过COMSOL Multiphysics多场耦合软件,利用瑞士Mont Terri高放废物地下试验室围岩温度?渗流?应力多场耦合现场试验数据对数值模拟方法进行验证,并探讨了温度?渗流?应力耦合过程的演化规律。研究表明,模拟结果和试验值吻合良好。研究结果可为我国高放废物处置库的安全评估和选址提供科学依据。     

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。     

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.     

考虑开挖损伤的高放废物地质处置库温度-渗流-应力耦合数值模拟方法

高放废物地质处置库处于温度?渗流?应力（THM）多场耦合环境中,对高放废物处置库进行安全评估时,需进行多场耦合分析。然而,高放废物处置库开挖引起硐壁附近围岩应力重分布,产生损伤,导致围岩热学参数（T）、渗流参数（H）和力学参数（M）发生变化,且在空间上分布不均匀,这将会对运营期处置库THM耦合演化过程产生显著影响。通过分析高放废物处置库温度?渗流?应力三场的耦合原理和处置库围岩损伤的分布和演化规律,定义了损伤变量和损伤演化准则,并将损伤变量与热学参数、渗流参数、力学参数以及多场耦合参数（Biot系数、Biot模量和温度排水系数）建立联系,将围岩损伤与温度?渗流?应力建立联系,形成了一个弹塑性损伤温度?渗流?应力多场耦合数值模型,然后利用建立的模型对瑞士Mont Terri高放废物地质处置库围岩加热试验进行模拟,对比了模拟值和试验值,比较了考虑开挖损伤和不考虑开挖损伤对高放废物地质处置库温度?渗流?应力的影响,并分析了在多场耦合作用下开挖损伤的演化规律。     

考虑开挖损伤的高放废物地质处置库温度-渗流-应力耦合数值模拟方法

高放废物地质处置库处于温度-渗流-应力（THM）多场耦合环境中,对高放废物处置库进行安全评估时,需进行多场耦合分析。然而高放废物处置库开挖引起硐壁附近围岩应力重分布,产生损伤,导致围岩热学参数（T）、渗流参数（H）和力学参数（M）发生变化,且在空间上分布不均匀,这将会对运营期处置库THM耦合演化过程产生显著影响。通过分析高放废物处置库温度-渗流-应力三场的耦合原理和处置库围岩损伤的分布和演化规律,定义了损伤变量和损伤演化准则,并将损伤变量与热学参数、渗流参数、力学参数以及多场耦合参数（Biot系数、Biot模量和温度排水系数）建立联系,将围岩损伤与温度-渗流-应力建立联系,形成了一个弹塑性损伤温度-渗流-应力多场耦合数值模型,然后利用建立的模型对瑞士Mont Terri高放废物地质处置库围岩加热试验进行模拟,对比了模拟值和试验值,比较了考虑开挖损伤和不考虑开挖损伤对高放废物地质处置库温度-渗流-应力的影响,并分析了在多场耦合作用下开挖损伤的演化规律。     

高放废物处置库新疆雅满苏和天湖预选地段地下水同位素特征

<正>高放废物的深地质处置方案在世界范围内已经得到公认。安全处置高放废物的前提是必须选择合适的处置库场址。由于高放废物地质处置的特殊要求,必须对高放废物处置库的场址进行多学科、全方位的详细调查。而场址的适宜性在很大程度上取决于其水文地质条件,因为地下水是高放废物有     

类似物研究和矿物学问题

本文叙述了核废物地质处置研究领域中涉及天然和人为类似物研究中的一些矿物学问题。在自然界的天然玻璃、膨润土、晶质铀矿等分别作为高放废物玻璃固化体、高放废物处置库的缓冲／回填材料和乏燃料的天然类似物，考古遗址中的玻璃和青铜器文物作为人为类似物。通过这些天然非晶质结晶物质和人造制品的稳定性研究来预测未来10000－100000a间处置库中废物和缓冲／回填物质的变化，放射性核素迁移规律，为高放废物处置库的设计和建造提供重要科学依据，提高公众对高放废物安全处置的信心。     

高放废物地质处置黏土岩处置库围岩研究现状

世界上很多国家都对处置库的可能围岩进行了详细研究。通过对比,认为花岗岩、黏土岩、岩盐比较适合作为处置库围岩,而黏土岩由于具有自封闭性、渗透率低等其他岩石类型不可比拟的优点,因而将黏土岩作为高放废物地质处置库围岩越来越受到各国的关注。文章同时介绍了瑞士、法国、比利时等国家在黏土岩中所进行的大量研究,均认为在黏土岩中处置高放废物和乏燃料是安全的。文章还对黏土岩处置库概念设计、黏土岩处置库围岩地下实验室研究,以及我国开展黏土岩处置库研究的意义等进行了综述。     

一个高放废物处置库场地特性评价费用的估算

一个高放废物处置库场地特性评价费用的估算高放废物的处置要比中低放废物的处置要求高得多，因此尽管现在已有不少国家建成中低放废物处置场的，但却没有一个国家已建成高放废物处置库的。目前国外大都处在处置库场地的预选阶段，只有少数国家进入场地特性评价阶段。在这...     

加拿大和美国高放废物地质处置研究概况

本文主要介绍了作者2000年对加拿大和美国进行科学访问时实地考察所了解到的加拿大的核素在裂隙和孔隙介质中的迁移模式，地下实验室，白壳实验室（Whiteshell Labs)，高放废物处置库场地预选和美国拟作为高放废物处置库的尤卡山场地和已投入运行的军用超铀废物处置库的废物镉离实验工厂；着重论述了这两个国家的高放废物地质处置研究现状、经验和所取得的成果。     

核素迁移的示踪试验研究综述

按地下实验室或处置库的不同主岩,简述了以花岗岩,岩盐,粘土岩和凝灰岩等作处置库主岩的核素迁移示踪试验的研究现状,重点介绍了以花岗岩作高效废物处置库主岩的示踪试验方法和进展。     

某花岗岩型铀矿床中铀系核素和类比元素迁移特征──高放废物处置库安全评价的天然类比研究

某花岗岩型铀矿床中铀天然衰变系长寿命核素和类比微量元量，自该矿床５１Ｍａ前生成以来，未向周围花岗岩中发生远距迁移，铀矿体及近矿岩石至今仍处于化学封闭状态。矿石、岩石裂隙处局部出现有核素、元素迁移和沉淀，因裂隙细小且大多充填有粘土矿物等，迁移距离不足２５－３０ｍ，且仅发生在距今１０－１０６ａ及至今时距内。     

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。     

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。     

Thermo-mechanical Stability Analysis for a Multi-level Radioactive Waste Disposal Concept

To dispose of the spent fuels generated from the Korean nuclear power plants in an underground repository, a large area of about 4 km² is required. This could be a constraint for selecting an adequate repository site and it is required to investigate the possibility of a multi-level repository design. In this study different parameters related to the multi-level repository design such as the level distance, waste type disposed of at each level, and the time interval between the operations at the levels, were investigated using the three-dimensional code, FLAC3D. For obtaining more reliable results, rock properties measured from deep boreholes were used. From the analysis, it was possible to conclude that a multi-level repository concept could be an attractive alternative to reduce the underground area as well as to dispose of the spent fuels from Pressurized Water Reactors (PWR) and Canadian Deuterium Uranium (CANDU) reactors at different levels with different time schedules.     

A new approach to numerical method of modelling geological processes and rock engineering problems — continuum to discontinuum and linearity to nonlinearity

Numerical modelling as an efficient method is widely employed in various fields of science and engineering. In rock mechanics and geomechanics, considerable progress has been made in numerical simulation on nonlinear and discontinuum problems. However, there is a tendency in this field that the theoretical framework for nonlinear and discontinuum problems becomes more and more complicated and sometimes becomes less practicable. This paper gives a brief introduction to a newly developed numerical code, RFPA^2D (rock failure process analysis), which is mathematically a linear and continuum mechanics method for numerically processing nonlinear and discontinuum mechanics problems in rock failure. Although it is simple comparing with other numerical methods for nonlinear and discontinuum problems. It allows one to model the observed evolution of the progressive failure leading to collapse in brittle rocks. An important conclusion from the simulation results is that the microscale heterogeneity is the source of macroscale nonlinearity. Examples showing the potential applications are given in this paper. It can be seen that the RFPA^2D has a unique ability to reveal the evolutionary nature of the fracture phenomenon from microfracture scale to global failure, and the great potential exists in modelling mining induced rockbursts and stability of underground openings in greath depth. The capabilities to handle dilation, self-induced faults or even block movement and rotation should also attract applications in the fields of geomechanics as well as rock mechanics.     

Stability of expansive cement grout borehole seals emplaced in the vicinity of underground radioactive waste repositories

An expansive cementitious borehole plug emplaced in an underground opening in the vicinity of an underground nuclear waste repository may generate radial stresses on the walls of the opening due to an axial stress applied to the borehole plug and due to plug swelling. As these radial stresses may lead to the tensile fracturing of the rock, minimizing or preferably eliminating tensile stresses in rock is particularly important to preserve waste containment. Presented in this paper are the theoretical radial (normal) stress distribution and tensile strength in a borehole plug–rock system due to combined axial, thermal and lateral loading, along with analyses of plug–rock mechanical interactions in regards to borehole stability against tensile fracturing.     

A comparative simulation study of coupled THM processes and their effect on fractured rock permeability around nuclear waste repositories

This paper presents an international, multiple-code, simulation study of coupled thermal, hydrological, and mechanical (THM) processes and their effect on permeability and fluid flow in fractured rock around heated underground nuclear waste emplacement drifts. Simulations were conducted considering two types of repository settings (1) open emplacement drifts in relatively shallow unsaturated volcanic rock, and (2) backfilled emplacement drifts in deeper saturated crystalline rock. The results showed that for the two assumed repository settings, the dominant mechanism of changes in rock permeability was thermal–mechanically induced closure (reduced aperture) of vertical fractures, caused by thermal stress resulting from repository-wide heating of the rock mass. The magnitude of thermal–mechanically induced changes in permeability was more substantial in the case of an emplacement drift located in a relatively shallow, low-stress environment where the rock is more compliant, allowing more substantial fracture closure during thermal stressing. However, in both of the assumed repository settings in this study, the thermal–mechanically induced changes in permeability caused relatively small changes in the flow field, with most changes occurring in the vicinity of the emplacement drifts.