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。     

中国高放废物地质处置21世纪进展

21世纪近20年,我国高放废物深地质处置进入了一稳步发展的新阶段,在法律法规、技术标准、战略规划、选址和场址评价、工程屏障研究、处置库和地下实验室概念设计、核素迁移和安全评价研究等方面取得了显著进展。其主要亮点包括颁布了《中华人民共和国放射性污染防治法》和《中华人民共和国核安全法》,制定了《高放废物地质处置研究开发规划指南》,颁布了《高放废物地质处置设施选址》核安全导则,确定了2020年前开工建设地下实验室、2050年建成高放废物处置库的目标,甘肃北山预选区被确定为我国高放废物地质处置库首选预选区,建立了场址评价方法技术体系,确定了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,建立了我国首台缓冲回填材料热 水-力-化学耦合条件下特性研究大型实验台架（China-Mock-Up）,获得了一批关键放射性核素的迁移行为数据,开展了初步的安全评价,完成了地下实验室安全技术研究。确定甘肃北山的新场为我国高放废物地质处置地下实验室的场址。2019年5月6日,国家国防科工局批复中国北山高放废物地质处置地下实验室工程建设立项建议书,标志着我国高放废物地质处置正式进入地下实验室阶段。这一系列工作进展和取得的成绩为我国2020年开工建设地下实验室、掌握高放废物地质处置技术奠定了坚实的基础。     

The UK rock characterization programme

The objective of the Nirex Science Programme is to evaluate the post-closure safety performance of a deep repository for intermediate level wastes (both long and short lived) and some low level wastes at a site near Sellafield in West Cumbria. The extensive surface-based site characterization programme, complemented by research and assessment studies, has established the potential suitability of the Sellafield site for the deep repository. However, a stage of underground investigations, the Rock Characterization Facility, is needed in order to establish the high level of confidence necessary to underpin a decision on whether to propose development of a repository, and subsequently a decision by the regulators to authorize commencement of disposal operations in the repository when it is constructed. The Rock Characterization Facility will be developed in three phases, providing a scientific programme lasting around ten years. It will address three key areas of uncertainty as follows: (1) groundwater flow and radionuclide transport; (2) natural and induced changes to the geological barrier; (3) design and construction of the repository. The nature of these uncertainties, the way in which underground investigations enable us to resolve them, and the design of the Rock Characterization Facility and its experimental programme to deliver the required information to resolve these uncertainties are described in this paper.     

开挖损伤区(EDZ)对核素迁移的影响

随着核电的发展,核电站产生的乏燃料处理处置受到了大众的高度关注.通过对嬗变法、稀释法和隔离法等方法的综合对比,目前,高放废物深地质处置是国内外公认处理核废物的最佳办法.在处置库建造阶段,由于开挖使得围岩中应力重新分布,围岩发生扰动,岩体内部原生裂隙出现扩展、连通,产生新生的微裂隙,岩体的渗透系数变大,这种区域即为开挖损...     

Progress towards a Deep Repository for Spent Nuclear Fuel in Sweden

The Swedish Nuclear Fuel and Waste Management Co. has in operation a safe and well integrated system for handling of all radioactive residues within Sweden. The existing central repository for low- and medium-level waste (SFR) and the central interim-storage facility for spent nuclear fuel (CLAB) can accommodate all the radioactive waste produced inside Sweden. Comprehensive research, development and demonstration activities are well under way for an encapsulation plant and a deep repository for spent fuel. These two facilities remain to be constructed to complete the waste management system. Siting of the deep repository is in progress with the aim of finding a suitable and accepted site. Implementation of the deep geological repository is a technical, scientific, social and political challenge. Smooth implementation must take into consideration both facts and emotions. Patience, flexibility and respect for the democratic process are important keywords. Research facilities, such as the underground Äspö Hard Rock Laboratory and the Encapsulation Laboratory, are important to promote scientific understanding as well as to demonstrate the disposal concept and technology.     

放射性碘在地质材料中吸附和迁移的研究

本文用间歇平衡实验和柱迁移实验研究了放射性~(131)I~-和~(131)IO_3~-在花岗岩-1(浙江)、花岗岩-2(江苏)、紫色页岩(江苏)、凝灰岩(江苏)等4种地质材料中的吸附和迁移行为,并测定了它们的吸附比。结果表明,四种岩石样品对~(131)I~-和~(131)IO_3~-基本上不吸附或仅有微小的吸附,间歇平衡实验与柱迁移实验所得结果除紫色页岩相差稍大外,其它基本是一致的。     

高放废物处置的几个问题

就与高放废物处置有关的几个问题,如地下实验室进行场所问题,地下实验室与处置库建设安排问题,高放废物深地质处置的替代方法等进行了探讨,希望有助于我国高放废物处置工作的进一步开展。     

核素在非饱和黄土介质中的二维迁移

试验结果表明，天然降水条件下，在近3年的试验期间，^60Co,^85Sr和^134Cs三种核素在非饱和黄土介质中的比活度分布质心仍在示中源层这内，^85Sr的侧向比活度分布方差与纵向比活度分布方差相当；在人工喷淋条件下，这些核素的迁移距离也很短，说明非饱和黄土对这些核素有较强的吸附滞留能力。或者换句话说，非饱和黄土可以作为中低放废物处置的候选地质介质。另外，根据对试验结果的拟合与分析看出，降水入渗量极大地影响着核素向下的迁移速度和纵向扩展，因此，控制流经处置库的入渗水量，是减少处置废物中放射性核素对环境影响的重要因素。     

多因素耦合作用下缓冲材料对铀的长期阻滞效应数值模拟北大核心CSCD

近场环境条件下核素在缓冲材料中的迁移扩散受控于温度场、渗流场、膨胀应力场和化学吸附场的耦合作用,其对核素的阻滞特性将影响到核素随地下水向处置库围岩迁移并返回生物圈的能力,开展多因素耦合作用下缓冲材料对铀的长期阻滞效应研究,对地质处置库的长期安全性评价具有重要的意义。本研究基于混合物理论、连续介质理论、质量守恒、动量守恒、能量守恒及溶质扩散的Fick定律,推导出饱和缓冲材料中核素迁移扩散的热-水-力-化耦合控制方程,并借助于COMSOL Multiphysics软件的直接全耦合求解优势,以自主研制的缓冲材料长期阻滞性能Mock-up实验装置为几何模型,采用内置接口和添加热-水-力-化耦合控制方程中的耦合项作为源项相结合方式,实现了多物理场耦合作用下铀在饱和缓冲材料中迁移扩散行为的直接耦合分析,其长期阻滞特性数值模拟结果表明:初期阶段铀在缓冲材料中迁移扩散较缓慢,迁移距离随时间增幅在1 m左右;中后期阶段,随缓冲材料对铀的吸附容量逐渐趋于饱和后,其迁移距离较初期阶段增加更为明显,迁移距离随时间增幅为3 m左右。多因素耦合下核素在饱和缓冲材料中迁移扩散的热-水-力-化耦合控制方程构建、求解及长期阻滞性能模拟研究的方法,能够为我国高放废物深地质处置库地下实验室开展1∶1工程尺度的工程屏障设计与安全性能评价提供技术参考。     

Evaluation of nuclide release scenarios for a hypothetical LILW repository

A program for the safety assessment and performance evaluation of a low- and intermediate-level radioactive waste (LILW) repository system has been developed. Utilizing GoldSim (2006), the program evaluates nuclide release and transport into the geosphere and biosphere under various disruptive natural and manmade events and scenarios that can occur after a waste package failure. We envisaged and illustrated these events and scenarios as occurring after the closure of a hypothetical LILW repository, and they included the degradation of various manmade barriers, pumping well drilling, and natural disruptions such as the sudden formation of a preferential flow pathway in the far-field area of the repository. Possible enhancement of nuclide transport facilitated by colloids or chelating agents is also dealt with. We used the newly-developed GoldSim template program, which is capable of various nuclide release scenarios and is greatly suited for simulating a potential repository given the geological circumstances in Korea, to create the detailed source-term and near-field release scheme, various nuclide transport modes in the far-field geosphere area, and the biosphere transfer. Even though all parameter values applied to the hypothetical repository were assumed, the illustrative results, particularly the probabilistic calculations and sensitivity studies, may be informative under various scenarios. (GoldSim, LILW, Nuclide transport, Safety assessment, Scenario).     

Boxes for the Transport and Disposal of Low Level and Decommissioning Intermediate Level Radioactive Wastes

Abstract

UK Nirex Ltd is developing specifications for standard containers for the packaging of low and intermediate level radioactive wastes for disposal in a deep underground repository. The methodology used for selection of the dimensions and payloads of boxes for LLW and decommissioning ILW are described, and design features for handling the boxes are also briefly discussed. It must be emphasised that the results of this study are as yet preliminary, and may change in the light of the evolving system design for waste packaging, storage, transport and disposal.     

Concept of a tritium extraction facility for a reprocessing plant

There are several alternatives for reducing the release of tritium to the environment originating from the wastewater of a reprocessing plant. Such alternatives, which are applicable for sites not located by the sea or by large rivers, are limited to either injection of tritiated wastewater into suitable deep geological formations, or final disposal into a deep underground repository after adequate treatment similar to other low and intermediate active waste.Removal of tritium from the wastewater by enrichment represents a further feasible option of the second alternative, which allows reduction of the huge volume of tritiated water to be treated before disposal. A significant volume reduction increases the safety of the subsequent steps such as transport, interim storage and final disposal of tritiated waste, furthermore, decreases the corresponding overall waste management cost.The projected Wackersdorf reprocessing plant has been considered as a reference for assessing the permitted tritium releases and other site characteristics.     

Am(Ⅲ)在地下水中的溶解度

溶解度对于验证地质化学程序的有效性非常重要,而地质化学程序是迁移模型的一部分。241 Am和243 Am是高放废物深地质处置研究中须重点考虑的核素,Am溶解度的准确测定将为Am的深地质处置安全评价提供可靠的数据。本文采用过饱和法测定了低氧高纯氩气氛中,不同恒定温度下,Am(Ⅲ)在甘肃北山花岗岩地下水中的溶解度,并探讨了温度、硫酸根浓度、碳酸氢根浓度及pH值对溶解度的影响。结果显示,Am(Ⅲ)的溶解度随温度和pH值的升高而减小,随起始硫酸根浓度和碳酸氢根浓度的增大而增大。虽然由于地下水中阴离子的配合作用使Am(Ⅲ)在地下水中的溶解度有增大趋势,但由于处置库近场环境中的温度较高,偏碱性地下水中Am(Ⅲ)的溶解度在温度和pH值升高的影响下大幅减小,最终有利于处置安全。     

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。     

Comparison Between Simulated Groundwater With BS03/04 Well Underground Water

The chemical composition of the underground water in the candidate area for high-level waste geological repository is one of key factors for the security and risk estimate and assessment of the repository site confirmation.     

Development of a web-based sorption database (KAERI-SDB) and application to the safety assessment of a radioactive waste disposal

Sorption plays a key role in a retardation of radionuclide migration in various geological environments. Hence sorption of radionuclides onto geological media is one of the important factors for the safety assessment of radioactive waste disposal. A web-based radionuclide sorption database program named KAERI-SDB has been developed to provide a database for the sorption of radionuclides onto geological media at various geochemical conditions. The KAERI-SDB is designed to determine the distribution coefficient (K_d) of a radionuclide and evaluate sorption properties by easily accessing an internet web-site (http://sdb.kaeri.re.kr). The KAERI-SDB provides a useful output and search result as a scatter plot chart or an index chart. The KAEI-SDB was designed to show the search results in a statistical way by representing the mean K_d value at 95% of confidence as a function of major geochemical indices. Several case studies were carried out to demonstrate the applicability of the KAERI-SDB and the result showed a successful applicability of the KAERI-SDB to various radionuclide sorption cases.     

放射性核素在矿物表面的吸附微观结构分析进展

放射性核素在矿物表面的吸附行为是影响其在环境中的浓度、迁移、转化及毒性的重要过程。本文简要介绍了放射性核素在吸附剂表面的吸附、沉淀、氧化还原反应的作用机理,针对放射性核素在矿物表面的微观吸附形态的研究中所使用的一些先进的实验分析方法,重点介绍了同步辐射X射线吸收精细结构（XAFS）技术、荧光分析以及理论计算等技术,并展望了放射性核素在矿物表面微观反应机制的研究趋势。     

Long-term lining performance - Civil engineering problem of potential retrieval of buried spent nuclear fuel

The current solution for the spent fuel, high-level and long-lived radioactive waste is to store them at surface facilities from which they will be subsequently moved to a deep repository. No such repositories are in operation currently but several such facilities are close to the construction phase. A deep repository can be situated in several types of geological conditions including clay formations, salt sediments, argillites and tuffitic and granitic rocks. The character of the host rock is the key factor determining the design and specific requirements of individual components of such a facility. The future potential retrieval of canisters containing nuclear waste from the repository is a further influential factor. The reason for retrieval of containers lies in the development of fast reactors and increased interest for spent fuel reprocessing. Naturally, the decision as to whether retrievability is technically feasible must be made before finalising the design and construction process of the repository. If the decision is made to retrieve, a design which will include all the relevant safety aspects for the potential retrieval of canisters must be determined. The lay-out of the repository, the materials to be used and the design of the various structures of the facility (e.g. access tunnels, disposal shafts, buffer and backfill) are not the only issues to be addressed. The long-term stability of the system as a whole, i.e. of all the components, is crucial. Depending on the disposal concept chosen, the thermal load generated by the waste in the disposal container, saturation by water from the surrounding environment and the loading of the host rock massif will constitute the main processes which will affect the behaviour, safety and future functioning of the repository from the civil engineering point of view. The long-term stability of the lining of disposal galleries is a basic precondition for the safe removal of spent nuclear waste from deep underground repositories. The stability problems of tunnel linings exposed to long-term thermal load have not yet been properly addressed and form the subject of the European TIMODAZ project (Thermal Impact on the Damaged Zone around a Radioactive Waste Disposal in Clay Host Rocks) and also supported by the “Complex System of Methods for Directed Design and Assessment of Functional Properties of Building Materials” project. This paper describes the design, construction and currently available results of a 1:1 scale “in situ” disposal tunnel model which has been built at the Josef Underground Educational Facility in the Czech Republic.     

The Planned Integrated Transport System for the Deep Repository in the UK

Abstract

UK Nirex Ltd is responsible for developing a deep repository for the safe disposal of intermediate and low level radioactive wastes (ILW and LLW), and is concentrating its investigations on Sellafield as a potential location. A key part of the repository development programme is a transport system to deliver packaged wastes from sites elsewhere in the UK. The transport system must be able to handle a range of standard waste packages, and all transport through the public domain must comply with the IAEA Transport Regulations. Two design concepts have been developed for re-usable shielded transport containers for ILW, which are predicted to withstand accidents at least as severe as the IAEA Type B test conditions. Assessment, testing and further development of both concepts continues, with a view to selecting one for quantity production. Nirex is working closely with various organisations to establish the optimum transport routes for a potential repository at Sellafield. The current policy is that rail transport shall be used wherever practical for the transport of waste to the repository, although some road transport may also be required; the company has assessed a range of options. A Probabilistic Safety Assessment of the proposed transport operations has predicted that the radiological risks are expected to be extremely low, reflecting the adequacy of the packaging concepts. In addition, Nirex has identified a suitable transport emergency plan to deal with any unforeseen events.