首页 | 本学科首页   官方微博 | 高级检索  
相似文献
 共查询到13条相似文献,搜索用时 0 毫秒
1.
2.
The large-scale geological structure of the crystalline rock at the proposed high-level nuclear waste repository site at Forsmark, Sweden, has been classified in terms of deformation zones of elevated fracture frequency. The rock between deformation zones was divided into fracture domains according to fracture frequency. A methodology to constrain the geometric and hydraulic parameters that define a discrete fracture network (DFN) model for each fracture domain is presented. The methodology is based on flow logging and down-hole imaging in cored boreholes in combination with DFN realizations, fracture connectivity analysis and pumping test simulations. The simulations suggest that a good match could be obtained for a power law size distribution where the value of the location parameter equals the borehole radius but with different values for the shape parameter, depending on fracture domain and fracture set. Fractures around 10–100 m in size are the ones that typically form the connected network, giving inflows in the simulations. The report also addresses the issue of up-scaling of DFN properties to equivalent continuous porous medium (ECPM) bulk flow properties. Comparisons with double-packer injection tests provide confidence that the derived DFN formulation of detailed flows within individual fractures is also suited to simulating mean bulk flow properties and their spatial variability.  相似文献   

3.
4.
5.
Effects on groundwater flow of abandoned engineered structures in relation to a potential geological repository for spent high-level nuclear fuel in fractured crystalline rock at the Forsmark site, Sweden, are studied by means of numerical modeling. The effects are analyzed by means of particle tracking, and transport-related performance measures are calculated. The impacts of abandoned, partially open repository tunnels are studied for two situations with different climate conditions: a “temperate” climate case with present-day boundary conditions, and a generic future “glacial” climate case with an ice sheet covering the repository. Then, the impact of abandoned open boreholes drilled through the repository is studied for present-day climate conditions. It is found that open repository tunnels and open boreholes can act as easy pathways from repository level to the ground surface; hence, they can attract a considerable proportion of particles released in the model at deposition hole positions within the repository. The changed flow field and flow paths cause some changes in the studied performance measures, i.e., increased flux at the deposition holes and decreased transport lengths and flow-related transport resistances. However, these effects are small and the transport resistance values are still high.  相似文献   

6.
Forsmark in Sweden has been proposed as the site of a geological repository for spent high-level nuclear fuel, to be located at a depth of approximately 470 m in fractured crystalline rock. The safety assessment for the repository has required a multi-disciplinary approach to evaluate the impact of hydrogeological and hydrogeochemical conditions close to the repository and in a wider regional context. Assessing the consequences of potential radionuclide releases requires quantitative site-specific information concerning the details of groundwater flow on the scale of individual waste canister locations (1–10 m) as well as details of groundwater flow and composition on the scale of groundwater pathways between the facility and the surface (500 m to 5 km). The purpose of this article is to provide an illustration of multi-scale modeling techniques and the results obtained when combining aspects of local-scale flows in fractures around a potential contaminant source with regional-scale groundwater flow and transport subject to natural evolution of the system. The approach set out is novel, as it incorporates both different scales of model and different levels of detail, combining discrete fracture network and equivalent continuous porous medium representations of fractured bedrock.  相似文献   

7.
The impact of periglacial and glacial climate conditions on groundwater flow in fractured crystalline rock is studied by means of groundwater flow modeling of the Forsmark site, which was recently proposed as a repository site for the disposal of spent high-level nuclear fuel in Sweden. The employed model uses a thermal-hydraulically coupled approach for permafrost modeling and discusses changes in groundwater flow implied by the climate conditions found over northern Europe at different times during the last glacial cycle (Weichselian glaciation). It is concluded that discharge of particles released at repository depth occurs very close to the ice-sheet margin in the absence of permafrost. If permafrost is included, the greater part discharges into taliks in the periglacial area. During a glacial cycle, hydraulic gradients at repository depth reach their maximum values when the ice-sheet margin passes over the site; at this time, also, the interface between fresh and saline waters is distorted the most. The combined effect of advances and retreats during several glaciations has not been studied in the present work; however, the results indicate that hydrochemical conditions at depth in the groundwater flow model are almost restored after a single event of ice-sheet advance and retreat.  相似文献   

8.
Both advocates and critics disagree on the significance and interpretation of critical geological features which relate to the safety and suitability of Yucca Mountain as a site for the construction of a high-level radioactive waste repository. Recent volcanism in the vicinity of Yucca Mountain is recognized readily by geologists and others with a knowledge of nuclear regulatory requirements as an important factor in determining future public and environmental safety. We regard basaltic volcanism as direct and unequivocal evidence of deep-seated geologic instability. Direct disruption of a repository site by basaltic volcanism therefore is a possibility. In this paper, sensitivity analysis of volcanic hazard assessment for the Yucca Mountain site is performed, taking into account some significant geological factors raised by experts. Three types of models are considered in the sensitivity data analysis. The first model assumes that both past and future volcanic activities follow a Homogeneous Poisson Process (HPP). The second model uses a Weibull Process (WP) to estimate the instantaneous recurrence rate based on the historical data at NTS (the Nevada Test Site). The model then switches from a WP of past events to a predictive HPP. The third model assumes that the prior historical trend based on a WP would continue for future activities. Hazards (at least one disruptive event during the next 10,000 years) using both classical and Bayesian approaches are evaluated based on the data for the following two observation periods: Pliocene and younger, and Quaternary. Combinations of various counts of events at volcanic centers of controversy and inclusion (or exclusion) of the youngest date at Lathrop Wells Center (=0.01 Ma) generate 90 different data sets. Sensitivity analysis is performed for each data set and the minimum and the maximum hazards for each model are summarized. We conclude that the estimated overall probability of at least one disruption of a repository at the Yucca Mountain site by basaltic volcanism during the next 10,000 years is bounded between 2.02×105 and 6.57×10–3.  相似文献   

9.
Calcite/opal deposits (COD) at Yucca Mountain were studied with respect to their regional and field geology, petrology and petrography, chemistry and isotopic geochemistry, and fluid inclusions. They were also compared with true pedogenic deposits (TPD), groundwater spring deposits (GSD), and calcite vein deposits (CVD) in the subsurface. Some of the data are equivocal and can support either a hypogene or pedogenic origin for these deposits. However, Sr-, C-, and O-isotope, fluid inclusion, and other data favor a hypogene interpretation. A hypothesis that may account for all currently available data is that the COD precipitated from warm, CO2-rich water that episodically upwelled along faults during the Pleistocene, and which, upon reaching the surface, flowed downslope within existing alluvial, colluvial, eluvial, or soil deposits. Being formed near, or on, the topographic surface, the COD acquired characteristics of pedogenic deposits. This subject relates to the suitability of Yucca Mountain as a high-level nuclear waste site.  相似文献   

10.
Advective mass transfer is a pore scale mass-transfer process that affects fluid and solute movement between pore domains such as fracture and matrix in a structured porous medium. Mechanistically similar to advection in the advection-dispersion of solutes in non-structured porous medium, it redistributes solutes by moving solute and solvent simultaneously between pore domains. While there is much research on diffusive mass transfer that is often referred to as matrix diffusion, there is a lack of information and study for advective mass transfer in the literature. The objective of this research is to study the effects of advective mass transfer on fluid and solute movement between pore domains. First, field hydraulic measurements at a waste disposal site in fractured rock at Oak Ridge National Laboratory (ORNL), Tennessee, USA, are used to calibrate a fracture-matrix, two-pore-domain groundwater flow model. Latin-hypercube sensitivity analysis suggests that the uncertainty of the calibrated model parameters is small and the calibrated flow model is nearly the optimal. Fracture spacing thus obtained is used to calculate diffusive mass transfer coefficients. The individual effects of advective and diffusive mass transfer on solute movement are then quantitatively evaluated. The calculations indicate that pore structure conceptual models may significantly affect the role of advective mass transfer in field and pore-scale mass transfer. In the particular ORNL field site and with a fracture-matrix pore structure model, contribution of advective mass transfer to solute mass movement is about three to eight orders of magnitude smaller than that of diffusive mass transfer.
Resumen La transferencia de masa advectiva es un proceso de transferencia de masa en escala intersticial que afecta el movimiento de fluido y soluto entre ámbitos porosos tal como fractura y matriz en un medio estructurado poroso. Este proceso, mecánicamente similar a la advección en la dispersión-advección de solutos de medios porosos no estructurados, redistribuye los solutos mediante el movimiento simultáneo de soluto y solvente entre ámbitos porosos. Mientras que existe bastante investigación en transferencia difusiva de masa que frecuentemente se conoce como difusión en matriz, existe falta de información y estudio de transferencia advectiva de masa en la literatura. El objetivo de esta investigación es estudiar los efectos de la transferencia advectiva de masa en el movimiento de fluido y soluto entre ámbitos porosos. Primero se utilizaron mediciones hidráulicas de campo en un sitio de depósito de residuos en roca fracturada en el Laboratorio Nacional Oak Ridge (ORNL), Tennessee, USA, para calibrar un modelo de flujo de agua subterránea de ámbito de dos poros fractura-matriz. Análisis de sensitividad hipercúbico-latino sugieren que la incertidumbre de los parámetros del modelo calibrado es pequeña y que el modelo de flujo calibrado es aproximadamente el óptimo. El espaciamiento de fracturas así obtenido se utiliza para calcular los coeficientes de transferencia de masa difusiva. Luego se evalúa cuantitativamente los efectos individuales de transferencia de masa advectiva y difusiva en el movimiento de soluto. Los cálculos indican que los modelos conceptuales de estructura porosa pueden afectar significativamente el papel de transferencia de masa advectiva en escalas de campo e intersticial de transferencia de masa. En el sitio de campo específico ORNL y con un modelo de estructura porosa de matriz-fractura, la contribución de transferencia de masa advectiva al movimiento de masa soluto es aproximadamente tres a ocho órdenes de magnitud más pequeño que la contribución por transferencia de masa difusiva.

Résumé Résumé Le transfert advectif de masse est un processus de transfert de masse à léchelle du pore qui affecte les mouvements du fluide et du soluté entre les différents domaines de pores, tel les fractures et la matrice dans un milieu poreux structuré. Mécaniquement similaire à ladvection dans le concept advection-dispersion de solutés dans les milieux non structurés, ce transfert redistribue les solutés simultanément avec le fluide entre les différents domaines poreux. Alors que de nombreuses recherches portent sur les transferts de masse par diffusion, se référant généralement à une diffusion par la matrice, il y a un grand manquement dinformations et détudes sur les transferts de masse par advection dans la littérature. Lobjectif de cette recherche est détudier leffet du transfert advectif de masse de fluide et de soluté entre les différents domaines poreux. Premièrement, les mesures hydrauliques de terrain sur la décharge en milieu fracturé du laboratoire national dOak Ridge ORNL, Tennessee, USA, sont utilisées pour calibrer un modèle hydrogéologique à double porosité fracture-matrice. Lanalyse de sensibilité latin-hypercube suggère que lincertitude sur les paramètres du modèle est faible et que le calibrage est pratiquement optimal. Lespace de fracture résultant permet de calculer les coefficients de transfert de masse par diffusion. Les effets individuels de ladvection et de la diffusion sur les mouvements de solutés sont dés lors évalués. Les calculs indiquent que le modèle conceptuel de la structure des pores peuvent significativement affectés le rôle du transfert advectif de masse à léchelle du pore et du terrain. Dans le cas du site de lORNL et avec un modèle structuré fracture-matrice, la contribution de ladvection au transfert de masse est de lordre de trois-huitième du transfert de masse par diffusion.
  相似文献   

11.
The development and implementation of a hybrid discrete fracture network/equivalent porous medium (DFN/EPM) approach to groundwater flow at the Gyeong-Ju low- and intermediate-level radioactive waste (LILW) disposal site in the Republic of Korea is reported. The geometrical and hydrogeological properties of fractured zones, background fractures and rock matrix were derived from site characterization data and implemented as a DFN. Several DFN realizations, including the deterministic fractured zones and the stochastic background fractures, whose statistical properties were verified by comparison with in-situ fracture and hydraulic test data, were suggested, and they were then upscaled to continuums using a fracture tensor approach for site-scale flow simulations. The upscaled models were evaluated by comparison to in-situ pressure monitoring data, and then used to simulate post-closure hydrogeology for the LILW facility. Simulation results demonstrate the importance of careful characterization and implementation of fractured zones. The study highlighted the importance of reducing uncertainty regarding the properties and variability of natural background fractures, particularly in the immediate vicinity of repository emplacement.  相似文献   

12.
Fracture data available for one of the rock masses (limestone) in the dam site of Yujian River Reservoir were used to build and validate a stochastic 3-D fracture network model, and to perform a REV and equivalent continuum study in 3-D. A number of relations are developed in the paper between the rock mass mechanical parameters and fracture tensor components in 3-D. Based on the mechanical parameter values obtained in every 45° direction in 3-D, the principal parameter values, principal directions and tensors are developed for rock mass mechanical parameters to represent the REV block size properties. An incrementally linear elastic, orthotropic constitutive model is suggested to represent the equivalent continuum pre-failure mechanical behavior of the jointed rock mass by incorporating the effect of joint geometry network by the fracture tensor components.  相似文献   

13.
In this study, the solubility constant of magnesium chloride hydroxide hydrate, Mg3Cl(OH)5·4H2O, termed as phase 5, is determined from a series of solubility experiments in MgCl2-NaCl solutions. The solubility constant in logarithmic units at 25 °C for the following reaction,
Mg3Cl(OH)5·4H2O+5H+=3Mg2++9H2O(l)+Cl-  相似文献   

设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号