共查询到20条相似文献，搜索用时 31 毫秒
1.
The design, construction and operation of a vault for used nuclear fuel in crystalline rock may be influenced by a number of geochemical factors. During the period when a site is being selected, information is needed regarding the rock type, heterogeneities in its composition and the mineralogy of permeable zones, because these will cause variations in thermal conductivity, strength and radionuclide sorptive properties of the rock. These factors may affect decisions regarding depth of vault construction, tunnel dimensions and spacing of panels and waste containers. During site characterization, borehole drilling from the surface and subsequent hydraulic testing will introduce both chemical and microbiological contaminants that may further influence this decision.During vault construction, the geochemistry of the rock may cause changes to the design and construction methods used. High salinity fluids in the rock matrix could limit the ability of radar surveys to detect fractures in the surrounding rock and may also cause unacceptably high total dissolved solids loadings in water discharged from the facility. The presence of toxic, corrosive or radioactive constituents in inflowing groundwater may require grouting or development of treatment facilities both above and below ground. The use of explosives will cause high organic and nitrate loadings in service water as well as the possible impregnation of these chemicals in the disturbed wall-rock surrounding an excavation. These chemicals may remain despite cleaning efforts and act as nutrients to promote microbial activity in the post-closure phase. In the operational phase, inflow of increasingly saline groundwater may affect predicted container corrosion-rates and buffer and grout stabilities following vault resaturation and increase in temperature. This, in turn, may affect designs for container materials and spacing. Salt accumulations and microbial growths on vault walls may extend into the rock mass and require skimming of wall-rock before closure.This paper describes geochemical influences that might be anticipated in the disposal of nuclear waste with examples from the construction and operation of Canada's Underground Research Laboratory, Manitoba, in a granitic batholith on the Canadian Shield. 相似文献
2.
Experiments have been performed to study the thermal performance of a backfilled disposal vault in which the waste containers are emplaced in boreholes and surrounded by a bentonitesand buffer.
The near-field thermal regime in a buffer-backfill disposal vault in which the nuclear fuel waste is emplaced in canisters, is studied by one-eight scale experimental models. The thermal performance of the buffer and backfill are examined in a thermal drying environment prior to the ground water recharge of the disposal vault.
The formation of shrinkage cracks in the buffer due to drying and the response of these shrinkage cracks to the rewetting condition and their influence on the near-field thermal regime are assessed. 相似文献
3.
A.P.S. Selvadurai 《Engineering Geology》1990,28(3-4):325-335
The bentonite-sand buffer material, which isolates the nuclear-fuel waste containers from the host rock mass, is a vital component of the multiple engineered barrier scheme advocated by the Canadian Nuclear Fuel Waste Management Program. This paper presents results of laboratory investigations which examine the influence of the container surface temperatures on the moisture migration within a compacted buffer in a borehole environment. 相似文献
4.
随着世界各国大力发展核电，放射性废料的安全处置已成为当今研究热点和前沿学科。高放废物深地质处置的安全性主要取决于处置库内放射性核素向生物圈的迁移程度。在侵入岩中，放射性核素主要是通过地下水沿岩石孔隙从处置库向生物圈迁移的。为了理解放射性核素在花岗岩体接触带的迁移行为，本文根据两花岗岩体接触带中样品的铀系核素放射性活度比值（^234U/^238U,^230Th/^234U,^226Ra/^230Th,^230Th/^238U)，利用 α-反冲（弹射）作用引起的放射性不平衡理论，计算了铀系核素子体^234U,^230Th,^226Ra在后期地下水的作用下在花岗岩体接触带及其裂隙内的迁出率、迁入率、并进行了质量平衡的计算。结果表明，经α-反冲作用进入流体的核素的迁出率要远大于因核素自然衰变的消亡率；裂隙充填物及裂隙能阻滞大量核素的迁移，其沉淀核素来自接触带花岗岩；花岗岩能强烈阻滞核素的迁移，可作为阻止放射性核素从核废料地下处置库向外迁移的有利天然屏障。 相似文献
5.
The Canadian Nuclear Fuel Waste Management Program (CNFWMP) is evaluating the concept of disposal of nuclear fuel waste in an engineerted vault at a depth of 500 to 1000 m in the plutonic rock of the Canadian Shield. In common with engineered barrier system designs being developed in other countries, the waste would be contained within durable containers that, in turn, would be isolated from the host rock by clay-based materials.
The objective of the CNFWMP is to develop a disposal concept that will protect human health and the natural environment far into the future. Assessments of the conceptual vault designs are based on system theory in which an attempt is made to correlate experiences with theoretical concepts of planned systems in such a way that the resulting coordination is sound and convincing. By necessity, since experiments with a total disposal system can never be performed, both the design and the performance assessment rely on experiments performed on physical models of vault elements over relatively short times and on information inferred from calculations (mathematical models) that simulate the probable behaviour of the system in the space-time domainof interest. For a simulation model to be successful, that is applied within a real world situation, the model must provide information regarding the behaviour of the system of interest that is clearly better, in some way, than the mental image or other abstract model that would be used instead. The results of a series of tests performed within the activity known as validation serve as tangible evidence regarding the success of a model in representing the system of interest.
This paper focusses on the validation of the models that describe the hygro-thermo-mechanical behaviour of the engineered clay-barriers proposed for application in the Canadian disposal system concept. The strategy being used to address the key issues in modelling to minimize the model error and to maximize the usefulness of the simulation model, based on testing procedures, is reviewed. Finally, a concept of the validation of codes/models that describe the unsaturated behaviour of engineered clay barriers, is described. 相似文献
6.
In-situ emplacement of clay-based buffers in a nuclear fuel waste disposal vault limits the maximum attainable buffer density. This will vary with the composition of the buffer. A study of the maximum attainable densities of candidate Na bentonite/sand and illite/sand buffers is described. The addition of sand significantly increases the achievable compacted density. This increase may be obtained without any decrease in the swelling pressures developed by Na bentonite buffers. Sand decreases the shrinkage potential of the buffer and may also decrease the mass diffusion coefficient. A mixture of 50% sand and 50% clay by mass appears to optimise the physical properties of the buffer. 相似文献
7.
中国高放废物地质处置缓冲材料大型试验台架和热-水-力-化学耦合性能研究 总被引：1，自引：0，他引：1
缓冲材料作为高放废物深地质处置库中一道重要的人工屏障,与高放废物容器和处置库围岩直接接触,在高放废物衰变热、辐射作用和地下水等影响下产生复杂的热-水-力-化学耦合作用,为了验证缓冲材料是否能长期有效地发挥其屏障材料的作用,核工业北京地质研究院利用高庙子钠基膨润土组装并运行了模拟中国高放废物地质处置室 尺寸的大型缓冲材料膨润土试验台架（China-Mock-Up）。建立了缓冲材料试验台架的安装和试验方法,依据实测数据和理论分析,揭示了热-水-力-化学耦合作用条件下膨润土中的相对湿度是在加热器的热效应和外部供水的湿效应共同作用下发生变化的,压实膨润土中应力的变化主要是由于膨润土遇水膨胀和加热器的热效应引起的,试验验证了模拟高放废物地质处置室内加热器（废物罐）运行初期的位移过程,为缓冲材料和高放废物地质处置库的设计提供了重要的工程参数和理论依据。 相似文献
8.
高放废物地质处置研究中的矿物学问题 总被引：2，自引：0，他引：2
在高放废物地质处置研究中的一些矿物学问题应引起矿物学家的注意 。高放废物地 质处置库的缓冲/回填材料是选择以钠质蒙脱石为主要成分的钠基膨润土,还是以钙质蒙脱 石为主的钙基膨润土?怎样选择对99Tc、129I有较好吸附能力的硒汞矿、脆 硫锑铅矿和辉锑矿的替代物来作缓冲/回填材料中的添加剂,以能阻滞99Tc和129 I的迁移?沸石对某些放射性核素的吸附特征也需进一步研究。 相似文献
9.
A.P.S. Selvadurai 《Engineering Geology》1996,41(1-4):239-256
The paper presents the results of a series laboratory experiments which were conducted to study the heat-induced moisture movement in a bentonitic clay buffer region. In the experimental investigations, hygro-thermal phenomena are induced by a cylindrical heater which is placed within the compacted buffer material located in a borehole centrally situated in a granite block. The paper summarizes the experimental methodologies and presents results for the time-dependent distribution of temperatures within the granite block and the residual moisture distribution within the buffer at the termination of the experiment. 相似文献
10.
《Applied Geochemistry》2002,17(10):1287-1303
Many countries are considering options for long-term management of nuclear waste. One common aspect among deep geological disposal options in granitic host rock is the use of clay-based buffer materials to limit radionuclide migration in case of container failure. The isothermal test (ITT) involved placing ∼2.4 m3 of clay-based buffer in a borehole at the 240 m level of AECL's Underground Research Laboratory to study the response of buffer to resaturation by groundwater over a 6.5-year period. Results are reported here on measurements taken at the end of the test for microbial, redox and organic characterization of the buffer. Results from enumerations and biomass determinations suggested that the viable population of cells in the buffer was several orders of magnitude larger than could be cultured. It is postulated that, due to the constrictive and nutrient-poor buffer environment, viable and active cells became stressed during burial and lost activity and culturability but not viability. Culturable microbial populations at interfaces in the ITT were about an order of magnitude larger than in comparable bulk buffer samples, suggesting that interfaces may be preferred sites for microbial activity and transport. The presence of culturable SO4-reducing bacteria and an increase in solid sulphide concentrations in the buffer suggested SO4 reduction, which appeared to be very variable locally. Only about 0.02–0.5% of SO4 was converted to sulphide, suggesting that SO4 reduction was not (yet) a dominant process. No methanogens could be enumerated from the ITT, and phospholipid fatty acid (PLFA) profiles did not suggest their presence. Gas analysis of samples recovered from the ITT suggested some reduction in O2 near the top of the experiment, but deeper samples did not show a significant decrease in O2 and had only a small increase in CH4 and H2 levels. This suggested that microbial processes were depressed in the buffer but may have been more active near the concrete/buffer interface. The suggestion of low microbial activity in the buffer was corroborated by the results from the PLFA analysis, which indicated low biomass turnover rates and starvation biomarkers. The combination of enumerations, PLFA and gas analysis results suggested that no significant evolution towards reducing conditions occurred during the duration of the ITT. Fulvic acids made up the largest fraction of water-leachable humic substances but accounted for only about 2% of the total C inventory of the buffer material. The complexing capacity of these humic substances, based on carboxylic functional groups, ranged from 24 to 32 meq/g dissolved organic C. This may provide buffer porewater with considerable complexing capacity for radionuclides. 相似文献
11.
A mudcake formed on the borehole wall between a fluid-filled porous formation and the borehole fluid can affect Stoneley wave propagation used to estimate the formation permeability. The mudcake effect on the permeability dependence of radial oscillations of borehole fluid is investigated in a system with a source generating radial acoustic waves in the borehole and hydrophones (pressure sensors) that record the respective attenuating oscillations of the borehole fluid. The permeability of the porous formation is estimated from theoretical permeability dependence of the attenuation exponent, knowing the time dependence of the exponential attenuation of borehole fluid oscillations. 相似文献
12.
A.P.S. Selvadurai 《Engineering Geology》1996,41(1-4):219-238
The paper presents the application of a Galerkin finite-element technique for the numerical solution of the differential equations governing coupled heat flow and moisture movement in a clay buffer. Attention is focussed on the axisymmetric modelling of the hygro-thermal processes encountered in the single borehole emplacement configuration developed for laboratory simulation. The numerical results derived for the time-dependent temperature distributions within the granite block and the residual moisture distribution within the buffer are compared with the respective experimental results. 相似文献
13.
高放废物深部地质处置目前受到世界各国的高度重视,处置库围岩岩体质量评价是高放废物处置库选址的关键问题之一。文章基于BQ系统对我国高放废物地质处置库阿拉善预选区巴彦诺日公NRG01号钻孔进行了岩体质量评价。NRG01号孔钻孔资料丰富,采用岩芯编录、波速测井、水压致裂地应力测量及岩石波速测试、单轴压缩试验等多种方法手段相结合的方式获取了BQ评价系统中的各个参数。评价过程中,综合考虑了岩体坚硬程度、完整程度及地下水、软弱结构面、初始地应力等因素对围岩稳定的影响。根据计算的[BQ]值对岩体质量进行评价并与RQD评价结果进行对比。评价结果表明,NRG01号孔岩体质量较好,Ⅰ级和Ⅱ级岩体占90%,410~500 m的岩体范围可作为处置库建设的目标岩体。[BQ]值与RQD值所得的岩体质量评价结果一致性良好,但由于BQ系统考虑的影响因素更为全面,评价结果更为精细。本次评价可为巴彦诺日公地段高放废物地质处置库场址比选及处置库目标岩体选择提供依据。 相似文献
14.
中国高放废物深地质处置的缓冲材料选择及其基本性能 总被引：12，自引：0，他引：12
人类的许多生产、生活活动均可能产生不同活度的放射性废物,其中高放废物的安全处置倍受全球科学家和广大公众所重视。目前深地质处置被国际上公认为处置高放废物的最有效可行的方法。借鉴国外成熟的技术和经验,我国采用多重工程屏障系统(包括废物固化体、废物容器及其外包装和缓冲/回填材料)和适宜的围岩地质体共同作用,来确保高放废物与生物圈的安全隔离。膨润土由于具有极低的渗透性和优良的核素吸附等性能而被国际上选作缓冲材料的基础材料。经过全国膨润土矿床筛选,我国高放废物深地质处置库缓冲材料的研究以产自高庙子膨润土矿床深部的钠基膨润土作为基本组成材料。本文介绍了高庙子膨润土矿床的地质特征以及高庙子钠基膨润土的基本特征。该膨润土与国外同类型材料相比具有蒙脱石含量高(75%左右)、杂质矿物相对较少的特点,该材料的系统和深入研究对于开发我国缓冲回填材料技术、确保高放废物的安全有效处置有重要意义。 相似文献
15.
深地质处置目前被国际上公认为是处置高放废物的最有效可行的方法。我国采用多重工程屏障系统和适宜的地质体共同作用来确保与生物圈的安全隔离。缓冲材料是高放废物重要的工程屏障材料之一,我国选用高庙子钠基膨润土作为缓冲材料的基础材料。膨润土作为缓冲材料的一个重要性能表现为缓冲孔隙水的化学变化。介绍了GMZ-1钠基膨润土大气条件下与蒸馏水的反应试验,并对试验结果进行了讨论。批式试验反应溶液中钠离子来源于钠基膨润土层间阳离子和矿物溶解,镁离子来源于钠基膨润土层间阳离子,钾离子和钙离子来源于矿物溶解,相关研究认识对于高放废物处置库近场核素迁移研究和评价工程屏障的长期稳定性具有重要意义。 相似文献
16.
本文论述了某污染的工业废物填埋场场址的地质、水文地质条件,应用水化学方法、环境同位素技术(地下水中氚及氢、氧稳定同位素)和同位素单孔示踪技术等同位素水文学领域中的新方法对区内地下水的活动条件以及填埋场场址区分布的第四系孔隙潜水和第三纪红层孔隙-裂隙水的成因进行了分析,测量并确定了填埋场下部地下水的流速及流向。研究结果表明场区地下水的运动与地表水无直接水力联系。污染的工业废物填埋后不会通过地下水的迁移造成对地表水的污染,进而证实填埋场的地质、水文地质条件对处置污染的工业废物是安全可靠的。 相似文献
17.
Thanh Son Nguyen Lennart Börgesson Masakazu Chijimatsu Jan Hernelind Lanru Jing Akira Kobayashi Jonny Rutqvist 《Environmental Geology》2009,57(6):1239-1254
In order to demonstrate the feasibility of geological disposal of spent CANDU fuel in Canada, a safety assessment was performed
for a hypothetical repository in the Canadian Shield. The assessment shows that the maximum long term radionuclide release
from such repository would meet international criteria for dose rate; however, uncertainties in the assumed evolution of the
repository were identified. Such uncertainties could be resolved by the consideration of coupled Thermal-Hydro-Mechanical-Chemical
(THMC) processes. In Task A of the DECOVALEX-THMC project, THM models were developed within the framework of the theory of
poroelasticity. Such model development was performed in an iterative manner, using experimental data from laboratory and field
tests. The models were used to perform near-field simulations of the evolution of the repository in order to address the above-mentioned
uncertainties. This paper presents the definition and rationale of task A and the results of the simulations. From a repository
safety point of view, the simulations predict that the maximum temperature would be well below the design target of 100°C;
however, the stress on the container can marginally exceed the design value of 15 MPa. However, the most important finding
from the simulations is that a rock damage zone could form around the emplacement borehole. Such damage zone can extend a
few metres from the walls of the emplacement holes, with permeability values that are orders of magnitude higher than the
initial values. The damage zone has the potential to increase the radionuclide transport flux from the geosphere; the effect
of such an increase should be taken into account in the safety assessment and mitigated if necessary by the provision of sealing
systems.
Prepared for publication in Environmental Geology.
DECOVALEX-THMC Special Issue. 相似文献
18.
为考察孔隙气体压力对高放废物地质处置中的热-流-固耦合过程的影响,借用Leiws等建立的可变形孔隙介质中非等温空气流和水流模型,在其水连续性方程中加入了温度梯度引起的水分扩散项,研制出相应的热-水-气-应力耦合弹塑性二维有限元程序。针对一个假定的高放废物地质处置库模型,在相同的初始温度、孔隙水压力和岩体应力条件下,取3种缓冲层中的初始孔隙气体压力,通过数值模拟考察了处置库近场的主应力、饱和度、气和水的流速、温度和孔隙压力的分布与变化。结果显示,当缓冲层中的初始孔隙气压力较高时,其对围岩中应力影响较大。 相似文献
19.
20.
Smoothing and Change Point Detection for Gamma Ray Count Data 总被引：1，自引：0，他引：1
Gamma ray detectors are used to measure the natural radioactivity of rocks. For a number of boreholes drilled at a site the gamma ray detector is lowered into each borehole and counts of gamma ray emissions at different depths are recorded as the instrument is gradually raised to ground level. The profile of gamma counts can be informative about the geology at each location. The raw count data are highly variable, and in this paper we describe the use of adaptive smoothing techniques and change point models in order to identify changes in the geology based on the gamma logs. We formulate all our models for the data in the framework of the class of generalized linear models, and describe computational methods for Bayesian inference and model selection for generalized linear models that improve on existing techniques. Application is made to gamma ray data from the Castelreagh Waste Management Centre which served as a hazardous waste disposal facility for the Sydney region between March 1974 and August 1998. Understanding the geological structure of this site is important for further modelling the transport of pollutants beneath the waste disposal area. 相似文献