Swelling characteristics of Gaomiaozi bentonite and its prediction

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De'an Sun

2014-04-01

Full Text Available Gaomiaozi (GMZ bentonite has been chosen as a possible matrix material of buffers/backfills in the deep geological disposal to isolate the high-level radioactive waste (HLRW in China. In the Gaomiaozi deposit area, calcium bentonite in the near surface zone and sodium bentonite in the deeper zone are observed. The swelling characteristics of GMZ sodium and calcium bentonites and their mixtures with sand wetted with distilled water were studied in the present work. The test results show that the relationship between the void ratio and swelling pressure of compacted GMZ bentonite-sand mixtures at full saturation is independent of the initial conditions such as the initial dry density and water content, but dependent on the ratio of bentonite to sand. An empirical method was accordingly proposed allowing the prediction of the swelling deformation and swelling pressure with different initial densities and bentonite-sand ratios when in saturated conditions. Finally, the swelling capacities of GMZ Na- and Ca-bentonites and Kunigel Na-bentonite are compared.

Prediction for swelling characteristics of compacted bentonite

International Nuclear Information System (INIS)

Komine, H.; Ogata, N.

1996-01-01

Compacted bentonites are attracting greater attention as back-filling (buffer) materials for high-level nuclear waste repositories. For this purpose, it is very important to quantitatively evaluate the swelling characteristics of compacted bentonite. New equations for evaluating the relationship between the swelling deformation of compacted bentonite and the distance between two montmorillonite layers are derived. New equations for evaluating the ion concentration of pore water and the specific surface of bentonite, which significantly influence the swelling characteristics of compacted bentonite, are proposed. Furthermore, a prediction method for the swelling characteristics of compacted bentonite is presented by combining the new equations with the well-known theoretical equations of repulsive and attractive forces between two montmorillonite layers. The applicability of this method was investigated by comparing the predicted results with laboratory test results on the swelling deformation and swelling pressure of compacted bentonites. (author) 31 refs., 8 tabs., 12 figs

Compression characteristics and permeability of saturated Gaomiaozi ca-bentonite

International Nuclear Information System (INIS)

Sun Wenjing; Sun De'an; Fang Lei

2012-01-01

The compression characteristics and permeability of compacted Gaomiaozi Ca-bentonite saturated by the water uptake tests are studied by conducting a series of one-dimension compression tests. The permeability coefficient can be calculated by the Terzaghi's one-dimensional consolidation theory after the consolidation coefficient is obtained by the square root of time method. It is found that the compression curves of compacted specimens saturated by the water uptake tests tend to be consistent in the relatively high stress range. The compression indexes show a linear decrease with increasing dry density and the swelling index is a constant. The permeability coefficient decreases with increasing compression stress, and they show the linear relationship in double logarithmic coordinates. Meanwhile, the permeability coefficient shows a linear decrease with decreasing void ratio, which has no relationship with initial states, stress states and stress paths. The permeability coefficient k of GMZ Ca-bentonite at dry density Pd of 1.75 g/cm 3 can be calculated as 2.0 × 10 -11 cm/s by the linear relationship between Pd and log k. It is closed to the permeability coefficient of GMZ Ca-bentonite with the same dry density published in literature, which testifies that the method calculating the permeability coefficient is feasible from the consolidation coefficient obtained by the consolidation test. (authors)

Advanced diffusion model in compacted bentonite based on modified Poisson-Boltzmann equations

International Nuclear Information System (INIS)

Yotsuji, K.; Tachi, Y.; Nishimaki, Y.

2012-01-01

Document available in extended abstract form only. Diffusion and sorption of radionuclides in compacted bentonite are the key processes in the safe geological disposal of radioactive waste. JAEA has developed the integrated sorption and diffusion (ISD) model for compacted bentonite by coupling the pore water chemistry, sorption and diffusion processes in consistent way. The diffusion model accounts consistently for cation excess and anion exclusion in narrow pores in compacted bentonite by the electric double layer (EDL) theory. The firstly developed ISD model could predict the diffusivity of the monovalent cation/anion in compacted bentonite as a function of dry density. This ISD model was modified by considering the visco-electric effect, and applied for diffusion data for various radionuclides measured under wide range of conditions (salinity, density, etc.). This modified ISD model can give better quantitative agreement with diffusion data for monovalent cation/anion, however, the model predictions still disagree with experimental data for multivalent cation and complex species. In this study we extract the additional key factors influencing diffusion model in narrow charged pores, and the effects of these factors were investigated to reach a better understanding of diffusion processes in compacted bentonite. We investigated here the dielectric saturation effect and the excluded volume effect into the present ISD model and numerically solved these modified Poisson-Boltzmann equations. In the vicinity of the negatively charged clay surfaces, it is necessary to evaluate concentration distribution of electrolytes considering the dielectric saturation effects. The Poisson-Boltzmann (P-B) equation coupled with the dielectric saturation effects was solved numerically by using Runge-Kutta and Shooting methods. Figure 1(a) shows the concentration distributions of Na + as numerical solutions of the modified and original P-B equations for 0.01 M pore water, 800 kg m -3

Water uptake and stress development in bentonites and bentonite-sand buffer materials

International Nuclear Information System (INIS)

Dixon, D.A.; Wan, A.W-L.; Gray, M.N.; Miller, S.H.

1996-10-01

The development of swelling pressure and the transfer of pore water pressures through dense bentonite and bentonite-sand materials are examined in this report. This report focuses on the swelling pressure and total pressure developed in initially unsaturated specimens allowed access to free water on one end. The bentonite in this wetted region rapidly develops its full swelling pressure and this pressure is transferred upwards through the specimen. Hence, the bentonite plug will exert a pressure approximately equivalent to the swelling pressure even though only a small region of the plug is actually saturated. A number of specimens were tested with total pressure sensors mounted normal and parallel to the axis of compaction. Lateral pressures developed long before the wetting front reached sensor locations, suggesting stress transfer through the unsaturated portions of these specimens. On achieving saturation, specimens were found to have similar swelling pressures both normal to and parallel to the axis of compaction. This indicates that there is little or no specimen anisotropy induced by the compaction process. Tests were conducted on specimens allowed only to take on a limited quantity of water and it was found that density anisotropy was induced as the result of the swelling pressures generated by the buffer. The wetted skin of buffer developed a considerable pressure and compressed a region of buffer immediately above the wetted region. The results suggest that the buffer material placed in a disposal vault will rapidly develop and transfer swelling pressures as a result of the saturation of a limited region or 'skin' within the emplacement site. The total pressure ultimately present on the container surface should be the sum of the swelling and hydraulic components. (author). 14 refs., 4 tabs., 8 figs

General corrosion of Ti in hot water and water saturated bentonite clay

International Nuclear Information System (INIS)

Mattsson, H.; Olefjord, I.

1984-12-01

Titanium has been proposed as one of the candidates for canister materials for storing spent nuclear fuel in the Swedish bed-rock. The deposition milieu was simulated on a laboratory scale by embedding titanium in compacted bentonite and the general corrosion rate was investigated. More fundamental studies were also performed where titanium was exposed to water in which special attention was paid to the NaCl content and oxygen content. In reaction cells designed according to high vacuum principles it was possible to reduce the oxygen content to very low values. The exposure time ranged between 1 min. and 6 months. Analysis of the corrosion products was performed mainly with ESCA. In water at 95 degrees C the oxide growth follows a direct logarithmic law: y equals 8.7 + 3.65 ln t. Oxygen and salt do not influence the rate of the oxide growth significantly. The general corrosion rate is approximately the same as the oxide growth rate since the dissolution of Ti into the water-solution is very low. The oxide consists of an outer layer of TiO 2 and a few atomic layers of suboxide close to the oxide/metal interface. Transmission electron microscopy studies of the water-formed oxides indicate that these are amorphous. The oxides formed on Ti exposed in bentonite is 70-100 Aa thick for exposure times ranging between 4 months and 2 years. It is shown, that montmorillonite - the main constituent in bentonite - is absorbed in the TiO 2 formed on these samples. If it is assumed that a logarithmic growth law is valid even for long-term exposure in bentonite, the growth law which will give the highest growth rate is y equals 5.5 ln t. An oxide thickness of 160 Aa is obtained if this law is extrapolated to 100.000 years exposure. (Author)

Response of Compacted Bentonites to Thermal and Thermo-Hydraulic Loadings at High Temperatures

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Snehasis Tripathy

2017-07-01

Full Text Available The final disposal of high-level nuclear waste in many countries is preferred to be in deep geological repositories. Compacted bentonites are proposed for use as the buffer surrounding the waste canisters which may be subjected to both thermal and hydraulic loadings. A significant increase in the temperature is anticipated within the buffer, particularly during the early phase of the repository lifetime. In this study, several non-isothermal and non-isothermal hydraulic tests were carried on compacted MX80 bentonite. Compacted bentonite specimens (water content = 15.2%, dry density = 1.65 Mg/m3 were subjected to a temperature of either 85 or 150 °C at one end, whereas the temperature at the opposite end was maintained at 25 °C. During the non-isothermal hydraulic tests, water was supplied from the opposite end of the heat source. The temperature and relative humidity were monitored along predetermined depths of the specimens. The profiles of water content, dry density, and degree of saturation were established after termination of the tests. The test results showed that thermal gradients caused redistribution of the water content, whereas thermo-hydraulic gradients caused both redistribution and an increase in the water content within compacted bentonites, both leading to development of axial stress of various magnitudes. The applied water injection pressures (5 and 600 kPa and temperature gradients appeared to have very minimal impact on the magnitude of axial stress developed. The thickness of thermal insulation layer surrounding the testing devices was found to influence the temperature and relative humidity profiles thereby impacting the redistribution of water content within compacted bentonites. Under the influence of both the applied thermal and thermo-hydraulic gradients, the dry density of the bentonite specimens increased near the heat source, whereas it decreased at the opposite end. The test results emphasized the influence of

Alteration behavior of bentonite barrier of radioactive waste disposal by alkaline solutions. Part 1. Permeability change of compacted bentonite immersed in alkaline solutions

International Nuclear Information System (INIS)

Yokoyama, Shingo; Nakamura, Kunihiko

2010-01-01

Permeability tests using the compacted bentonites and alkaline solutions were carried out to estimate of alteration behavior and the change of permeability during the alteration reaction. The permeability tests of the compacted bentonites were carried out at 23degC for one week after they were immersed in alkaline solution at 60degC for four weeks (immersing test). After permeability tests, the compacted bentonites were repeatedly tested as the same procedure (i.e. repetition of permeability test and immersing test) at 11 cycles. The compacted bentonites with initial dry density of 1.6 Mg/m 3 were reacted with the different type of the alkaline solutions (deionized water, NaOH (pH=12 and 14), KOH (pH=12 and 14) and Ca(OH) 2 (pH=12)) in each experiments. In the case of deionized water and alkaline solutions of pH12, the mineral compositions of altered bentonite were similar to original bentonite while the exchangeable cations of altered bentonites were changed. No changes of the mineralogical features of montmorillonite in altered bentonites (i.e. illitization, baideritization and increasing of layer charge) were observed in the case of deionized water, pH12-NaOH and pH12-Ca(OH) 2 . The montmorillonite was changed to the illite/smectite interstratified mineral containing about 40% illite like component during the reaction with pH12-KOH. In the case of alkaline solutions with pH14, the component minerals of bentonite (e.g. montmorillonite, quartz and clinoptilolite) were dissolved, consequently secondly minerals (e.g. analcime and phillipsite) were crystallized during experiments. Furthermore, the mineralogical features of montmorillonite were changed as illitization (pH14-KOH), beidellitization (pH14-NaOH and pH14-KOH) and increasing of layer charge (pH14-NaOH and pH14-KOH). No increasing of permeability were observed during the experiment using pH12-NaOH and pH12-Ca(OH) 2 as well as the case of deionized water. In the case of pH12-KOH, the permeability continually

Swelling pressure in compacted bentonite below 0°C

International Nuclear Information System (INIS)

Birgersson, Martin; Karnland, Ola; Nilsson, Ulf

2010-01-01

Document available in extended abstract form only. Bentonite is a common component in many concepts for underground storage of high level radioactive waste. During its lifetime, an underground repository will be subject to various ambient temperatures. Backfilled tunnels, shafts and investigation bore holes closest to ground level will experience periods of temperature below 0 deg. C. From a safety assessment perspective, it is therefore essential to investigate and understand the behavior of bentonite below 0 deg. C. A large set of laboratory tests have been performed where fully water saturated samples of bentonites have been exposed to temperatures in the range -10 deg. C - +25 deg. C. The swelling pressure response has been recorded continuously. The samples have been varied with respect to bentonite type (e.g. calcium or sodium dominated), smectite content and density. The general observation is that the pressure of the bentonite lowers in a temperature range between 0 deg. C and a specific (negative) temperature T c , which is strongly correlated to the swelling pressure measured above 0 deg. C. Consequently, Tc decreases (i.e. becomes more negative) with increased density or smectite content. At T c , swelling pressure is completely lost. Furthermore, a very weak pressure dependence is observed at temperatures above 0 deg. C. This dependence is however strictly dependent on sample density. For any type of bentonite at high enough densities above 0 deg. C, the slope of the P-T curve is negative and becomes more negative with increasing density. For Na-dominated bentonites at lower densities, on the other hand, the slope is positive. An important observation is that no pressure increase was observed for any of the tested bentonite samples as the transition to temperatures below 0 deg. C was made. Since water expands as it freezes, this observation indicates that no ice is formed in compacted bentonite as the 0 deg. C level is passed. The observed swelling

Filtration behavior of organic substance through a compacted bentonite

International Nuclear Information System (INIS)

Kanaji, Mariko; Kuno, Yoshio; Yui, Mikazu

1999-07-01

Filtration behavior of organic substance through a compacted bentonite was investigated. Na-type bentonite containing 30wt% of quartz sand was compacted in a column and the dry density was adjusted to be 1.6 g/cm 3 . Polyacrylic acid solution (including three types of polyacrylic acid, average molecular weight 2,100, 15,000 and 450,000) was prepared and was passed through the compacted bentonite. Molecular weight distributions of polyacrylic acid in the effluent solution were analysed by GPC (Gel Permeation Chromatography). A batch type experiment was also carried out in order to examine a sorption behavior of these organic substances onto the surfaces of grains of the bentonite. The results indicated that the smaller size polyacrylic acid (molecular weight < 100,000) was passed through the compacted bentonite. On the other hand, the larger size polyacrylic acid (molecular weight ≥100,000) was mostly filtrated by the compacted bentonite. The batch type sorption tests clarified that the polyacrylic acid did not sorb onto the surfaces of minerals constituting the bentonite. Therefore it was suggested that the larger size molecules (≥100,000) of organic substances could be predominantly filtrated by the microstructure of the compacted bentonite. (author)

Diffusion of helium and estimated diffusion coefficients of hydrogen dissolved in water-saturated, compacted Ca-montmorillonite

International Nuclear Information System (INIS)

Higashihara, Tomohiro; Sato, Seichi; Ohashi, Hiroshi; Otsuka, Teppei

2001-01-01

The diffusion coefficients of hydrogen gas dissolved in water-saturated, compacted montmorillonite are required to estimate the performance of bentonite buffer materials for geological disposal of nuclear waste. As part of the effort to determine the diffusion coefficients, the diffusion coefficients of helium in water-saturated, compacted calcium montmorillonite (Ca-montmorillonite) were determined as a function of dry density, 0.78 to 1.37x10 3 kg m -3 , by a transient diffusion method. The diffusion coefficients were from 8.3x10 -10 m 2 s -1 at 0.78x10 3 kgm -3 to 2.8x10 -10 m 2 s -1 at 1.37x10 3 kgm -3 . The data obtained by this diffusion experiment of helium were highly reproducible. The diffusion coefficients of helium in Ca-montmorillonite were somewhat larger than those previously obtained for helium in sodium montmorillonite (Na-montmorillonite). The diffusion coefficients of hydrogen gas in the montmorillonites were roughly estimated using the diffusion coefficients of helium. These estimates were based on assumptions that both helium and hydrogen molecules are non-adsorptive and that the geometric factors in the compacted montmorillonites are approximately the same for diffusion of helium and diffusion of hydrogen. (author)

Advances on study of temperature effects on hydro-mechanical behaviour of densely compacted bentonite

International Nuclear Information System (INIS)

Ye Weimin; Wan Min; Chen Bao; Liu Yuemiao; Cui Yujun

2008-01-01

During the operation of a multiple-barrier geological repository, bentonite that works as a buffer/fill material of an artificial barrier will suffer complex coupling effects of thermal (T), hydrological (H), mechanical (M) process, which comes from heat of the nuclear waste radiation, mechanical stress from parent rock mass and seepage action of groundwater. The scientific results show that temperature has influence on the water retention, saturated permeability, swelling pressure, swelling strain and thermal strain of compacted bentonite. As a whole, the research about GMZ (Gao Miaozi) bentonite, which may potentially be chose as Chinese buffer/backfill material for high radioactive nuclear waste disposal, has a long way to go compare to developed contraries. Based on comprehensive laboratory tests and advanced theoretical framework, both of the study on behaviour of compacted GMZ bentonite under HTM coupling conditions, and the establishment of a constitutive relation for prediction of behaviour of compacted bentonite under multi-field coupling conditions are important in theoretic and practical way. (authors)

Geochemical and Mineralogical Changes in Compacted MX-80 Bentonite Submitted to Heat and Water Gradients

International Nuclear Information System (INIS)

Gomez-Espina, R.; Villar, M. V.

2010-01-01

A 20-cm high column of MX80 bentonite compacted at dry density 1.70 g/cm 3 with an initial water content of 16 percent was submitted to heating and hydration by opposite ends for 496 days (TH test). The temperature at the bottom of the column was set at 140 degree centigrade and on top at 30 degree centigrade, and deionised water was injected on top at a pressure of 0.01 MPa. Upon dismantling water content, dry density, mineralogy, specific surface area, cation exchange capacity, content of exchangeable cations, and concentration of soluble salts and pH of aqueous extracts were determined in different positions along the bentonite column. The pore water composition was modelled with a geochemical software. The test tried to simulate the conditions of an engineered barrier in a deep geological repository for high-level radioactive waste. The water intake and distribution of water content and dry density along the bentonite were conditioned by the thermal gradient. Liquid water did not penetrate into the column beyond the area in which the temperature was higher than 100 degree centigrade. A convection cell was formed above this area, and liquid water loaded with ions evaporated towards cooler bentonite as it reached the area where the temperature was too high. In this area precipitation of mineral phases took place, Advection, interlayer exchange and dissolution/precipitation processes conditioned the composition of the pore water along the column. In most of the column the pore water was Na-SO 4 2 - type, and changed to Na-Cl near the heater. TH treatment did not cause significant changes in the smectite content or the other mineral phases of the bentonite. (Author) 41 refs.

Geochemical and Mineralogical Changes in Compacted MX-80 Bentonite Submitted to Heat and Water Gradients

Energy Technology Data Exchange (ETDEWEB)

Gomez-Espina, R.; Villar, M. V.

2010-05-01

A 20-cm high column of MX80 bentonite compacted at dry density 1.70 g/cm{sup 3} with an initial water content of 16 percent was submitted to heating and hydration by opposite ends for 496 days (TH test). The temperature at the bottom of the column was set at 140 degree centigrade and on top at 30 degree centigrade, and deionised water was injected on top at a pressure of 0.01 MPa. Upon dismantling water content, dry density, mineralogy, specific surface area, cation exchange capacity, content of exchangeable cations, and concentration of soluble salts and pH of aqueous extracts were determined in different positions along the bentonite column. The pore water composition was modelled with a geochemical software. The test tried to simulate the conditions of an engineered barrier in a deep geological repository for high-level radioactive waste. The water intake and distribution of water content and dry density along the bentonite were conditioned by the thermal gradient. Liquid water did not penetrate into the column beyond the area in which the temperature was higher than 100 degree centigrade. A convection cell was formed above this area, and liquid water loaded with ions evaporated towards cooler bentonite as it reached the area where the temperature was too high. In this area precipitation of mineral phases took place, Advection, interlayer exchange and dissolution/precipitation processes conditioned the composition of the pore water along the column. In most of the column the pore water was Na-SO{sub 4} {sup 2}- type, and changed to Na-Cl near the heater. TH treatment did not cause significant changes in the smectite content or the other mineral phases of the bentonite. (Author) 41 refs.

Evaluation of gas migration characteristics of compacted bentonite and Ca-bentonite mixture

International Nuclear Information System (INIS)

Tanaka, Yukihisa; Hironaga, Michihiko

2014-01-01

In the current concept of subsurface disposal and near-surface pit disposal for low level radioactive waste, compacted bentonite and Ca-bentonite mixture will be used as an engineered barrier mainly for inhibiting migration of radioactive nuclides, respectively. Hydrogen gas can be generated inside the engineered barrier of subsurface disposal facilities mainly by anaerobic corrosion of metals used for containers, etc. Hydrogen gas can be also generated inside the engineered barrier of near-surface pit disposal facilities mainly by the chemical interaction between aluminum and the alkaline component of cement, or water. If the gas generation rate exceeds the diffusion rate of gas molecules inside of the compacted bentonite and Ca-bentonite mixture, gas will accumulate in the void space inside of the compacted bentonite and Ca-bentonite mixture until breakthrough occurs. It is expected to be not easy for gas to entering into the compacted bentonite mixture as a discrete gaseous phase because the pore of the compacted bentonite and Ca-bentonite mixture is so minute. Therefore in this study, the gas migration characteristics and the effect of gas migration on the hydraulic conductivity of the compacted bentonite and Ca-bentonite mixture are investigated by the gas migration tests. The applicability of the two phase flow model without considering deformability of the specimen is investigated. The applicability of the model of two phase flow through deformable porous media, which was originally developed by CRIEPI, is also investigated. Results of this study imply that : (1) Gas migration mechanism of the compacted bentonite and Ca-bentonite mixture is revealed through gas migration test. (2) Hydraulic conductivity measured after the large gas breakthrough is substantially the same that measured before the gas migration test. (3) Stress change, pore-water pressure change and volume change of the specimen during the gas migration test can be reproduced by the numerical

Porewater chemistry in compacted bentonite

Energy Technology Data Exchange (ETDEWEB)

Muurinen, A.; Lehikoinen, J. [VTT Chemical Technology, Espoo (Finland)

1999-03-01

In this study, the porewater chemistry in compacted bentonite, considered as an engineered barrier in the repository of spent fuel, has been studied in interaction experiments. Many parameters, like the composition and density of bentonite, composition of the solution, bentonite-to-water ratio (B/W), surrounding conditions and experimental time have been varied in the experiments. At the end of the interaction the equilibrating solution, the porewaters squeezed out of the bentonite samples, and bentonites themselves were analyzed to give information for the interpretation and modelling of the interaction. Equilibrium modelling was performed with the HYDRAQL/CE computer code 33 refs.

Saturation of bentonite dependent upon temperature

International Nuclear Information System (INIS)

Hausmannova, Lucie; Vasicek, Radek

2010-01-01

volume which attains a value of 1.0 in the fully saturated material. In the case of fully saturated bentonite with high dry density this value may exceed this theoretical limit due to very strong forces acting within the structure of the solid material which change the properties of the fixed water monolayer (the highest values of water density are close to 2000 kg/m 3 ). The aim of the experiment was to compare the degree of saturation of samples saturated at different temperatures (25 deg. C, 95 deg. C and 110 deg. C). Nine small physical models were used in the experiment. Cylindrically shaped samples with a height of 20 mm and a diameter of 30 mm were tested. The models were perforated and equipped with permeable plates on both bases to allow the supply of water. The expansion of the samples (volume change) was not permitted. The swelling pressure was not measured so as to keep the construction of the models as simple as possible. The saturation medium consisted of distilled water. The samples were compacted directly into the body of the individual models. The investigated medium consisted of Czech Ca-Mg bentonite from the Rokle locality, sieved to a fraction of 0-1 mm. The target dry density was 1700 kg/m 3 because Rokle bentonite at this dry density level contains the desired properties for use as a buffer (principally low permeability and a certain level of swelling pressure). A specific density of 2800 kg/m 3 was used for further calculations. Three models were used for testing at a certain temperature. The three models were then placed in a pressure cooker and each pressure cooker was stored at a different temperature (25 deg. C, 95 deg. C and 110 deg. C). The cookers had safety valves to limit the increase in generated steam pressure at higher temperatures; the exact monitoring of steam pressure was, unfortunately not possible. The models were dismantled after all the bentonite samples became fully saturated. The experiment was monitored by the regular weighing

Changes on the mineralogical and physico-chemical properties of a compacted bentonite in contact with hyperalkaline pore fluids

International Nuclear Information System (INIS)

Fernandez, A.M.; Melon, A.; Sanchez, D.M.

2010-01-01

Document available in extended abstract form only. In high-level radioactive waste disposal (HLW) concepts, compacted bentonites are being considered in many countries as a sealing material because of their low permeability, high swelling capacity and high plasticity. In the case of the geological disposal of nuclear wastes in argillaceous host formations, concrete will be also used as support of tunnels and galleries and as waste containment material. Therefore, the bentonite barrier will become saturated with the water resulting from the host-rock/concrete interaction. An understanding of the rate and nature of the bentonite alteration, as well as the evolution of the bentonite pore water in the long-term is important for performance assessment. In this work the behaviour of the bentonite has been simulated in a laboratory test. A concrete-bentonite interaction experiment has been performed at a high solid to liquid ratio with FEBEX bentonite. The aim of the experiment was to analyse the buffering capacity of the bentonite and the clay mineral stability in a high-pH environment over a long contact period. The rate of pH buffering capacity of the bentonite is related to its surface hydroxyl sites (≡SOH) located along the edges of the clay platelets (fast reaction), and the montmorillonite crystal lattice itself (governed by reaction kinetics). Two infiltration tests with hyper-alkaline water were performed with FEBEX bentonite compacted at a dry density of 1.65 g/cm 3 with a hygroscopic water content (w.c.) of 13.4% in small-scale hermetic cells (50- mm diameter and 25-mm high). The experiments were running for 1.65 years under anoxic conditions inside an anoxic glove (< 1 ppm O 2 ) box and at temperature of 30-35 deg. C. The type of alkaline solution was a Na-K-OH water in equilibrium with portlandite, Ca(OH) 2 , at pH 13.5. This water is representative of an average pore water of a mortar made with CEM-I-SR type Portland cement (sulphate-resistant) at a 0

Two-phase water movement in unsaturated compacted bentonite under isothermal condition

International Nuclear Information System (INIS)

Takeuchi, Shinji

1994-01-01

Bentonite is considered as one of the most promising buffer materials of engineered barrier system (EBS) for the geological isolation of high level radioactive waste (HLW) in Japan. The EBS may be composed of vitrified waste, overpack and buffer material. In the early stage of setting and backfilling of HLW, a coupled thermal-hydro-mechanical phenomenon may occur in buffer material due to various causes, but water movement may be the most important phenomenon for the coupled process. It is necessary to verify the two-phase movement for the precise modeling of the water movement in unsaturated bentonite. In this study, in order to analyze water movement, the water retention curves and water diffusivity of compacted bentonite were obtained as the functions of water content, dry density and temperature. Also water movement behavior was examined by applying the Philip and de Vries' and Darcy's equations to the obtained water diffusivity. Water potential was measured with a thermocouple psychrometer. The equation for water diffusivity is shown. The measurement of water potential and water diffusivity and the results are reported. (K.I.)

A validation study for the gas migration modelling of the compacted bentonite using existing experiment data

International Nuclear Information System (INIS)

Tawara, Y.; Mori, K.; Tada, K.; Shimura, T.; Sato, S.; Yamamoto, S.; Hayashi, H.

2010-01-01

Document available in extended abstract form only. After the field-scaled Gas Migration Test (GMT) was carried out at Grimsel Test Site (GTS) in Switzerland from 1997 through 2005, a study on advanced gas migration modelling has been conducted as a part of R and D programs of the RWMC (Radioactive Waste Management funding and Research Center) to evaluate long-term behaviour of the Engineered Barrier System (EBS) for the TRU waste disposal system in Japan. One of main objectives of this modelling study is to provide the qualified models and parameters in order to predict long-term gas migration behaviour in compacted bentonite. In addition, from a perspective of coupled THMC (Thermal, Hydrological, Mechanical and Chemical) processes, the specific processes which may have considerable impact to the gas migration behaviour are discussed by means of scoping calculations. Literature survey was conducted to collect experimental data related to gas migration in compacted bentonite in order to discuss an applicability of the existing gas migration models in the bentonite. The well-known flow rate controlled-gas injection experiment by Horseman, et al. and the pressure-controlled-gas injection test using several data with wide range of clay density and water content by Graham, et al, were selected. These literatures show the following characteristic behaviour of gas migration in high compacted and water-saturated bentonite. The observed gas flow rate from the outlet in the experiment by Horseman et al. was numerically reproduced by using the different conceptual models and computer codes, and then an applicability of the models and the identified key parameters such as relative permeability and capillary pressure were discussed. Helium gas was repeatedly injected into fully water-saturated and isotropically consolidated MX-80 bentonite (dry density: 1.6 Mg/m 3 ) in the experiment. One of the most important conclusions from this experiment is that it's impossible for

Pore water chemistry of Rokle Bentonite (Czech Republic)

International Nuclear Information System (INIS)

Cervinka, R.; Vejsada, J.

2010-01-01

Document available in extended abstract form only. With inflowing the groundwater to Deep Geological Repository (DGR), the interaction of this water with engineering barrier materials will alter both, barrier materials and also the groundwater. One of the most important alterations represents the formation of bentonite pore water that will affect a number of important processes, e.g. corrosion of waste package materials, solubility of radionuclides, diffusion and sorption of radionuclides. The composition of bentonite pore water is influenced primarily by the composition of solid phase (bentonite), liquid phase (inflowing groundwater), the gaseous phase (partial pressure of CO 2 ), bentonite compaction and the rate of groundwater species diffusion through bentonite. Also following processes have to be taken into account: dissolution of admixtures present in the bentonite (particularly well soluble salts, e.g. KCl, NaCl, gypsum), ion exchange process and protonation and deprotonation of surface hydroxyl groups on clay minerals. Long-term stability of mineral phases and possible mineral transformation should not be neglected as well. In the Czech Republic, DGR concept takes local bentonite into account as material for both buffer and backfill. The candidate bentonite comes from the Rokle deposit (NW Bohemia) and represents complex mixture of (Ca,Mg)-Fe-rich montmorillonite, micas, kaolinite and other mineral admixtures (mainly Ca, Mg, Fe carbonates, feldspars and iron oxides). The mineralogical and chemical characteristics were published previously. This bentonite is different in composition and properties from worldwide studied Na-bentonite (e.g. MX-80, Volclay) or Na-Ca bentonite (e.g. Febex). This fact leads to the need of investigation of Rokle bentonite in greater detail to verify its suitability as a buffer and backfill in DGR. Presented task is focused on the study of pore water evolution. Our approach for this study consists in modeling the pore water using

Study on the saturating and swelling behavior of an engineering bentonite barrier using a test model

International Nuclear Information System (INIS)

Nakajima, Makoto; Kobayashi, Ichizo; Toida, Masaru; Fujisaki, Katsutoshi

2007-01-01

The conceptual design of a disposal facility with additional buffer depth for radioactive waste is mainly constituted from the multi-barrier system that is constructed around the waste form so that it prevents radionuclide transfer to the biosphere. The engineered bentonite barrier is one of the elements of the multi-barrier system and is constructed with homogeneous bentonite-containing material compacted to a high density so that there are no voids. Due to the swelling characteristics of the bentonite material, the self-sealing function which is an important function of the bentonite barrier can work, but at the same time it mechanically affects the neighboring structures. Therefore, an experimental study was implemented in order to evaluate the mechanical effect of the bentonite swelling behavior throughout the construction, emplacement operations and closure re-saturation phase. In this article, the results of swelling tests to obtain the mechanical properties of the bentonite and three types of test model experiments performed for the event observations in the different saturation processes are described. As a result, the effects of a seepage pattern of ground water and a variation in the density produced by construction on the swelling pressure distribution of the bentonite barrier could be reproduced and validated. It is thought that they will be important events when ground water permeates the bentonite layer of a multiple barrier system. (author)

Effect of dry density and salinity on Cl- diffusion of compacted Na-montmorillonite

International Nuclear Information System (INIS)

Goto, T.; Gorai, M.; Kozaki, T.; Sato, S.

2010-01-01

Document available in extended abstract form only. Compacted bentonite is candidate buffer material in geological disposal of high-level radioactive waste (HLW). One of the expected functions of the buffer is to retard the migration of radionuclides from waste form to biosphere. Due to low hydraulic conductivity of the compacted bentonite, diffusion is considered to be predominant process in radionuclide migrations. Therefore, it is important for safety assessment of the geological disposal to clarify the diffusion behavior of radionuclides in montmorillonite, which is a major clay mineral of bentonite. However, detail diffusion mechanism has not been fully understood especially for the compacted bentonite saturated with groundwater having relatively high salt concentration. In this study, apparent diffusion coefficient (D a [m 2 s -1 ]) of Cl- ions was determined by one-dimensional, non-steady diffusion method for Na-montmorillonite saturated with NaCl solutions with different concentrations. Activation energy for Cl - diffusion (E a [kJ mol -1 ]) was also obtained from the temperature dependence of Da at each NaCl concentration. Based on these experimental results together with the basal spacing of the montmorillonite determined by XRD measurements, the diffusion mechanism of Cl - ions was discussed. The montmorillonite used in this study was Kunipia-F, a commercial product of Kunimine Industries Co. Ltd., Japan. The montmorillonite sample was homo-ionized into Na-type before use. The Na-montmorillonite was compacted into an acrylic resin cell (20 mm in diameter, 20 mm in height for diffusion experiment or 10 mm in height for XRD measurement) and fully saturated with NaCl solutions of concentration from 0 to 0.5 M. The dry densities of the Na-montmorillonite were 1.0 and 1.3 Mg m -3 for diffusion experiments, and from 0.7 to 1.4 Mg m -3 for the XRD measurements. The apparent diffusion coefficients of 36 Cl - ions in the solution-saturated, compacted

Changes in the microstructure of compacted bentonite caused by heating and hydration

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Villar M.V.

2016-01-01

Full Text Available Two twin 40-cm long columns of compacted FEBEX bentonite were tested in Teflon cells; water was supplied through the top surface of the columns and in one of them a heater was placed at the base and set to 100°C. The purpose of these tests was to simulate the behaviour of an engineered barrier in a radioactive waste repository and investigate the effect of the thermal gradient on saturation. In particular, changes in the pore size distribution and interlayer size have been investigated in this work. The thermal gradient had a strong influence on the water intake and distribution. Water content and dry density gradients persisted in the two columns after 12 years of testing. These changes gave place to the modification of the bentonite microstructure, overall increasing the microstructural void ratio and the proportion of adsorbed, interlayer water.

Borehole sealing with highly compactd Na bentonite

International Nuclear Information System (INIS)

Pusch, R.

1981-12-01

This report describes the use of highly compacted Na bentonite for borehole plugging. Bentonites have an extremely low permeability and a low diffusivity, and a swelling ability which produces a nonleaching boundary between clay and rock if the initial bulk density of the bentonite is sufficiently high. The suggested technique, which is applicable to long vertical, and inclined, as well as horizontal boreholes, is based on the use of perforated copper pipes to insert elements of compacted bentonite. Such pipe segments are connected at the rock surface and successively inserted in the hole. When the hole is equipped, the clay takes up water spontaneously and swells through the perforation, and ultimately forms an almost completely homogenous clay core. It embeds the pipe which is left in the hole. Several tests were conducted in the laboratory and one field test was run in Stripa. They all showed that a gel soon fills the slot between the pipe and the confinement which had the form of metal pipes in the laboratory investigations. Subsequently, more clay migrates through the perforation and produces a stiff clay filling in the slot. The redistribution of minerals, leading ultimately to a high degree of homogeneity, can be described as a diffusion process. The rate of redistribution depends on the joint geometry and water flow pattern in the rock. In the rock with an average joint frequence of one per meter or higher, very good homogeneity and sealing ability of the clay are expected within a few months after the application of the plug. (author)

Gas migration characteristics of highly compacted bentonite ore

International Nuclear Information System (INIS)

Tanaka, Yukihisa; Hironaga, Michihiko

2010-01-01

In the current concept of repository for radioactive waste disposal, compacted bentonite will be used as an engineered barrier mainly for inhibiting migration of radioactive nuclides. Hydrogen gas can be generated inside the engineered barrier by anaerobic corrosion of metals used for containers, etc. If the gas generation rate exceeds the diffusion rate of dissolved gas inside of the engineered barrier, gas will accumulate in the void space inside of the engineered barrier until its pressure becomes large enough for it to enter the bentonite as a discrete gaseous phase. It is expected to be not easy for gas to entering into the bentonite as a discrete gaseous phase because the pore of compacted bentonite is so minute. Gas migration characteristics of highly compacted powdered bentonite are already reported by CRIEPI. In this report, gas migration characteristics of bentonite ore, which is a candidate for construction material of repository for radioactive waste, is investigated. The following conclusions are obtained through the results of the gas migration tests which are conducted in this study: 1) When the total gas pressure exceeds the initial total axial stress, the total axial stress is always equal to the total gas pressure because specimens shrink in the axial direction with causing the clearance between the end of the specimen and porous metal. By increasing the gas pressure more, gas breakthrough, which defined as a sudden and sharp increase in gas flow rate out of the specimen, occurs. Therefore gas migration mechanism of compacted bentonite ore is basically identical to that of compacted powdered bentonite. 2) Hydraulic conductivity measured after the gas breakthrough is somewhat smaller than that measured before the gas migration test. This fact means that it might be possible to neglect decline of the function of bentonite as engineered barrier caused by the gas breakthrough. These characteristics of compacted bentonite ore are identical to those of

Alteration behavior of bentonite barrier of radioactive waste disposal by alkaline solutions. Part 2. Effect of type of alkaline solution on permeability of compacted bentonite-sand mixture

International Nuclear Information System (INIS)

Yokoyama, Shingo; Nakamura, Kunihiko; Tanaka, Yukihisa; Hironaga, Michihiko

2011-01-01

Permeability tests were carried out using compacted bentonite-sand mixture with initial dry density of 1.55 Mg/m 3 and alkaline solutions at 50degC for about two years to estimate the alteration behavior and the change in the permeability. Bentonite-sand mixtures which contain bentonites of 15wt% were made using Na-bentonite or Ca-exchanged bentonite. 0.3M-NaOH solution with pH 13.3 and 5mM-Ca(OH) 2 solution with pH 12.0 were used to the permeability tests of Na-bentonite-sand mixture and of Ca-exchanged bentonite-sand mixture, respectively. In the case of the permeability test conducted using NaOH solution, montmorillonite and other associated minerals were dissolved, and consequently, the dry density and effective montmorillonite density of Na-bentonite-sand mixture were decreased. Furthermore, the mineralogical feature of montmorillonite was changed (i.e. beidellitization and an increase in the layer charge). The permeability of Na-bentonite-sand mixture was increased 5.6 times by the end of permeability test as a result of above alteration. In the case of the permeability test conducted using Ca(OH) 2 solution, montmorillonite and other associated minerals were dissolved, and calcium silicate hydrate (C-S-H) was precipitated. Consequently, the dry density of Ca-exchanged bentonite-sand mixture was increased, while the effective montmorillonite density was decreased. The mineralogical feature of montmorillonite was changed (i.e. beidellitization and an increase in the layer charge). The permeability of Ca-exchange bentonite-sand mixture was decreased by more than two orders of magnitude due to fill the pore of Ca-exchange bentonite-sand mixture by the precipitation of C-S-H. From above results, the type of alkaline solution affects the mineralogical alteration behavior of the compacted bentonite-sand mixture, and consequently, affects the changing trend of permeability. In conclusion, it is important not only to consider the dissolution of montmorillonite, but

Effect of heating and pore water salinity on the swelling characteristics of bentonite buffer

International Nuclear Information System (INIS)

Dhawan, Sarita; Rao, M. Sudhakar

2010-01-01

Document available in extended abstract form only. Changes in swell potential of bentonite-sand mixture as a function of temperature and pore water salinity were measured. Bentonite dried at 105 deg. C and sand was mixed in 50:50 ratio by weight for study. The bentonite sand mix was compacted to 1.83 Mg/m 3 dry density and 13.8% water content (mixed with distilled water) obtained from Modified proctor compaction test for all test conditions. For the first series, the mix was prepared using distilled water as molding fluid. The compacted samples were dried at temperatures 50 deg. C and 80 deg. C for time periods 2 to 45 days. Dried samples were assembled in oedometer cells and allowed to swell under load of 6.25 kPa. In second series, bentonite sand mixes were prepared with 1000 ppm Na, 1000 ppm K, 1000 ppm Ca and 1000 ppm Mg solutions using chloride salts to achieve water content of 13.8%. The mixes were then compacted and dried at 80 deg. C for 15 days and allowed to swell in oedometer assembly. In third series of experiments, bentonite sand mix were compacted with distilled water as molding fluid and heated at 80 deg. C for 15 days. The dried samples were then swollen inundating with solutions simulating less saline granitic ground water and a moderately saline groundwater. The swell behavior is compared with samples without heating treatment. For samples prepared with distilled water and heated, the swell potential reduced up to 10-28% on heating compared to sample without any heating. The swell reduction varied depending on temperature and time period. The volumetric shrinkage varied from 1.4 to 3.3% of original volume of compacted sample on heating. Addition of sand was found effective in controlling shrinkage caused by heating. For samples prepared with salt solutions with no heating and inundated with distilled water for swell, the swell potential reduced from 12-20% compared to sample mixed and inundated with distilled water. The reduction in swell

Diffusion of anions and cations in compacted sodium bentonite

International Nuclear Information System (INIS)

Muurinen, A.

1994-02-01

The thesis presents the results of studies on the diffusion mechanisms of anions and cations in compacted sodium bentonite, which is planned to be used as a buffer material in nuclear waste disposal in Finland. The diffusivities and sorption factors were determined by tracer experiments. The pore volume accessible to chloride, here defined as effective porosity, was determined as a function of bentonite density and electrolyte concentration in water, and the Stern-Gouy double-layer model was used to explain the observed anion exclusion. The sorption of Cs + and Sr 2+ was studied in loose and compacted bentonite samples as a function of the electrolyte concentration in solution. In order to obtain evidence of the diffusion of exchangeable cations, defined as surface diffusion, the diffusivities of Cs + and Sr 2+ in compacted bentonite were studied as a function of the sorption factor, which was varied by electrolyte concentration in solution. The measurements were performed both by a non-steady state method and by a through-diffusion method. (89 refs., 35 fig., 4 tab.)

Rapid increases in permeability and porosity of bentonite-sand mixtures due to alteration by water vapor

International Nuclear Information System (INIS)

Couture, R.A.

1984-01-01

Packed columns of canister packing material containing 25% bentonite and 75% quartz or basalt sand, were exposed to water vapor at temperatures up t 260 0 C. The permeabilities of the columns were subsequently measured after complete saturation with liquid water in a pressurized system. Exposure to water vapor caused irreversible increases in permeability by factors of up to 10 5 . After saturation with liquid water, the permeability was nearly independent of temperature. The increases in permeability were due to a large decrease in the ability of the bentonite to swell in water. Calculations suggest that swelling of bentonite altered at 250 0 C was not sufficient to fill the pore spaces. If the pore spaces are filled, the mixture will form an effective barrier against flow, diffusion, and transport of colloids. The results suggest that if bentonite-based canister packing material is exposed even briefly to water vapor at high temperatures in a high-level nuclear waste repository, its performance will be seriously impaired. The problem is less severe if the proportion of bentonite is high and the material is highly compacted. Previous results show significant degradation of bentonite by water vapor at temperatures as low as 150 0 C. This suggests that in some repositories, backfill in tunnels and drifts may also be affected. 9 references, 5 figures, 1 table

Selfinjection of highly compacted bentonite into rock joints

International Nuclear Information System (INIS)

Pusch, R.

1978-02-01

When radioactive waste is disposed in bore holes in rocks there will be some space between rock and canister. Other investigations have suggested that the space could be filled with highly compacted bentonite. In this report it is discussed if open joints formed or widened in the surrounding rock after the deposition will be sealed by self-injecting bentonite. Bentonite in contact with water will swell. The flow pattern and properties of the swelling bentonite, the permeability of the extruded bentonite and the viscosity of the extruded bentonite have been investigated. The following statements are done. In the narrow joints that can possibly be opened by various processes, the rate of bentonite extrusion will be very slow except for the first few centimeter move, which may take place in a few mounths. The swelling pressure of the extruded bentonite will decrease rapidly with the distance from the deposition hole. The loss of bentonite extruded through the narrow joints will be negligible. In the outer part of the bentonite zone there will be a successive transition to a very soft, dilute bentonite suspension. It will consist of fairly large particle aggregates which will be stuck where the joint width decreases

Ageing effects on swelling behaviour of compacted GMZ01 bentonite

Energy Technology Data Exchange (ETDEWEB)

Ye, W.M., E-mail: ye_tju@tongji.edu.cn [Key Laboratory of Geotechnical and Underground Engineering of Ministry of Education, Tongji University, Shanghai 200092 (China); United Research Center for Urban Environment and Sustainable Development, the Ministry of Education, China, Shanghai 200092 (China); Lai, X.L.; Liu, Y. [Key Laboratory of Geotechnical and Underground Engineering of Ministry of Education, Tongji University, Shanghai 200092 (China); Chen, Y.G. [Key Laboratory of Geotechnical and Underground Engineering of Ministry of Education, Tongji University, Shanghai 200092 (China); United Research Center for Urban Environment and Sustainable Development, the Ministry of Education, China, Shanghai 200092 (China); Cui, Y.J. [Key Laboratory of Geotechnical and Underground Engineering of Ministry of Education, Tongji University, Shanghai 200092 (China); Ecole des Ponts Paris Tech, UR Navier/CERMES (France)

2013-12-15

Highlights: • Ageing effects on compacted GMZ01 bentonite are investigated. • Swelling property decreases with ageing and influenced by initial conditions. • Ageing effects are mainly attributed to the bonding effects and the hydration of smectites. - Abstract: Ageing effects on the swelling properties of compacted GMZ01 bentonite are investigated in this paper. Samples were compacted to prescribed dry densities and water contents and kept for ageing under constant volume and K{sub 0} confined conditions for target days of 0, 1, 7, 15, 30 and 90. Then, swelling deformation and swelling pressure tests were performed on the aged samples. Results indicate that both the swelling deformation and swelling pressure decrease with ageing time, with a more significant decrease at the first few days of ageing. Ageing effects are more pronounced for samples with large dry density and high water content. At the same initial dry density and water content, samples aged under constant volume conditions show much smaller decrease of swelling pressure compared to that of samples aged under K{sub 0} confined conditions. The decrease of swelling potential of samples with ageing days is mainly attributed to the bonding effects and the internal redistribution of water within the bentonite, which was confirmed by the changes of microstructure of samples with ageing.

Gas migration mechanism of saturated dense bentonite and its modeling

International Nuclear Information System (INIS)

Tanaka, Yukihisa; Hironaga, Michihiko; Kudo, Koji

2007-01-01

In the current concept of repository for nuclear waste disposal, compacted bentonite will be used as an engineered barrier mainly for inhibiting migration of radioactive nuclides. Hydrogen gas can be generated inside the engineered barrier by anaerobic corrosion of metals used for containers, etc. If the gas generation rate exceeds the diffusion rate of gas molecules inside of the engineered barrier, gas will accumulate in the void space inside of the engineered barrier until its pressure becomes large enough for it to enter the bentonite as a discrete gaseous phase. It is expected to be not easy for gas to entering into the bentonite as a discrete gaseous phase because the pore of compacted bentonite is so minute. Therefore it is necessary to investigate the following subjects: a) Effect of the accumulated gas pressure on surrounding objects such as concrete lining, rock mass. b) Effect of gas breakthrough on the barrier function of bentonite. c) Revealing and modeling gas migration mechanism for overcoming the scale effects in laboratory specimen test. Therefore in this study, gas migration tests for compacted and saturated bentonite to investigate and to model the mechanism of gas migration phenomenon. Firstly, the following conclusions were obtained through by the results of the gas migration tests which are conducted in this study: 1) Bubbles appear in the semitransparent drainage tube at first when the total gas is equal to the initial total axial stress or somewhat smaller. By increasing the gas pressure more, breakthrough of gas migration, which is defined as a sudden increase of amount of emission gas, occurred. When the total gas pressure exceeds the initial total axial stress, the total axial stress is always equal to the total gas pressure because specimens shrink in the axial direction with causing the clearance between the end of the specimen and porous metal. 2) Effective gas conductivity after breakthrough of gas migration is times larger than that

Theory and calculation of water distribution in bentonite in a thermal field

International Nuclear Information System (INIS)

Carnahan, C.L.

1988-09-01

Highly compacted bentonite is under consideration for use as a buffer material in geological repositories for high-level radioactive wastes. To assess the suitability of bentonite for this use, it is necessary to be able to predict the rate and spatial extent of water uptake and water distribution in highly compacted bentonite in the presence of thermal gradients. The ''Buffer Mass Test'' (BMT) was conducted by workers in Sweden as part of the Stripa Project. The BMT measured uptake and spatial distributions of water infiltrating annuli of compacted MX-80 sodium bentonite heated from within and surrounded by granite rock; the measurements provided a body of data very valuable for comparison to results of theoretical calculations. Results of experiments on adsorption of water by highly compacted MX-80 bentonite have been reported by workers in Switzerland. The experiments included measurements of heats of immersion and adsorption-desorption isotherms. These measurements provide the basis for prediction of water vapor pressures in equilibrium with bentonite having specified adsorbed water contents at various temperatures. The present work offers a phenomenological description of the processes influencing movement of water in compacted bentonite in the presence of a variable thermal field. The theory is applied to the bentonite buffer-water system in an assumed steady state of heat and mass transport, using critical data derived from the experimental work done in Switzerland. Results of the theory are compared to distributions of absorbed water in buffers observed in the Swedish BMT experiments. 9 refs., 2 figs

Investigation on the effect of seawater to hydraulic property and wetting process of bentonite

International Nuclear Information System (INIS)

Hasegawa, Takuma

2004-01-01

On high-level waste disposal, bentonite is one of the most promising material for buffer and backfill material. The hydraulic properties and wetting process of bentonite are important not only for barrier performance assessment but also for prediction of waste disposal environment, such as resaturation time and thermal distribution. In Japan, we should consider the effect of seawater for bentonite, because radioactive waste will be disposed of in coastal area and in marine sediment where seawater remained. However, it is not enough to understand the effect of seawater. Therefore, experimental study was conducted to investigate the effect of seawater on the hydraulic conductivity and wetting process of bentonite. The effect of seawater on hydraulic conductivity is significant for Na-bentonite, the hydraulic conductivity of Na-bentonite in seawater is one order to magnitude higher than that in distilled water. On the other hand, the hydraulic conductivity of Ca-bentonite is not influenced by seawater. The hydraulic conductivity of bentonite decreases as effective montmorillonite density increases. The effective montmorillonite density is ratio between the weight of montmorillonite and volume of porosity and montmorillonite. The hydraulic conductivity of bentonite is close related to swelling property since the hydraulic conductivity decrease as the swelling pressure increase. Wetting process of compacted bentonite could be evaluated by diffusion phenomena since infiltration rate and change of saturation rate and represented by diffusion equation. The effect of seawater on water diffusivity is significant for Na-type bentonite with low effective montmorillonite density. Except for that condition, the water diffusivity of bentonite is almost constant and is not influenced by effective montmorillonite density and seawater. (author)

Chemical and mineralogical aspects of water-bentonite interaction in nuclear fuel disposal conditions

International Nuclear Information System (INIS)

Melamed, A.; Pitkaenen, P.

1996-01-01

In the field of nuclear fuel disposal, bentonite has been selected as the principal sealing and buffer material for placement around waste canisters, forming both a mechanical and chemical barrier between the radioactive waste and the surrounding ground water. Ion exchange and mineral alteration processes were investigated in a laboratory study of the long-term interaction between compacted Na-bentonite (Volclay MX-80) and ground water solutions, conducted under simulated nuclear fuel disposal conditions. The possible alteration of montmorillonite into illite has been a major object of the mineralogical study. However, no analytical evidence was found, that would indicate the formation of this non-expandable clay type. Apparently, the change of montmorillonite from Na- to Ca-rich was found to be the major alteration process in bentonite. In the water, a concentration decrease in Ca, Mg, and K, and an increase in Na, HCO 3 and SO 4 were recorded. The amount of calcium ions available in the water was considered insufficient to account for the recorded formation of Ca-montmorillonite. It is therefore assumed that the accessory Ca-bearing minerals in bentonite provide the fundamental source of these cations, which exchange with sodium during the alteration process. (38 refs.)

Microbial incidence on copper and titanium embedded in compacted bentonite clay

Energy Technology Data Exchange (ETDEWEB)

Persson, Joergen; Lydmark, Sara; Edlund, Johanna; Paeaejaervi, Anna; Pedersen, Karsten (Microbial Analytics Sweden AB (Sweden))

2011-10-15

The incidence of bacteria on metal surfaces was examined in an experimental setting simulating conditions of the proposed Swedish concept for disposal of spent nuclear fuel. Titanium and copper rods were embedded in compacted bentonite clay saturated with groundwater collected at a depth of 450 m. Bentonite blocks were exposed to an external flux of groundwater with or without added lactate or H{sub 2} for up to 203 days. Bacterial accumulation on metal rods and in the surrounding bentonite was analyzed using real-time quantitative PCR (qPCR), with genetic markers for overall bacterial presence (16S rDNA) as well as specific for sulfate-reducing bacteria (apsA). Clay species composition was analyzed by cloning and sequencing 16S rDNA extracted from the clay. Results suggest limited bacterial accumulation on metal surfaces, amounting to a maximum of approximately 106 apsA copies cm-2, corresponding to a 3.7% coverage of metal surfaces. Bacterial species composition appeared to be a mix of species originating from the bentonite clay and from the added groundwater, including an apparently high proportion of sulfate-reducing bacteria. While titanium surfaces exhibited higher bacterial presence than did copper surfaces, neither the degree of bentonite compaction nor the addition of lactate or H{sub 2} appeared to have any effect on the bacterial incidence on metal surfaces

Microbial incidence on copper and titanium embedded in compacted bentonite clay

International Nuclear Information System (INIS)

Persson, Joergen; Lydmark, Sara; Edlund, Johanna; Paeaejaervi, Anna; Pedersen, Karsten

2011-10-01

The incidence of bacteria on metal surfaces was examined in an experimental setting simulating conditions of the proposed Swedish concept for disposal of spent nuclear fuel. Titanium and copper rods were embedded in compacted bentonite clay saturated with groundwater collected at a depth of 450 m. Bentonite blocks were exposed to an external flux of groundwater with or without added lactate or H 2 for up to 203 days. Bacterial accumulation on metal rods and in the surrounding bentonite was analyzed using real-time quantitative PCR (qPCR), with genetic markers for overall bacterial presence (16S rDNA) as well as specific for sulfate-reducing bacteria (apsA). Clay species composition was analyzed by cloning and sequencing 16S rDNA extracted from the clay. Results suggest limited bacterial accumulation on metal surfaces, amounting to a maximum of approximately 10 6 apsA copies cm -2 , corresponding to a 3.7% coverage of metal surfaces. Bacterial species composition appeared to be a mix of species originating from the bentonite clay and from the added groundwater, including an apparently high proportion of sulfate-reducing bacteria. While titanium surfaces exhibited higher bacterial presence than did copper surfaces, neither the degree of bentonite compaction nor the addition of lactate or H 2 appeared to have any effect on the bacterial incidence on metal surfaces

Modelling interaction of deep groundwaters with bentonite and radionuclide speciation

International Nuclear Information System (INIS)

Wanner, H.

1986-04-01

In the safety analysis recently reported for a potential Swiss high-level waste repository, radionuclide speciation and solubility limits are calculated for expected granitic groundwater conditions. With the objective of deriving a more realistic description of radionuclide release from the near-field, an investigation has been initiated to quantitatively specify the chemistry of the near-field. In the Swiss case, the main components of the near-field are the glass waste-matrix, a thick steel canister horizontally emplaced in a drift, and a backfill of highly compacted sodium bentonite. This report describes a thermodynamic model which is used to estimate the chemical composition of the pore water in compacted sodium bentonite. Solubility limits and speciation of important actinides and the fission product technetium in the bentonite pore water are then calculated. The model is based on available experimental data on the interaction of sodium bentonite and groundwater and represents means of extrapolation from laboratory data to repository conditions. The basic reactions between sodium bentonite and groundwater are described by an ion-exchange model for sodium, potassium, magnesium, and calcium. The model assumes equilibrium with calcite as long as sufficient carbonates remain in the bentonite, as well as quartz saturation. It is calculated that the pore water of compacted sodium bentonite saturated with Swiss Reference Groundwater will have a pH value of 9.7 and a free carbonate activity of 8x10 -4 M. The long-term situation is modelled by the assumption that the near-field of a deep repository behaves like a mixing tank. In this way, an attempt is made to account for the continuous water exchange between the near-field and the host rock. It is found that sodium bentonite will be slowly converted to calcium bentonite. This conversion is roughly estimated to be completed after 2 million years

Diffusion and sorption properties of radionuclides in compacted bentonite

Energy Technology Data Exchange (ETDEWEB)

Yu Ji-Wei; Neretnieks, I. [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Chemical Engineering and Technology

1997-07-01

In this report, recent studies on sorption and diffusion of radionuclides in compacted bentonite have been reviewed. The sorption distribution coefficient and diffusion coefficient data obtained from experiments in the literature have been compiled. Based on these experimental data and the report SKB-TR--91-16 (Brandberg and Skagius, 1991), this report proposes a set of sorption distribution coefficient and diffusion coefficient values for modelling purpose for safety analysis of nuclear waste repositories. The variability and uncertainty of the diffusivity data span somewhat more than an order or magnitude up and down. Most of the nuclides have an effective diffusivity in around 10{sup -10} m{sup 2}/s. Ion exclusion effects are observed for C, Cl and for Tc in oxidizing waters. Effective diffusivities are nearly tow orders of magnitude lower for these elements and of the order of 10{sup -12} m{sup 2}/s. Surface diffusion effects are found for Cs, Ni, Pa, Pb, Ra, Sn, Sr and Zr. Effective diffusivities for these elements are of the order of 10{sup -8} m{sup 2}/s. The surface diffusion effect should decrease in saline waters which is seen for Cs and Sr where there are data available. It is also deemed that Ra will have this effect because of its similarity with Sr. The other nuclides should also show this decrease but no data is available. Sorption and diffusion mechanisms in compacted bentonite are discussed in the report. In highly compacted bentonite, sorption and hence its distribution coefficient is not well defined, and a pore diffusion coefficient or a surface diffusion coefficient is not well defined either. Therefore, an apparent diffusion coefficient and a total concentration gradient should be more relevant in describing the diffusion process in compacted bentonite. 99 refs.

Compaction of bentonite blocks. Development of technique for industrial production of blocks which are manageable by man

Energy Technology Data Exchange (ETDEWEB)

Johannesson, L E; Boergesson, L; Sanden, T [Clay Technology AB, Lund (Sweden)

1995-04-01

In this report a useful technique for producing compacted blocks of bentonite is described. The report only deals with the technique to produce uniaxially compacted blocks (weight of the blocks: 10-15 kg) which are manageable by man. Tests for producing blocks with a weight of approximately 10 kg were carried out at Hoeganaes Bjuf AB in Bjuf. This industry is normally producing refractory bricks and other refractory products. The plant has facilities for handling large volumes of clay. Furthermore there are machines suitable for producing uniaxially compacted blocks. Performed tests at the plant show that it is possible to compact blocks with good quality. Best quality was reached with a coarsely ground bentonite at a water ratio of 20 %. The compaction was performed with lubricated form and stepwise loading. The tests at Hoeganaes Bjuf AB were preceded by tests in the laboratory. In these tests smaller samples were compacted for studying how different factors affect the quality of the samples (density, water ratio, homogeneity et cetera). The influence of following factors was studied: water ratio of bentonite; bentonite type and granulometry; compaction pressure; compaction rate; form geometry; form lubrication; form heating. The results from these tests were used to modify and optimize the technique in the factory.

Thermodynamic data of water on smectite surface and those applications to swelling pressure of compacted bentonite

International Nuclear Information System (INIS)

Sato, H.

2009-01-01

Swelling pressure was discussed focusing on the thermodynamic properties of water on smectite (montmorillonite) which is the major clay mineral constituent of the bentonite buffer. The thermodynamic data of the water on the smectite surface were obtained as a function of water content and temperature in a range of dry density 0.6-0.9 Mg/m 3 . Purified Na-smectite of which all interlayer cations were exchanged with Na+ ions, was used. The activity (a H 2 O ) and the relative partial molar Gibbs free energy (ΔG H 2 O ) of the water were obtained at 25 C. Both a H 2 O and ΔG H 2 O decreased with a decrease of water content, and similar results were obtained to data reported for montmorillonite (Kunipia-F bentonite). Since the specific surface area of smectite is about 800 m 2 /g, water up to approximately 2 water layers from smectite surface is thermodynamically evaluated to be bound. Swelling pressure versus smectite partial density was calculated based on ΔG H 2 O and compared to data experimentally obtained for various kinds of bentonites. The calculated results were in good agreement with the measured data over the range of smectite partial density between 1.0 and 2.0 Mg/m 3 . (author)

Development and validation of mechanical model for saturated/unsaturated bentonite buffer

International Nuclear Information System (INIS)

Yamamoto, S.; Komine, H.; Kato, S.

2010-01-01

Document available in extended abstract form only. Development and validation of mechanical models for bentonite buffer and backfill materials are one of important subjects to appropriately evaluate long term behaviour or condition of the EBS in radioactive waste disposal. The Barcelona Basic Model (BBM), which is one of extensions of the modified Cam-Clay model for unsaturated and expansive soil, has been developed and widely applied to several problems by using the coupled THM code, Code B right. Advantage of the model is that mechanical characteristics of buffer and backfill materials under not only saturated condition but also unsaturated one are taken account as well as swelling characteristics due to wetting. In this study the BBM is compared with already existing experimental data and already developed another model in terms of swelling characteristics of Japanese bentonite Kunigel-V1, and is validated in terms of consolidation characteristics based on newly performed controlled-suction oedometer tests for the Kunigel-V1 bentonite. Komine et al. (2003) have proposed a model (set of equations) for predicting swelling characteristics based on the diffuse double layer concept and the van der Waals force concept etc. They performed a lot of swelling deformation tests of bentonite and sand-bentonite mixture to confirm the applicability of the model. The BBM well agrees with the model proposed by Komine et al. and the experimental data in terms of swelling characteristics. Compression index and swelling index depending on suction are introduced in the BBM. Controlled-suction consolidation tests (oedometer tests) were performed to confirm the applicability of the suction dependent indexes to unsaturated bentonite. Compacted bentonite with initial dry density of 1.0 Mg/m 3 was tested. Constant suction, 80 kPa, 280 kPa and 480 kPa was applied and kept during the consolidation tests. Applicability of the BBM to consolidation and swelling behaviour of saturated and

Thermal conductivity of compacted bentonite as a buffer material for a high-level radioactive waste repository

International Nuclear Information System (INIS)

Lee, Jae Owan; Choi, Heuijoo; Lee, Jong Youl

2016-01-01

Highlights: • The thermal conductivities were measured under various disposal conditions. • They were significantly influenced by the water content and dry density. • They were not sensitive to the temperature and the anisotropic structure. • A new model of thermal conductivity was proposed for the thermal analysis. - Abstract: Bentonite buffer is one of the major barrier components of a high-level radioactive waste (HLW) repository, and the thermal conductivity of the bentonite buffer is a key parameter for the thermal performance assessment of the HLW repository. This study measured the thermal conductivity of compacted bentonite as a buffer material and investigated its dependence upon various disposal conditions: the dry density, water content, anisotropic structure of the compacted bentonite, and temperature. The measurement results showed that the thermal conductivity was significantly influenced by the water content and dry density of the compacted bentonite, while there was not a significant variation with respect to the temperature. The anisotropy of the thermal conductivity had a negligible variation for an increasing dry density. The present study also proposed a geometric mean model of thermal conductivity which best fits the experimental data.

Diffusion of uranium in compacted sodium bentonite

International Nuclear Information System (INIS)

Muurinen, A.; Lehikoinen, J.

1992-09-01

In the study the diffusion of uranium dissolved from uranium oxide fuel was studied experimentally in compacted sodium bentonite (Wyoming bentonite MX-80). The experiments were carried out by the through-diffusion method. The parameters varied in the study were the density of bentonite, salt content of the solution and redox conditions. Uranium was dissolved under aerobic conditions in order to simulate oxic conditions possibly caused by radiolysis in the repository

Diffusion mechanisms of strontium, cesium and cobalt in compacted sodium bentonite

International Nuclear Information System (INIS)

Muurinen, A.; Rantanen, J.; Penttilae-Hiltunen, P.

1986-01-01

For a porous water-saturated material where diffusion in the porewater, sorption on the solid material and diffusion of the sorbed ions (surface diffusion) occur, a diffusion equation can be derived where the apparent diffusivity includes two terms. One represents diffusion in the pore-water, the other surface diffusion. In this research diffusion mechanisms were studied. The apparent diffusivities of strontium, cesium and cobalt in compacted sodium bentonite were measured by a non-steady state method. The sorption factors were adjusted using different sodium chloride solutions, groundwater and addition of EDTA for saturation of the bentonite samples. The corresponding sorption factors were measured by a batch method. The results suggest that cations diffuse also while being sorbed. A combined pore diffusion-surface diffusion model has been used to explain the transport and the corresponding diffusivities have been evaluated. The surface diffusivities (D/sub s/) of Sr and Cs were 8-9 x 10 -12 m 2 /s and 4-7 x 10 -13 m 2 /s respectively. The pore diffusivity epsilon D/sub p/ of Cs was 3.5 x 10 -11 m 2 /s which has been used also for Sr. The sorption mechanisms of Co seems to be different from that of Sr or Cs and the results allow no specific conclusions of the diffusion mechanisms of Co. The apparent diffusivity of Co ranged from 2 x 10 -14 to 7 x 10 -14 m 2 /s. The anionic Co-EDTA seems to follow some other diffusion mechanism than the cations

Compaction of full size blocks of bentonite for the KBS-3 concept. Initial tests for evaluating the technique

International Nuclear Information System (INIS)

Johanesson, Lars-Erik

1999-12-01

Besides the test with the compaction device several other pieces of equipment were tested for the mixing of the bentonite with water, filling of the form with bentonite and lifting of the blocks. The tests of the equipment turned out well. Furthermore the density of the compacted bentonite was in parity with the expected. The compacted blocks had grooves and flanges in order to facilitate the emplacement of the blocks. Unacceptable damages and cracks close to the flanges were observed on the blocks with low water ratio. As a consequence of these damages it is recommended that the form is modified so that blocks with plane surfaces can be made

Mobility and survival of sulphate-reducing bacteria in compacted and fully water saturated bentonite - microstructural aspects

Energy Technology Data Exchange (ETDEWEB)

Pusch, R. [Geodevelopment AB, Lund (Sweden)

1999-12-01

Sulphate-reducing bacteria will not be able to enter MX-80 buffer clay with the intended bulk density, i.e. 1900-2100 kg/m{sup 3}. Nor will they be able to survive and migrate in such environment. The only circumstances under which sulphate-reducing bacteria can enter, survive and migrate in engineered soil barriers in a KBS-3-type repository are those prevailing in backfills with lower MX-80 contents than about 10 % or in more smectite-rich, poorly compacted backfills saturated with electrolyte-rich pore water with Ca as dominating cation. In the phase of hydration and expansion of canister-embedding buffer, bacteria can enter the initially very soft clay gel at the rock/buffer contact to a depth of about a centimeter.

Mobility and survival of sulphate-reducing bacteria in compacted and fully water saturated bentonite - microstructural aspects

International Nuclear Information System (INIS)

Pusch, R.

1999-12-01

Sulphate-reducing bacteria will not be able to enter MX-80 buffer clay with the intended bulk density, i.e. 1900-2100 kg/m 3 . Nor will they be able to survive and migrate in such environment. The only circumstances under which sulphate-reducing bacteria can enter, survive and migrate in engineered soil barriers in a KBS-3-type repository are those prevailing in backfills with lower MX-80 contents than about 10 % or in more smectite-rich, poorly compacted backfills saturated with electrolyte-rich pore water with Ca as dominating cation. In the phase of hydration and expansion of canister-embedding buffer, bacteria can enter the initially very soft clay gel at the rock/buffer contact to a depth of about a centimeter

Corrosion of carbon steel in contact with bentonite

International Nuclear Information System (INIS)

Dobrev, D.; Vokal, A.; Bruha, P.

2010-01-01

Document available in extended abstract form only. Carbon steel canisters were chosen in a number of disposal concepts as reference material for disposal canisters. The corrosion rates of carbon steels in water solution both in aerobic and anaerobic conditions are well known, but only scarce data are available for corrosion behaviour of carbon steels in contact with bentonite. A special apparatus, which enables to measure corrosion rate of carbon steels under conditions simulating conditions in a repository, namely in contact with bentonite under high pressure and elevated temperatures was therefore prepared to study: - Corrosion rate of carbon steels in direct contact with bentonite in comparison with corrosion rate of carbon steels in synthetic bentonite pore water. - Influence of corrosion products on bentonite. The apparatus is composed of corrosion chamber containing a carbon steel disc in direct contact with compacted bentonite. Synthetic granitic water is above compacted bentonite under high pressure (50 - 100 bar) to simulate hydrostatic pressure in a repository. The experiments can be carried out under various temperatures. Bentonites used for experiments were Na-type of bentonite Volclay KWK 80 - 20 and Ca-Mg Czech bentonite from deposit Rokle. Before adding water into corrosion system the corrosion chamber was purged by nitrogen gas. The saturation of bentonite and corrosion rate were monitored by measuring consumption of water, pressure increase caused by swelling pressure of bentonite and by generation of hydrogen. Corrosion rate was also determined after corrosion experiments from weight loss of samples. The results of experiments show that the corrosion behaviour of carbon steels in contact with bentonite is very different from corrosion of carbon steels in water simulating bentonite pore water solution. The corrosion rates of carbon steel in contact with bentonite reached after 30 days of corrosion the values approaching 40 mm/yr contrary to values

Pre-study on cementation processes in bentonite buffer under uneven saturation and temperature gradient

International Nuclear Information System (INIS)

Jaervinen, Joonas; Muurinen, Arto; Tanhua-Tyrkkoe, Merja

2012-01-01

Document available in extended abstract form only. Under final disposal conditions the uneven and slow saturation together with heat from the canister can lead to a situation where water vaporizes in certain areas in bentonite. The evaporation of ion rich water leads to enrichment of ions and precipitation of the components which may e.g. cement montmorillonite layers together and cause some changes in the bentonite properties. To study the cementation in bentonite buffer under uneven and slow saturation conditions the experimental setup was pre-modelled, constructed and tested. The experimental setups consist of a cylindrical cell (d:100 mm and h:100 mm), adsorption cells, heating system, hydration system, cooling system, sensors and a data acquisition system. A schematic drawing of the experimental equipment is presented in Figure 1. In the cell the hydration end of the bentonite was covered only partly by the sinter and the access of water to bentonite was thus limited. The cell was also equipped with holes in the upper part of the cylinder to allow the water vapour to escape from the cell. The released water vapour is collected on an adsorption material in the adsorption cells. Thermal and hydrological properties of the experimental system were pre-modelled in 2D by using TOUGH2, version 2.0. The aim of the model was to see if the planned experimental set-up leads to the wanted conditions, within reasonable time and to find justifiable parameters for experimental setup. An eleven months long pre-experiment was carried out to get preliminary understanding how the experimental arrangement works. After the experiment the cell was dismantled and water content, bulk density, CEC, exchangeable cations, poorly crystalline iron oxides and silicates, chloride, sulphate and carbonate were analysed and pH measured. The low water content and high chloride concentration next to the heater indicated movement of chloride ions from the hydration surface towards the heater and

Diffusion of strongly sorbing cations (60Co and 152Eu) in compacted Febex bentonite

International Nuclear Information System (INIS)

Garcia-Gutierrez, M.; Missana, T.; Alonso, U.; Mingarro, M.; Cormenzana, J.L.

2010-01-01

tablets. The apparent diffusion coefficient (Da) can be obtained analysing the tracer concentration profile in the samples at the end of the experiment. FEBEX bentonite was compacted, at 1.65 g/cm 3 of dry density (the density considered in the Spanish reference concept for radioactive waste repositories in granite and clay), in cylindrical stainless-steel rings of 38 mm in diameter and 25 mm of length. A filter paper with the tracer was placed between two rings with the compacted clay and the system was closed with two end-pieces and two sintered filters. The diffusion cells were introduced in a vessel to avoid humidity loss. Synthetic water simulating the pore water composition at 1.65 g/cm 3 was used for bentonite saturation. Three experiments with each tracer ( 60 Co 1.0.10 -8 M and 152 Eu 3.9.10 -8 M) were performed. The experiments lasted 843 and 852 days, for 60 Co and 152 Eu respectively, time enough to obtain an evolved profile. At the end of the experiments, the cell is disassembled, the bentonite is sliced and the tracer activity is measured directly in each slice to obtain the tracer concentration profile within the compacted sample. As both tracers used are gamma emitters, a Packard Cobra II auto-gamma counter was used to measure the samples activity. The experimental results were modelled using the analytical solution for the instantaneous injection of a solute in a one-dimensional (1D) semi-infinite medium. A stochastic 1D model with GoldSim 9.60 computer code was additionally used to analyze the role of the paper filter in which the tracer was spiked in the calculations. The range of values for the apparent diffusion coefficients, D a , obtained with the analytical and numerical solution are D a (Co) = (1-3).10 -13 m 2 /s and D a (Eu) (1-2).10 -14 m 2 /s. Always the first slice fit better with the lower value. The filter paper or instantaneous plane source is therefore, a simple and useful method to determine apparent diffusion coefficients for sorbing

Strength and Permeability Evolution of Compressed Bentonite in Response to Salinity and Temperature Changes

Science.gov (United States)

Winnard, B. R.; Mitchell, T. M.; Browning, J.; Cuss, R. J.; Norris, S.; Meredith, P. G.

2017-12-01

Deep geological repositories are the preferred solution to dispose of radioactive waste; design concepts for these disposal facilities include compacted, saturated bentonite as a buffer between waste canister and host rock. Bentonite is favoured for its high swelling capacity, low permeability, and radionuclide retention properties. However, its thermo-hydro-mechanical tolerances must be thoroughly tested to ensure adequate long term performance. Climate variations are likely to induce periods of permafrost, and consequently, changes in groundwater salinity at depth. We performed laboratory experiments investigating effects of temperature and salinity change on uniaxial compressive strength (UCS), and permeability of compacted MX-80 bentonite cylinders. These specimens (moisture content = 22.9±0.1%, dry density = 1.66±0.02 g.cm-3) were compacted with deionised water, and a range of wt% NaCl, CaCl2, or KCl, to compare the effects of compaction fluid. Samples of compressed bentonite were cooled to -20 °C, and heated to 90 ºC, a possible temperature forecast for a repository dependent on factors such as geographical location, waste type, and facility design. Tests were all performed at room temperature, however in situ temperature tests are planned. The UCS of samples that experienced freeze thaw, and 40 ºC treatment failed at 6.5 MPa, with 4% strain, maintaining the same values as untreated bentonite compacted with deionised water. Samples compacted with saline solutions also yielded similar strengths, of 7 MPa, and failed at 4%. However, the 90 ºC, regardless of compaction fluid, failed at 15-18 MPa, at just 2% strain. In all experiments, the spread of strain accommodated varied inconsistently, however, peak stress was uniform. Further experiments into heterogeneity are needed to understand the responsible mechanisms. To obtain permeability, we utilised the pore pressure oscillation (PPO) technique with argon as the pore fluid. We also tested water as the pore

Isostatic compaction of beaker shaped bentonite blocks on the scale 1:4

Energy Technology Data Exchange (ETDEWEB)

Johannesson, Lars-Erik [Clay Technology AB, Lund (Sweden); Nord, Sven [Ifoe Ceramics AB, Bromoella (Sweden ); Pusch, Roland [Geodevelopment AB, Lund (Sweden); Sjoeblom, Rolf [AaF-Energikonsult AB, Stockholm (Sweden)

2000-09-01

The purpose of the present work is to test, on a scale of 1:4, the feasibility of manufacturing bentonite blocks by isostatic compaction for application as a buffer material in a repository for spent nuclear fuel. In order for the tests to be sensitive to any weaknesses of the method, the blocks were shaped as beakers. The scope included the following: 1. Preparation of powder: a. mixing of the bentonite and addition of water in predetermined amounts, b. sieving to remove any lumps generated; 2. Isostatic compaction: a. establishment of a separate laboratory for the handling of bentonite powder (weighing, mixing, filling, sampling and machining), b. development and design of equipment and procedures for compaction of bentonite to beaker-shaped specimens, c. compaction process operation, d. visual inspection; 3. Sampling and characterisation: a. extraction of samples from the blocks made, b. determination of water content, c. determination of density, d. determination of strain at maximum stress by means of bending tests, e. determination of tensile strength by means of bending tests, f. determination of geometries of the blocks prepared; 4. Post-treatment by means of machining: a. machining of blocks made, b. visual inspection; 5. Evaluation. The work went very smoothly. No significant obstacles or unexpected events were encountered. The conclusions are as follows: The conclusions drawn in this report from work on the (linear)scale of one to four are very relevant to the full scale. Mixing of bentonite powder as well as moistening can be carried out on a pilot scale with a good homogeneity and with maintained good quality of the press powder. The compaction of bentonite can be carried out in a similar manner to the present operation at Ifoe Ceramics AB. This implies a very efficient handling as well as a very efficient use of the time in the press which may account for a large proportion of the total cost. The blocks could readily be produced to reproducible

Experimental evaluation of the hydraulic resistance of compacted bentonite/boom clay interface

International Nuclear Information System (INIS)

Tang, Anh-Minh; Cui, Yu-Jun; Delage, Pierre; Munoz, Juan Jorge; Li, Xiang-Ling

2008-01-01

In the framework of the in-situ PRACLAY Heater experiment to be performed in the HADES URF in Mol (Belgium), the feasibility of a hydraulic cut-off of the Excavation Damaged Zone (EDZ) and the Repository Components (RC) of the disposal galleries by using a horizontal seal will be examined. It has been planned to install an annular seal composed of compacted bentonite between the heated zone and the access gallery (PRACLAY seal test), so that to avoid any hydraulic shortcut towards the access gallery. According to numerical scoping calculations, heating until 80 deg C will induce a pore pressure of the order of 3.0 MPa. In order to verify the effects of this water pressure on the performance of the annular seal system and more specifically on the hydraulic resistance of the interface between the compacted bentonite and the host rock (Boom clay), laboratory percolation tests at 20 and 80 deg C were performed. The results confirm the performance of the compacted bentonite seal to avoid the hydraulic shortcut to the access gallery under the foreseen hydraulic and thermal conditions. (author)

Physical changes in MX-80 bentonite saturated under thermal gradient

International Nuclear Information System (INIS)

Villar, Maria Victoria; Gomez-Espina, Roberto; Gutierrez-Nebot, Luis; Campos, Rocio; Barrios, Iciar

2012-01-01

Document available in extended abstract form only. This study was developed in the framework of the Temperature Buffer Test (TBT project), which was a full-scale test for HLW disposal that aimed at improving the understanding of the thermo-hydro-mechanical (THM) behaviour of buffers with a temperature around and above 100 deg. C during the water saturation transient. The French organisation ANDRA run this test at the Aespoe HRL in cooperation with SKB (Svensk Kaernbraenslehantering AB 2005). To simulate the conditions of the field test in the laboratory, 20-cm high columns of MX80 bentonite compacted at dry density 1.70 g/cm 3 with an initial water content of 16 percent were submitted in thermo-hydraulic cells to heating and hydration by opposite ends for different periods of time (TH test). The temperature at the bottom of the columns was set at 140 deg. C and on top at 30 C, and deionised water was injected on top at a pressure of 0.01 MPa. The tests were running for 337, 496 and 1510 days. Upon dismantling water content, dry density, specific surface area, porosity and basal spacings, among others, were determined in different positions along the bentonite columns. The strong gradients developed are remarkable. In the shorter tests the water content decreased below the initial value in the 7 cm closest to the heater, whereas in the longer test the decrease below the initial value took place only in the 5 cm closest to the heater. In the remaining part of the columns the water content increased with respect to the initial value, particularly so in the longest test. The dry density along the bentonite changed accordingly, decreasing in the hydrated areas below the initial value and increasing near the heater. The decrease in dry density is due to the swelling of the bentonite upon saturation, while the dry density increase results from the combination of two processes: the compression of the dry areas exerted by the hydrated bentonite, and the shrinkage due to the

Soil-water characteristics of Gaomiaozi bentonite by vapour equilibrium technique

Directory of Open Access Journals (Sweden)

Wenjing Sun

2014-02-01

Full Text Available Soil-water characteristics of Gaomiaozi (GMZ Ca-bentonite at high suctions (3–287 MPa are measured by vapour equilibrium technique. The soil-water retention curve (SWRC of samples with the same initial compaction states is obtained in drying and wetting process. At high suctions, the hysteresis behaviour is not obvious in relationship between water content and suction, while the opposite holds between degree of saturation and suction. The suction variation can change its water retention behaviour and void ratio. Moreover, changes of void ratio can bring about changes in degree of saturation. Therefore, the total change in degree of saturation includes changes caused by suction and that by void ratio. In the space of degree of saturation and suction, the SWRC at constant void ratio shifts to the direction of higher suctions with decreasing void ratio. However, the relationship between water content and suction is less affected by changes of void ratio. The degree of saturation decreases approximately linearly with increasing void ratio at a constant suction. Moreover, the slope of the line decreases with increasing suction and they show an approximately linear relationship in semi-logarithmical scale. From this linear relationship, the variation of degree of saturation caused by the change in void ratio can be obtained. Correspondingly, SWRC at a constant void ratio can be determined from SWRC at different void ratios.

Compaction of bentonite blocks. Development of techniques for production of blocks with different shapes and sizes

International Nuclear Information System (INIS)

Johannesson, Lars-Erik; Boergesson, Lennart

1998-09-01

In this report useful techniques for producing both smaller blocks manageable by man (10-15 kg) and larger blocks which need special equipment for handling (weight up to 600 kg) are described. Tests for producing blocks with a weight of approximately 10 kg were carried out at Hoeganaes Bjuf AB in Bjuv. This industry is normally producing refractory bricks and other refractory products. The plant has facilities for handling large volumes of clay. It also has machines suitable for producing uniaxially compacted blocks. Tests performed at the plant show that it is possible to compact blocks with good quality. The best quality was reached with a coarsely ground bentonite at a water ratio of 17 %. The compaction rate was high and performed with lubricated form and stepwise loading. Tests, in order to find a technique for producing larger blocks with a diameter of the same size as a deposition hole (about 1.65 m), were also made. The technique was developed in a smaller scale (250 mm). Ring-shaped blocks with the same outer diameter and with an inner diameter of about 156 mm were also compacted. The compaction was made with vacuum in the form. The outer surface of the form was conical and most of the tests were performed with a lubricated form. Tests were performed with different water ratios of the bentonite. All the blocks had a good quality. In consequence of the good test results a form with a 1000 mm diameter was constructed and a number of compaction tests were performed. The same technique was used as for the smaller blocks. The compaction pressure in most tests was 100 MPa (maximum compaction load 80.000 kN). The tests were performed at HYDROWELD in Ystad in a press with a maximum capacity of 300.000 kN. All tests were performed with MX-80. Most of the blocks had a good quality. A small damage close to the upper surface of all blocks was observed but is considered to be of no importance for the possibility to handle the blocks and is not affecting the properties

Compaction of bentonite blocks. Development of techniques for production of blocks with different shapes and sizes

Energy Technology Data Exchange (ETDEWEB)

Johannesson, Lars-Erik; Boergesson, Lennart [Clay Technology AB, Lund (Sweden)

1998-09-01

In this report useful techniques for producing both smaller blocks manageable by man (10-15 kg) and larger blocks which need special equipment for handling (weight up to 600 kg) are described. Tests for producing blocks with a weight of approximately 10 kg were carried out at Hoeganaes Bjuf AB in Bjuv. This industry is normally producing refractory bricks and other refractory products. The plant has facilities for handling large volumes of clay. It also has machines suitable for producing uniaxially compacted blocks. Tests performed at the plant show that it is possible to compact blocks with good quality. The best quality was reached with a coarsely ground bentonite at a water ratio of 17 %. The compaction rate was high and performed with lubricated form and stepwise loading. Tests, in order to find a technique for producing larger blocks with a diameter of the same size as a deposition hole (about 1.65 m), were also made. The technique was developed in a smaller scale (250 mm). Ring-shaped blocks with the same outer diameter and with an inner diameter of about 156 mm were also compacted. The compaction was made with vacuum in the form. The outer surface of the form was conical and most of the tests were performed with a lubricated form. Tests were performed with different water ratios of the bentonite. All the blocks had a good quality. In consequence of the good test results a form with a 1000 mm diameter was constructed and a number of compaction tests were performed. The same technique was used as for the smaller blocks. The compaction pressure in most tests was 100 MPa (maximum compaction load 80.000 kN). The tests were performed at HYDROWELD in Ystad in a press with a maximum capacity of 300.000 kN. All tests were performed with MX-80. Most of the blocks had a good quality. A small damage close to the upper surface of all blocks was observed but is considered to be of no importance for the possibility to handle the blocks and is not affecting the properties

Influence of material and solution composition on the extrusion/erosion behaviour of compacted bentonite

International Nuclear Information System (INIS)

Schatz, Timothy; Martikainen, Jari; Koskinen, Kari

2010-01-01

experiments, total material mass loss through a compacted material/porous frit/solution reservoir interface was measured as a function of time. The effect of material and solution composition on extruded mass loss was analysed using combinations of compacted, homo-ionised bentonite (Ca-, Na-, Mg-Mt and admixtures thereof) and aqueous solutions of interest (from deionised water to high salinity concentrations). In some cases, measurements of stable colloid concentrations, above the distinct gel/sol phase boundary, were performed as well. Additionally, mechanical effects on mass extrusion were also analysed by varying both the porosity and the length of the interface. Results from these experiments indicate that the extrusion of compacted buffer mass is a self-limiting, diffusion-controlled process. These observations are in accordance with a view that ascribes the driving force of the extrusion process to swelling pressure with resistance provided by the viscosity of the extruded material and friction with the fracture surface. Moreover, material and solution composition effects on the rate of mass loss were clearly observed as well. Additionally, the mass fraction of spontaneously generated colloids, relative to the total extruded mass, was small to negligible for every measured case. As with the overall rate of mass loss, there were also clear material and solution composition effects on the magnitude of the measured colloidal mass fractions. (authors)

Removal of oil from water by bentonite

International Nuclear Information System (INIS)

Moazed, H.; Viraraghavan, T.

1999-01-01

Many materials, included activated carbon, peat, coal, fiberglass, polypropylene, organoclay and bentonite have been used for removing oils and grease from water. However, bentonite has been used only rarely for this purpose. In this study Na-bentonite was used to remove oil from oil-in-water emulsions of various kinds such as standard mineral oil, cutting oils, refinery effluent and produced water from production wells at Estevan, Saskatchewan. Removal efficiencies obtained were 85 to 96 per cent for cutting oils, 84 to 86 per cent for produced water and 54 to 87 per cent for refinery effluent. Bentonite proved to be more effective in the removal of oil from oil-in-water emulsions than from actual waste waters; up to 96 percent from oil-in-water emulsions to only 87 per cent from actual waste water. The percentage of oil removed was found to be a function of the amount of bentonite added and the adsorption time up to the equilibrium time. Result also showed that the Langmuir, Freundlich and BET isotherms are well suited to describe the adsorption of oil by bentonite from the various oily waters employed in this study. 15 refs

Strength and Compaction Analysis of Sand-Bentonite-Coal Ash Mixes

Science.gov (United States)

Sobti, Jaskiran; Singh, Sanjay Kumar

2017-08-01

This paper deals with the strength and compaction characteristics of sand-bentonite-coal ash mixes prepared by varying percentages of sand, bentonite and coal ash to be used in cutoff walls and as a liner or cover material in landfills. The maximum dry density (MDD) and optimum moisture content (OMC) of sand-bentonite mixes and sand-bentonite-coal ash mixes were determined by conducting the standard proctor test. Also, the strength and stiffness characteristics of soil mixes were furnished using unconfined compressive strength test. The results of the study reveal influence of varying percentages of coal ash and bentonite on the compaction characteristics of the sand-bentonite-coal ash mixes. Also, validation of a statistical analysis of the correlations between maximum dry density (MDD), optimum moisture content (OMC) and Specific Gravity (G) was done using the experimental results. The experimental results obtained for sand-bentonite, sand-bentonite-ash and coal ash-bentonite mixes very well satisfied the statistical relations between MDD, OMC and G with a maximum error in the estimate of MDD being within ±1 kN/m3. The coefficient of determination (R2) ranged from 0.95 to 0.967 in case of sand-bentonite-ash mixes. However, for sand-bentonite mixes, the R2 values are low and varied from 0.48 to 0.56.

Fabrication and handling of bentonite blocks

International Nuclear Information System (INIS)

1978-06-01

In accordance with the project for the final storage of spent nuclear fuel, the waste will be encapsulated into copper canisters, which will be deposited in a final repository located in rock 500 m below ground level. The canisters will be placed in vertical holes in the bottoms of the tunnels, where the copper cylinders will be surrounded by blocks of highly compacted bentonite. When the blocks are saturated with water and expansion is essentially retained as in the actual case, a very high swelling pressure will arise. The bentonite will be extremely impermeable and thus it will form a barrier against transport of corrosive matters to the canister. The blocks are fabricated by means of cold isostatic pressing of bentonite powder. The base material in the form of powder is enclosed in flexible forms, which are introduced into pressure vessels where the forms are surrounded by oil or water. Thus the powder is compacted into rigid bodies with a bulk density of about 2.2 t/m 3 for ''air dry'' bentonite, which might be compared with a specific density of about 2.7 t/m 3 . The placing of a canister is preceded by piling up bentonite blocks to a level just below the canister lid position, after which the slot around the blocks is filled with bentonite powder. The rest of the blocks are mounted after filling bentonite powder into the inner slot around the canister as well. Finally the storage tunnels will be sealed by filling them with a mixture o02067NRM 0000181 45

Influence of temperature, exchangeable cation composition, salinity and density in the adsorption of water by a bentonite: implications to the pore water composition

International Nuclear Information System (INIS)

Fernandez, A.M.; Melon, A.M.

2010-01-01

Document available in extended abstract form only. Compacted bentonites are being considered in many countries as a sealing material in high-level radioactive waste disposal (HLW) concepts because of their low permeability, high swelling capacity and high plasticity. In this context, the knowledge of the pore water composition in bentonites is an uncertainty associated to the retention and transport processes through highly compacted material. The nature of the pore water directly affects how the radionuclides are transported through the buffer materials because of a potential distribution is developed at the solid-liquid interface. Besides, the moisture potential of bentonites is closely related to swelling pressure. The pore water chemistry depends on the hydration and swelling of bentonites (matric and osmotic potentials), and therefore on the distribution of the external and the interlayer water. This relationship depends, in turn, on parameters such as water content, bulk dry density, temperature, type of cations at interlayers and salinity. The osmotic potential is related to the dissolved salt content and increases with pore water salinity. It is well-known that variations in pore water osmotic suction affect osmotic repulsion pressure caused by the diffuse double layers interactions of adjacent particles as both are functions of dissolved salt concentration in pore water. In this work, the moisture potential has been analysed as a function of the water content, temperature (20, 30 and 60 deg. C), type of cations at interlayers, salinity and degree of compaction of the FEBEX bentonite. The aim was to analyse the hydration of this bentonite, and the types and distribution of water as a function of these parameters, since both the Cl-accessible porosity (key parameter for transport processes) and the amount of internal (interlayer)/external water depend strongly on the ionic strength of the saturating solution, the composition at interlayers and the

Can the water content of highly compacted bentonite be increased by applying a high water pressure?

International Nuclear Information System (INIS)

Pusch, R.; Kasbohm, J.

2001-10-01

A great many laboratory investigations have shown that the water uptake in highly compacted MX-80 clay takes place by diffusion at low external pressure. It means that wetting of the clay buffer in the deposition holes of a KBS-3 repository is very slow if the water pressure is low and that complete water saturation can take several tens of years if the initial degree of water saturation of the buffer clay and the ability of the rock to give off water are low. It has therefore been asked whether injection of water can raise the degree of water saturation and if a high water pressure in the nearfield can have the same effect. The present report describes attempts to moisten highly compacted blocks of MX-80 clay with a dry density of 1510 kg/m 3 by injecting water under a pressure of 650 kPa through a perforated injection pipe for 3 and 20 minutes, respectively. The interpretation was made by determining the water content of a number of samples located at different distances from the pipe. An attempt to interpret the pattern of distribution of injected uranium acetate solution showed that the channels into which the solution went became closed in a few minutes and that dispersion in the homogenized clay gave low U-concentrations. The result was that the water content increased from about 9 to about 11-12 % within a distance of about 1 centimeter from the injection pipe and to slightly more than 9 % at a distance of about 4-5 cm almost independently of the injection time. Complete water saturation corresponds to a water content of about 30 % and the wetting effect was hence small from a practical point of view. By use of microstructural models it can be shown that injected water enters only the widest channels that remain after the compaction and that these channels are quickly closed by expansion of the hydrating surrounding clay. Part of the particles that are thereby released become transported by the flowing water and cause clogging of the channels, which is

Bentonite erosion by dilute waters in initially saturated bentonite

International Nuclear Information System (INIS)

Olin, Markus; Seppaelae, Anniina; Laurila, Teemu; Koskinen, Kari

2012-01-01

Document available in extended abstract form only. One scenario of interest for the long-term safety assessment of a spent nuclear fuel repository involves the loss of bentonite buffer material through contact with dilute groundwater at a transmissive fracture interface (SKB 2011, Posiva 2012a). The scenario is based on the stable colloids at low ionic strength: - the cohesive forces of bentonite decrease in low-salinity conditions, and colloids start to dominate and are able to leave the gel-like bentonite on the groundwater bentonite boundary; - after colloid formation, groundwater may carry away the only just released clay colloids; - low-salinity events are most probable during post-glacial conditions, when also pressure gradients are high, causing elevated flow velocity, which may enhance colloidal transport. Therefore, it is very important from the point of view of repository safety assessment to be able to estimate how much bentonite may be lost during a post-glacial event, when the groundwater salinity and velocity, as well as the duration of the event are fixed. It is possible that more than one event will hit the same canister and buffer, and that several canisters and buffers may be jeopardized. The results in the issue so far may be divided into modelling attempts and experimental work. The modelling has been based on two main guidelines: external (Birgersson et al., 2009) and internal friction models (Neretnieks et al., 2009). However, these models have not been validated for erosion, probably due to lack of suitable laboratory data. The latter approach is more ambitious due to lack of fitting parameters, though the internal friction model itself may be varied. The internal friction model has proven to be time-consuming to solve numerically. This work indicates that experiments carried out by Schatz et al. (2012) differ significantly from the predictions obtained from Neretnieks' model. We present our numerical modelling results based on a set of

Functioning of blocks of compacted bentonite in a repository for spent nuclear fuels

International Nuclear Information System (INIS)

Boergesson, Lennart; Kalbantner, P.; Sjoeblom, R.

2001-12-01

The main purpose of the presented work is to provide The Swedish Nuclear Fuel and Waste Management Company (SKB) with a proposed set of requirements regarding the functioning of the blocks of compacted bentonite. These blocks are intended to constitute the bentonite envelope which after uptake of water will form the buffer between the canister and the rock. The purpose is also to provide a basis for SKB for their direction of the continued development work for the selection of a reference technology and for creating a quality system for the buffer material. No attempts are made in the report to derive the functional requirements. Instead, such requirements are postulated based on realistic scenarios regarding the chain of processes from excavation - transport - preparation of press powder - compaction - handling and emplacement in the deposition hole. It is the strategy of SKB to use a natural material which after the above-mentioned processes forms a buffer with properties which closely resemble those of the original material. This implies that all process steps must be designed in such a way that the properties of the bentonite do not change to any significant degree with respect to the disposal function. The main results in the report are as follows: A set of functional requirements are compiled and presented. These concord with the different descriptions given on the process steps. The requirements are generic and are assessed to be relatively invariant for various operational requirements and process controls. The process chain comprising excavation of bentonite - transport - preparation of press powder - compaction - handling and emplacement are explained. The presentations of functional requirements and processes are foreseen to constitute a basis for a comparison between uniaxial and isostatic compaction and can be an important basis for SKB's quality work. The development of cracks in the bentonite blocks has been identified as an important aspect for the

Limits to the use of highly compacted bentonite as a deterrent for microbiologically influenced corrosion in a nuclear fuel waste repository

Science.gov (United States)

Stroes-Gascoyne, Simcha; Hamon, Connie J.; Maak, Peter

Recent studies have suggested that microbial activity in highly compacted bentonite (⩾1600 kg/m 3) is severely suppressed. Therefore, it appears that the dry density of emplaced bentonite barriers in a geological repository for nuclear waste may be tailored such that a microbiologically unfavorable environment can be created adjacent to used fuel containers. This would ensure that microbiologically influenced corrosion is a negligible contributor to the overall corrosion process. However, this premise is valid only as long as the emplaced bentonite maintains a uniform high dry density (⩾1600 kg/m 3) because it has been shown that high dry density only suppresses microbial activity but not necessarily eliminates the viable microbial population in bentonite. In a repository, a reduction in the dry density of highly compacted bentonite may occur at a number of interface locations, such as placement gaps, contact regions with materials of different densities and contact points with water-carrying fractures in the rock. Experiments were carried out in our laboratory to examine the effects of a reduction in dry density (from 1600 kg/m 3 to about 1000 kg/m 3) on the recovery of microbial culturability in compacted bentonite. Results showed that upon expansion of compacted bentonite into a void, the resulting reduction in dry density stimulated or restored culturability of indigenous microbes. In a repository this would increase the possibility of in situ activity, which might be detrimental for the longevity of waste containers. Reductions in dry density, therefore, should be minimized or eliminated by adequate design and placement methods of compacted bentonite. Materials compliance models can be used to determine the required as-placed dry densities of bentonite buffer and gap fillings to achieve specific targets for long-term equilibrium dry densities for various container placement room designs. Locations where flowing fractures could be in contact with highly

Diffusion of organic colloids in compacted bentonite. The influence of ionic strength on molecular size and transport capacity of the colloids

International Nuclear Information System (INIS)

Wold, S.; Eriksen, Trygve E.

2000-09-01

Diffusion of radionuclides in compacted bentonite can be affected by inorganic and organic colloids if the radionuclides form complexes with the colloids. Formation and mobility of the colloid-radionuclide complexes will be governed by the properties of the colloids as well as the competition between complexation and sorption of the radionuclides on bentonite. This report presents the results of experiments with organic colloids humic acid (HA) and lignosulfonate (LS). The aim of the experiments has been to describe the HA and LS properties: size distribution, acidity, sorption on bentonite, diffusivity in compacted bentonite, complexation with strontium, and diffusion of strontium in bentonite in the presence of HA. This study indicates that the diffusion of cationic radionuclides like Sr 2+ is not affected by the presence of HA in high ionic strength solution. In 0.1 M NaClO 4 solution, HA is most probably not available for complexation due to coiling and shielding of the negative sites

Limits to the use of highly compacted bentonite as a deterrent for microbially influenced corrosion in a nuclear fuel waste repository

International Nuclear Information System (INIS)

Stroes-Gascoyne, Simcha; Hamon, Connie J.; Maak, Peter

2010-01-01

Highly compacted bentonite-based sealing materials are being developed for use in future geological repositories for nuclear fuel waste. Such materials would ensure a diffusion-controlled hydrology and additionally form a sorption barrier against radionuclide migration after container breach. Due to some inherent physical characteristics, such as low water activity (a w ), small pores and high swelling pressure, an additional role of highly compacted bentonite may be the elimination of significant microbial activity near used fuel containers, which would reduce the occurrence of microbially influenced corrosion (MIC) to insignificant levels. Several recent studies have examined the indigenous microbial populations in compacted bentonite and the factors that control microbial activity in such environments. Laboratory experiments with Wyoming MX-80 bentonite plugs, compacted to dry densities (DD's) of 0.8 to 2.0 g/cm 3 , and infiltrated with sterile distilled deionised water were carried out. At DD's of 0.8 and 1.3 g/cm 3 , culturability of heterotrophic aerobic bacteria increased by up to four orders of magnitude above back-ground levels. Anaerobic heterotrophic bacteria and SRB did not increase significantly above background levels in any of the tests. At higher DD's all culturability remained at, or fell below, the background levels. However, even at the highest DD tested, some culturability remained and viability was only mildly affected by high DD's. Therefore, the potential for increased microbial activity exist if a substantial reduction in DD of bentonite were to occur in a repository. The microbes that survive in dry as-purchased or highly compacted bentonite appear to be largely spore-forming organisms. Chi Fru and Athar (2008) studied the bacterial colonization of compacted MX-80 bentonite from the surrounding granitic groundwater population, at various temperature ranges. Results suggested that high temperature rather than high DD

Diffusion behavior for Se and Zr in sodium-bentonite

International Nuclear Information System (INIS)

Sato, Haruo; Yui, Mikazu; Yoshikawa, Hideki

1995-01-01

Apparent diffusion coefficients for Se and Zr in bentonite were measured by in-diffusion method at room temperature using water-saturated sodium-bentonite, Kunigel V1 reg-sign containing 50wt% Na-smectite as a major mineral was used as the bentonite material. The experiments were carried out in the dry density range of 400--1,800 kg/m 3 . Bentonite samples were immersed with distilled water and saturated before the experiments. The experiments for Se were carried out under N 2 atmospheric condition (O 2 : 2.5ppm). Those for Zr were carried out under aerobic condition. The apparent diffusion coefficients decrease with increasing density of the bentonite. Since dominant species of Se in the pore water is predicted to be SeO 3 2- , Se may be retarded by anion-exclusion because of negative charge on the surface of the bentonite and little sorption. The dominant species of Zr in the porewater is predicted to be Zr(OH) 5 - or HZrO 3 - . Distribution coefficient measured for Zr on the bentonite was about 1.0 m 3 /kg from batch experiments. Therefore, the retardation may be caused by combination of the sorption and the anion-exclusion. A modeling for the diffusion mechanisms in the bentonite were discussed based on an electric double layer theory. Comparison between the apparent diffusion coefficients predicted by the model and the measured ones shows a good agreement

Study on GMZ bentonite-sand mixture by undrained triaxial tests

Directory of Open Access Journals (Sweden)

Sun Wen-jing

2016-01-01

Full Text Available It is particularly necessary to study the deformation, strength and the changes of pore water pressure of bentonite-based buffer/backfill materials under the undrained condition. A series of isotropic compression tests and triaxial shear tests under undrained conditions were conducted on the compacted saturated/unsaturated GMZ bentonite-sand mixtures with dry mass ratio of bentonite/sand of 30:70. During the tests, the images of the sample were collected by photographic equipment and subsequently were cropped, binarized and centroids marked by image processing technique. Based on identification of the variation of the position of marked centroids, the deformation of the sample can be determined automatically in real-time. Finally, the hydro-mechanical behaviour of saturated and unsaturated bentonite-sand mixtures under the undrained condition can be obtained. From results of triaxial shear tests on unsaturated samples under constant water content, inflated volumetric deformation transforms to contractive volumetric deformation due to the increase of the confining pressure and lateral expansion deformation are observed due to the increase in the shearing stress. Moreover, the net mean stress affects the initial stiffness, undrained shear strength and deformation of the sample during the undrained shear tests.

Microstructural modifications induced by hydraulic and mechanical actions on compacted bentonite

International Nuclear Information System (INIS)

Romero, E.; Suriol, J.; Lloret, A.; Castellanos, E.; Villar, M.V.

2010-01-01

consequence of the constant volume condition during wetting, inter-granular porosity is reduced, tending to its occlusion. Due to limitations of the method, the evolution of the intra-aggregate pore size mode cannot be registered, but it is expected to increase on wetting. The inter-aggregate mode that emerges due to saturation reaches systematic higher peaks on wetting under constant load paths, in which the swelling strains are higher than the small strains imposed under isochoric conditions. The changes due to wetting are more evident in samples with lower density. - Heating of compacted bentonite at 150 deg. C causes a certain decrease in the size of intra-aggregate pores and small changes in the inter-aggregate and inter-platelet pore domains. A systematic observation of some specimens that were used in the MIP was performed by means of an environmental scanning electron microscope (ESEM). Although the observations mainly provide qualitative information, the use of this technique is of interest to enhance the knowledge of the structure changes due to wetting and drying paths. In the context of the study of swelling clay behaviour the most relevant feature of the ESEM devices is the possibility of changing the relative humidity of the microscope chamber in order to change the total suction of clay. This possibility allows visualizing the structural changes in bentonite associated to the changes in water content. Nevertheless, it is necessary to take into account that during the observation, the samples are not confined, which makes difficult to observe the occlusion of inter-granular pores due to the expansion of clay aggregates. Measurements of volume changes in ESEM photomicrographs were calculated using digital imaging techniques. Some of the conclusions reached in this study are: - The consolidated slurries posses a uniform and homogeneous structure (matrix structure), in which peds are not clearly distinguished and the pore size distribution presents a clear mode for

Water uptake and motion in highly densified bentonite

International Nuclear Information System (INIS)

Kahr, G.; Mueller-Vonmoos, F.; Kraehenbuehl, F.; Stoeckli, H.F.

1986-07-01

Water uptake by the bentonites MX-80 and Montigel was investigated according to the classical method of determination of the heat immersion and the adsorption-desorption isotherms. In addition, the layer expansion of the montmorillonite was measured as a function of the water content. The evaluation of the adsorption isotherms according to Dubinin-Radushkevich and the stratification distances determined by x-ray confirmed gradual water uptake. Up to 10% water content, the water is adsorbed as a monolayer, up to 20%, as a bimolecular layer around the interlayer cations. The partial specific entropy could be determined from the approximative calculation of the partial specific enthalpy from the heats of immersion and the free enthalpy from the adsorption isotherms. From this it is evident that the interlayer water shows a high degree of order. In this condition, the mobility of the water molecules is considerably lower than in free water. From the adsorption isotherm and the layer expansion observed, it can be assumed that water can appear in the pore space only from approximately 25% water content. The spaces outwith the interlayer space and the surfaces of the montmorillonite particles are considered as pore space. If free swelling is prevented and with dry densities greater than 1.8 Mg/m/sup 3/ for the highly compacted bentonites, water uptake causes a drastic reduction of the original pore space so that practically all the water is in the interlayer space. Calculation of the swelling pressure from the adsorption isotherms gives a good approximation of the measured swelling pressures. A montmorillonite surface of ca. 750 m/sup 2//g for both bentonites can be derived from a Dubinin-Radushkevich analysis of the adsorption isotherm. Water uptake into the compacted unsaturated bentonites can be described as diffusion with a diffusion coefficient of the order of magnitude of 3.10/sup -10/ m/sup 2//s. (author)

Coupled behaviour of bentonite buffer results of PUSKURI project

International Nuclear Information System (INIS)

Olin, M.; Rasilainen, K.; Itaelae, A.

2011-08-01

In the report main results form a KYT2010 programme's project Coupled behaviour of bentonite buffer (PUSKURI) are presented. In THC modelling, Aku Itaelae made and published his Master of Science Thesis. Itaelae was able to successfully model the LOT-experiment. Additionally, he also listed problems and development proposals for THC-modelling of bentonite buffer. VTT and Numerola created in collaboration a model coupling saturation, diffusion and cation exchange; the model was implemented and tested in Numerrin, COMSOL and TOUGHREACT. Petri Jussila's PhD THM-model was implemented into COMSOL to facilitate further development. At GTK, the mineralogical characterisation of bentonite was planned. The previous THM model (Jussila's model) including only small deformations was successfully generalized to finite deformations in way at least formally preserving the original formalism. It appears that the theory allows also a possibility to include finite plastic deformations in the theory. In order to measure the relevant mechanical properties of compacted bentonite, two different experiments, namely hydrostatic compression experiment and one-dimensional compression experiment were designed. In the hydrostatic compression experiment, a cylindrical sample of compacted bentonite covered with liquid rubber coating is placed in the sample chamber equipped with a piston. The same device was also used in one-dimensional compression experiment. X-ray microtomographic techniques were used in order to study the basic mechanisms of water transport in bentonite. The preliminary results indicate that in the present experimental set-up, water transport is dominated by a dispersive mechanism such as diffusion of vapour in gas phase or diffusion of water in solid phase. (orig.)

Diffusion of Fission Product Elements in Compacted Bentonite

International Nuclear Information System (INIS)

Pratomo-Budiman-Sastrowardoyo; Dewi-Susilowati; Dadang-Suganda

2000-01-01

Study on diffusion of fission product in compacted bentonite has been conducted. The information about mobilities of these elements have been obtained from the studies resulted in many countries. It is presented that the diffusion coefficient was varied by the function of solution phase condition as well as the nature of bentonite. It is also showed that the diffusion coefficient decreased by the increasing of density, as well as the increasing of montmorillonite content in bentonite. The ratio of bentonite/silica-sand used, was related to the increasing of elements mobility. In many case variation of diffusion coefficient was related to the variation of pH, redox condition, and the presence of complex ant in solution phase. The lower diffusion coefficient could give the higher retardation factor, which is a favorable factor to retard the radionuclides release from a disposal facility to geosphere. (author)

Fe-bentonite. Experiments and modelling of the interactions of bentonites with iron

Energy Technology Data Exchange (ETDEWEB)

Herbert, Horst-Juergen; Xie, Mingliang [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Koeln (Germany); Kasbohm, Joern; Lan, Nguyen T. [Greifswald Univ. (Germany); Hoang Thi Minh Thao [Hanoi Univ. of Science (Viet Nam)

2011-11-15

The main objectives of this study were to enhance the understanding of the interactions of bentonites with steel containers in the near field of a repository in salt formations and to determine missing experimental thermo-hydraulical-chemical and mineralogical data needed for the THC modelling of the interactions of bentonites with iron. At the beginning of this project a literature review helped to clarify the state of the art regarding the above mentioned objectives prior to the start of the experimental work. In the following experimental programme the hydraulic changes in the pore space of compacted MX80 bentonites containing metallic iron powder and in contact with three solutions of different ionic strength containing different concentrations of Fe{sup 2+} have been investigated. The alterations of MX80 and several other bentonites have been assessed in contact with the low ionic strength Opalinus Clay Pore Water (OCPW) and the saturated salt solutions NaCl solution and IP21 solution. Under repository relevant boundary conditions we determined on compacted MX80 samples with the raw density of 1.6 g/cm{sup 3} simultaneously interdependent properties like swelling pressures, hydraulic parameters (permeabilities and porosities), mineralogical data (changes of the smectite composition and iron corrosion products), transport parameters (diffusion coefficients) and thermal data (temperature dependent reaction progresses). The information and data resulting from the experiments have been used in geochemical modelling calculations and the existing possibilities and limitations to simulate these very complex near field processes were demonstrated. The main conclusion of this study is that the alteration of bentonites in contact with iron is accentuated and accelerated. Alterations in contact with solutions of different ionic strength identified by the authors in previous studies were found be much more intensive in contact with metallic iron and at elevated

Effect of Heating/Hydratation on Compacted Bentonite: Tests in 60-cm Long Cells

Energy Technology Data Exchange (ETDEWEB)

Villar, M. V.; Fernandez, A. M.; Martin, P. L.; Barcala, J. M.; Gomez-Espina, R.; Rivas, P.

2008-07-01

The conditions of the bentonite in an engineered barrier for high-level radioactive waste disposal have been simulated in a series of tests. Cylindrical cells with an inner length of 60 cm and a diameter of 7 cm were constructed. Inside the cells, blocks of compacted FEBEX bentonite were put one on top of the other. the bottom surface of the material was heated at 100 degree centigree and the top surface was injected with granitic water. the duration of the tests was 0.5, 1,2 and 7,6 years. The temperatures and water intake were measured during the tests and, at the end, the cells were dismounted and the dry density, water content, mineralogy, geochemistry and some hydro-mechanical properties of the clay (permeability, swelling) were measured at different positions. the values obtained are compared among them and to those of the untreated FEBEX bentonite. The study has run over for 10 years in the context of the projects FEBEX I and II and NF-PRO. (Author) 50 refs.

Effect of Heating/Hydratation on Compacted Bentonite: Tests in 60-cm Long Cells

International Nuclear Information System (INIS)

Villar, M. V.; Fernandez, A. M.; Martin, P. L.; Barcala, J. M.; Gomez-Espina, R.; Rivas, P.

2008-01-01

The conditions of the bentonite in an engineered barrier for high-level radioactive waste disposal have been simulated in a series of tests. Cylindrical cells with an inner length of 60 cm and a diameter of 7 cm were constructed. Inside the cells, blocks of compacted FEBEX bentonite were put one on top of the other. the bottom surface of the material was heated at 100 degree centigree and the top surface was injected with granitic water. the duration of the tests was 0.5, 1,2 and 7,6 years. The temperatures and water intake were measured during the tests and, at the end, the cells were dismounted and the dry density, water content, mineralogy, geochemistry and some hydro-mechanical properties of the clay (permeability, swelling) were measured at different positions. the values obtained are compared among them and to those of the untreated FEBEX bentonite. The study has run over for 10 years in the context of the projects FEBEX I and II and NF-PRO. (Author) 50 refs

Microstructure and anisotropic swelling behaviour of compacted bentonite/sand mixture

Directory of Open Access Journals (Sweden)

Simona Saba

2014-04-01

Full Text Available Pre-compacted elements (disks, torus of bentonite/sand mixture are candidate materials for sealing plugs of radioactive waste disposal. Choice of this material is mainly based on its swelling capacity allowing all gaps in the system to be sealed, and on its low permeability. When emplaced in the gallery, these elements will start to absorb water from the host rock and swell. Thereby, a swelling pressure will develop in the radial direction against the host rock and in the axial direction against the support structure. In this work, the swelling pressure of a small scale compacted disk of bentonite and sand was experimentally studied in both radial and axial directions. Different swelling kinetics were identified for different dry densities and along different directions. As a rule, the swelling pressure starts increasing quickly, reaches a peak value, decreases a little and finally stabilises. For some dry densities, higher peaks were observed in the radial direction than in the axial direction. The presence of peaks is related to the microstructure change and to the collapse of macro-pores. In parallel to the mechanical tests, microstructure investigation at the sample scale was conducted using microfocus X-ray computed tomography (μCT. Image observation showed a denser structure in the centre and a looser one in the border, which was also confirmed by image analysis. This structure heterogeneity in the radial direction and the occurrence of macro-pores close to the radial boundary of the sample can explain the large peaks observed in the radial swelling pressure evolution. Another interesting result is the higher anisotropy found at lower bentonite dry densities, which was also analysed by means of μCT observation of a sample at low bentonite dry density after the end of test. It was found that the macro-pores, especially those between sand grains, were not filled by swelled bentonite, which preserved the anisotropic microstructure caused by

Sealing performance assessments of bentonite and bentonite/crushed rock plugs

International Nuclear Information System (INIS)

Ouyang, Shoung.

1990-01-01

Bentonite and mixtures of bentonite and crushed rock are potential sealing materials for high level nuclear waste repositories. The materials have been used to form cap layers to reduce infiltration for mined waste tailings and can also be used to construct clay liners for municipal as well as industrial waste managements. American Colloid C/S granular dentonite and Apache Leap tuff have been mixed to prepare samples for laboratory flow testing. Bentonite weight percent and crushed tuff gradation are the major variables studied. The sealing performance assessments include high injection pressure flow tests, polyaxial flow tests, high temperature flow tests, and piping tests. The results indicate that an appropriate composition would have at least 25% bentonite by weight mixed with well-graded crushed rock. Hydraulic properties of the mixture plugs may be highly anisotropic if significant particle segregation occurs during sample installation and compaction. Temperature has no negative effects on the sealing performance within the test range from room temperature to 60C. The piping damage to the sealing performance is small if the maximum hydraulic gradient does not exceed 120 and 280 for 25 and 35% bentonite content, respectively. The hydraulic gradients above which flow of bentonite may take place are deemed critical. Analytical work includes the introduction of bentonite occupancy percentage and water content at saturation as two major parameters for the plug design. A permeability model developed is useful for the prediction of permeability in clays. A piping model permits the estimation of critical hydraulic gradient allowed before the flow of bentonite takes place. It can also be used to define the maximum allowable pore diameter of a protective filter layer

Bentonite swelling pressure in strong NaCl solutions. Correlation between model calculations and experimentally determined data

International Nuclear Information System (INIS)

Karnland, O.

1997-12-01

A number of quite different quantitative models concerning swelling pressure in bentonite clay have been proposed by different researchers over the years. The present report examines some of the models which possibly may be used also for saline conditions. A discrepancy between calculated and measured values was noticed for all models at brine conditions. In general the models predicted a too low swelling pressure compared to what was experimentally found. An osmotic component in the clay/water system is proposed in order to improve the previous conservative use of the thermodynamic model. Calculations of this osmotic component is proposed to be made by use of the clay cation exchange capacity and Donnan equilibrium. Calculations made by this approach showed considerably better correlation to literature laboratory data, compared to calculations made by the previous conservative use of the thermodynamic model. A few verifying laboratory tests were made and are briefly described in the report. The improved thermodynamic model predicts substantial bentonite swelling pressures also in saturated sodium chloride solution if the density of the system is high enough. In practice, the model predicts a substantial swelling pressure for the buffer in a KBS-3 repository if the system is exposed to brines, but the positive effects of mixing bentonite into a backfill material will be lost, since the available compaction technique does not give a sufficiently high bentonite density

Dustiness behaviour of loose and compacted Bentonite and organoclay powders: What is the difference in exposure risk?

International Nuclear Information System (INIS)

Jensen, Keld Alstrup; Koponen, Ismo Kalevi; Clausen, Per Axel; Schneider, Thomas

2009-01-01

Single-drop and rotating drum dustiness testing was used to investigate the dustiness of loose and compacted montmorillonite (Bentonite) and an organoclay (Nanofil 5), which had been modified from montmorillonite-rich Bentonite. The dustiness was analysed based on filter measurements as well as particle size distributions, the particle generation rate, and the total number of generated particles. Particle monitoring was completed using a TSI Fast Mobility Particle Sizer (FMPS) and a TSI Aerosol Particle Sizer (APS) at 1 s resolution. Low-pressure uniaxial powder compaction of the starting materials showed a logarithmic compaction curve and samples subjected to 3.5 kg/cm 2 were used for dustiness testing to evaluate the role of powder compaction, which could occur in powders from large shipments or high-volume storage facilities. The dustiness tests showed intermediate dustiness indices (1,077-2,077 mg/kg powder) in tests of Nanofil 5, Bentonite, and compacted Bentonite, while a high-level dustiness index was found for compacted Nanofil 5 (3,487 mg/kg powder). All powders produced multimodal particle size-distributions in the dust cloud with one mode around 300 nm (Bentonite) or 400 nm (Nanofil 5) as well as one (Nanofil 5) or two modes (Bentonite) with peaks between 1 and 2.5 μm. The dust release was found to occur either as a burst (loose Bentonite and Nanofil 5), constant rate (compacted Nanofil 5), or slowly increasing rate (compacted Bentonite). In rotating drum experiments, the number of particles generated in the FMPS and APS size-ranges were in general agreement with the mass-based dustiness index, but the same order was not observed in the single-drop tests. Compaction of Bentonite reduced the number of generated particles with app. 70 and 40% during single-drop and rotating drum dustiness tests, respectively. Compaction of Nanofil 5 reduced the dustiness in the single-drop test, but it was more than doubled in the rotating drum test. Physically relevant

The coupled process laboratory test of highly compacted bentonite

International Nuclear Information System (INIS)

Shen Zhenyao; Li Guoding; Li Shushen; Wang Chengzu

2004-01-01

Highly compacted bentonite blocks have been heated and hydrated in the laboratory in order to simulate the thermo-hydro-mechanical (THM) coupled processes of buffer material in a high-level radioactive waste (HLW) repository. The experiment facility, which is composed of experiment barrel, heated system, high pressure water input system, temperature measure system, water content measure system and swelling stress system, is introduced in this paper. The steps of the THM coupled experiment are also given out in detail. There are total 10 highly compacted bentonite blocks used in this test. Experimental number 1-4 are the tests with the heater and the hydrated process, which temperature distribution vs. time and final moisture distribution are measured. Experimental number 5-8 are the tests with the heater and without the hydrated process, which temperature distribution vs. time and final moisture distribution are measured. Experimental number 9-10 are the tests with the heater and the hydrated process, which temperature distribution vs. time, final moisture distribution and the swelling stress distribution at some typical points vs. time are measured. The maximum test time is nearly 20 days and the minimum test time is only 8 hours. The results show that the temperature field is little affected by hydration process and stress condition, but moisture transport and stress distribution are a little affected by the thermal gradient. The results also show that the water head difference is the mainly driving force of hydration process and the swelling stress is mainly from hydration process. It will great help to understand better about heat and mass transfer in porous media and the THM coupled process in actual HLW disposal. (author)

Modelling interaction of deep groundwaters with bentonite and radionuclide speciation

International Nuclear Information System (INIS)

Wanner, H.

1986-04-01

In the safety analysis recently reported for a potential Swiss high-level waste repository, radionuclide speciation and solubility limits are calculated for expected granitic groundwater conditions. This report describes a thermodynamic model which is used to estimate the chemical composition of the pore water in compacted sodium bentonite. The model is based on available experimental data and describes the basic reactions between bentonite and groundwater by an ion-exchange model for sodium, potassium, magnesium, and calcium. The model assumes equilibrium with calcite as long as sufficient carbonates remain in the bentonite, as well as quartz saturation. The long-term situation is modelled by the assumption that the near-field of a deep repository behaves like a mixing tank. It is found that sodium bentonite will slowly be converted to calcium bentonite. The modelled composition of the pore water of compacted sodium bentonite is used to estimate radionuclide solubilities in the near-field of a deep repository. The elements considered are: uranium, neptunium, plutonium, thorium, americium, and technetium. The redox potential in the near-field is assumed to be controlled by the corrosion products of the iron canister. Except for uranium and neptunium, radionuclide solubilities turn out to be lower under the modelled near-field conditions than in the groundwater of the surrounding granitic host rock. Uranium and neptunium solubility might be higher by orders of magnitude in the near-field than in the far-field. From the chemical point of view, calcium bentonite seems to be more stable than sodium bentonite in the presence of Swiss Reference Groundwater. The use of calcium bentonite instead of sodium bentonite will improve the reliability in the prediction of source terms for radionuclide transport in the geosphere. (author)

Migration study of actinides and lanthanides in compacted bentonite

International Nuclear Information System (INIS)

Sastrowardoyo, P.B.; Susilowati, D.; Suganda, D.

1998-01-01

Migration study of actinide and lanthanide elements in compacted bentonite has been conducted. Data of these elements mobilities have been shown, and it is showed that the diffusion coefficient was varied as the function of solution phase condition as well as the origin/composition of bentonite. It is showed that the diffusion coefficient decreased by the increasing of density, as well as the increasing of montmorillonite content in bentonite. The ratio of bentonite/silica-sand used was related to the increasing of elements mobility. In many case the difference of diffusion coefficient was related to the variation of pH and redox condition, as well as the presence of complexant in solution phase. The Lower diffusion coefficient could give the higher retardation factor, which is a favourable factor to retard the radionuclides release from a disposal facility to geosphere. (author)

Diffusion of I{sup -}, Cs{sup +}, and Sr{sup 2+} in compacted bentonite - Anion exclusion and surface diffusion

Energy Technology Data Exchange (ETDEWEB)

Eriksen, T.E.; Jansson, Mats [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Nuclear Chemistry

1996-11-01

The diffusion of I, Cs and Sr ions in bentonite compacted to a dry density of 1.8 gr/cm{sup 3} and saturated with two groundwaters of different ionic strength have been studied experimentally using the through diffusion technique. The I{sup -} diffusivity and diffusion porosity were found to be concentration independent in the concentration range exp(-8) to exp(-2) mol/dm{sup 3}. The diffusion porosity, being only a fraction of the water porosity for normal groundwaters, is strongly ionic strength dependent due to anion exclusion. The dependence of the diffusion of Cs{sup +} and Sr{sup 2+} on the sorption intensity is accommodated by a model encompassing diffusion of the sorbed cations within the electrical double layer next to the mineral surface in addition to diffusion in the pore water. 18 refs, 12 figs.

Diffusion of Radionuclides in Bentonite Clay - Laboratory and in situ Studies

International Nuclear Information System (INIS)

Jansson, Mats

2002-12-01

This thesis deals with the diffusion of ions in compacted bentonite clay. Laboratory experiments were performed to examine in detail different processes that affect the diffusion. To demonstrate that the results obtained from the laboratory investigations are valid under in situ conditions, two different kinds of in situ experiments were performed. Laboratory experiments were performed to better understand the impact of ionic strength on the diffusion of S 2+ and Cs + ions, which sorb to mineral surfaces primarily by ion exchange. Furthermore, surface related diffusion was examined and demonstrated to take place for Sr 2+ and Cs + but not for Co 2+ , which sorbs on mineral surfaces by complexation. The diffusion of anions in bentonite clay compacted to different dry densities was also investigated. The results indicate that anion diffusion in bentonite clay consists of two processes, one fast and another slower. We ascribe the fast diffusive process to intralayer diffusion and the slow process to diffusion in interparticle water, where anions are to some extent sorbed to edge sites of the montmorillonite. Two different types of in situ experiments were performed, CHEMLAB and LOT. CHEMLAB is a borehole laboratory, where cation (Cs + , Sr 2+ and Co 2+ ) and anion (I- and TcO 4 - ) diffusion experiments were performed using groundwater from a fracture in the borehole. In the LOT experiments cylindrical bentonite blocks surrounding a central copper rod were placed in a 4 m deep vertical borehole. The borehole was then sealed and the blocks are left for 1, 5 or >> 5 years. When the bentonite was water saturated the central copper rod is heated to simulate the temperature increase due to radioactive decay of the spent fuel. Bentonite doped with radioactive Cs and Co was placed in one of the lower blocks. Interestingly, the redox-sensitive pertechnetate ion (TcO 4 - ) which thermodynamically should be reduced and precipitate as TcO 2 n H 2 O, travelled unreduced through

Experimental study on swelling character of statics-compacted bentonite-sand mixture

International Nuclear Information System (INIS)

Cui Suli; Zhang Huyuan; Liu Jisheng; Liang Jian

2010-01-01

In the high-level radioactive waste (HLW) geological disposal projects barrier system, there are two types for constructing buffer/backfill material in preconceived: locale field-pressed and locale-build by prefab lock. Statics-Compacted is needed for both footrill padding in the locale field-pressed and locale-build by prefab lock. Laboratory tests were conducted on statics-compacted mixture of GMZ001 bentonite and quartz sand in different addition. The results obtained indicated that in the semi-log coordinates, the form of the P-time and e-time curves were sigmoid,the same as dynamic-compacted specime. The swelling character of statics-compacted specime were also as well as dynamic-compacted specime, that is with the increase of initial dry density, the maximum swelling pressure were exponential increase and maximum swelling strain increase linearly. These made it clear that the methods of making specime have no effect on the swelling character of bentonite-sand mixture, so methods for constructing buffer/backfill material can be selected free as needed in the construction site. The validity of regression relationship received by dynamic-compacted specime test was verified, and the coefficients for the regression equation were revised in a greater range of initial dry density. Based on the comprehensive analysis of experimental results, it is concluded that addition of 10-30% quartz sand and 1.60-1.80 g/cm 3 for initial dry density to GMZ001 bentonite-sand mixture is suitable for the swelling quality. (authors)

Observations of bentonite-hyper-alkaline fluid and bentonite-cement interactions by the X-ray computed tomography

International Nuclear Information System (INIS)

Nakabayashi, R.; Chino, D.; Kawaragi, C.; Sato, T.; Yoneda, T.; Kaneko, K.; Shibata, S.; Sakamoto, H.

2010-01-01

even though it is a powerful tool to obtain information on chemical distribution with high special resolution. X-ray CT, on the contrary, is a powerful and non-destructive analytical tool to study the micro- and inner-structure of materials and can provide an opportunity to conduct measurement on the same sample at different position and time. Therefore, X-ray CT has a high potential to obtain many images with digital data to trace the alteration process in bentonite-hyper-alkaline fluid and bentonite-cement interactions as a function of time. In this context, the advective alteration experiments for the bentonite column with lower density and diffusive alteration experiments for the compacted bentonite sandwiched by cement pellets were conducted to observe the micro-structural changes in the sampled by X-ray CT. For the advective alteration experiments, Na-bentonite specimens (Kunigel V1) with densities of 0.3 Mg/m 3 and 0.4 Mg/m 3 were used. NaOH solution (pH 13.5) with 0.3 M passed through the bentonite specimens with flow pressure of 0.03 and 0.04 MPa, respectively. The specimens were kept inside the oven at 80 deg. C. The flow-through periods of NaOH solution for bentonite specimens were conducted for 200 days. On the other hand, for diffusive alteration experiments, the compacted Na-type bentonite (Kunigel V1) sandwiched by ordinary portland cement (W/C 0.6) initially immersed in ion-exchange water for 100 days at 50 deg. C. Both of the specimens were observed by X-ray CT every 10 days. For advective alteration experiments, the effluent was periodically collected, and the coefficient of permeability and solution pH were measured. The reacted solid was analyzed by X-ray powder diffraction (XRD) after the experiments were terminated. The concentration of Al in the effluent was determined by using inductively coupled plasma-atomic emission spectroscopy (ICP-AES), while Si concentration was determined as SiO 2 through molybdenum-blue spectrometry. In the case of

Customized bentonite pellets. Manufacturing, performance and gap filling properties

Energy Technology Data Exchange (ETDEWEB)

Marjavaara, P.; Holt, E.; Sjoeblom, V. [VTT Technical Research Centre of Finland, Espoo (Finland)

2013-12-15

The goal of this work was to provide knowledge about how to manufacture customized bentonite pellets and how customized bentonite pellets perform in practice during the nuclear repository construction process. The project was mainly focused on laboratory experimental tests to optimize the pellet filling by customizing the raw materials and pellet manufacturing. Bentonite pellets were made using both extrusion and roller compaction methods. The pellets were intended for use in gaps between compacted bentonite and the rock walls in both buffer deposition holes and tunnel backfilling. Performance of different types of custom-made pellets were evaluated with regard to their ease of manufacturing, density, crush strength, abrasion resistance, water holding capacity, free swelling and also their thermal conductivity. These evaluations were done in both Finland (by VTT) and Canada (by AECL). Over 50 different varieties of pellets were roller-compaction manufactured at AECL in Canada and 20 types of extrusion pellets at VTT in Finland. The parameters that were varied during manufacturing included: bentonite raw material type, water content, pellet sizes, bentonite compaction machine parameters, use of recycled pellets, and addition of two different types of filler (illite or granitic sand) at varying addition percentages. By examining the pellets produced with these methods and materials the performance and behaviour of the bentonite pellets were evaluated in laboratory with selected tests. The work done using extrusion pellets showed that it was possible to manufacture pellets with higher water contents, up to 21 % from MX-80. This water content value was higher than what was typically possible using roller-compaction method in this study. Higher water content values allow closer compatibility with the designed bentonite buffer water content. The extrusion tests also showed that the required production simulation runs could be made successfully with reference type of MX

Bentonite swelling pressure in strong NaCl solutions. Correlation between model calculations and experimentally determined data

Energy Technology Data Exchange (ETDEWEB)

Karnland, O. [Clay Technology, Lund (Sweden)

1997-12-01

A number of quite different quantitative models concerning swelling pressure in bentonite clay have been proposed by different researchers over the years. The present report examines some of the models which possibly may be used also for saline conditions. A discrepancy between calculated and measured values was noticed for all models at brine conditions. In general the models predicted a too low swelling pressure compared to what was experimentally found. An osmotic component in the clay/water system is proposed in order to improve the previous conservative use of the thermodynamic model. Calculations of this osmotic component is proposed to be made by use of the clay cation exchange capacity and Donnan equilibrium. Calculations made by this approach showed considerably better correlation to literature laboratory data, compared to calculations made by the previous conservative use of the thermodynamic model. A few verifying laboratory tests were made and are briefly described in the report. The improved thermodynamic model predicts substantial bentonite swelling pressures also in saturated sodium chloride solution if the density of the system is high enough. In practice, the model predicts a substantial swelling pressure for the buffer in a KBS-3 repository if the system is exposed to brines, but the positive effects of mixing bentonite into a backfill material will be lost, since the available compaction technique does not give a sufficiently high bentonite density 37 refs, 15 figs

Thermo-hydro-geochemical modelling of the bentonite buffer. LOT A2 experiment

Energy Technology Data Exchange (ETDEWEB)

Sena, Clara; Salas, Joaquin; Arcos, David (Amphos 21 Consulting S.L., Barcelona (Spain))

2010-12-15

The Swedish Nuclear Fuel and waste management company (SKB) is conducting a series of long term buffer material (LOT) tests at the Aespoe Hard Rock Laboratory (HRL) to test the behaviour of the bentonite buffer under conditions similar to those expected in a KBS-3 deep geological repository for high level nuclear waste (HLNW). In the present work a numerical model is developed to simulate (i) the thermo-hydraulic, (ii) transport and (iii) geochemical processes that have been observed in the LOT A2 test parcel. The LOT A2 test lasted approximately 6 years, and consists of a 4 m long vertical borehole drilled in diorite rock, from the ground of the Aespoe HRL tunnel. The borehole is composed of a central heater, maintained at 130 deg C in the lower 2 m of the borehole, a copper tube surrounding the heater and a 100 mm thick ring of pre-compacted Wyoming MX-80 bentonite around the copper tube /Karnland et al. 2009/. The numerical model developed here is a 1D axis-symmetric model that simulates the water saturation of the bentonite under a constant thermal gradient; the transport of solutes; and, the geochemical reactions observed in the bentonite blocks. Two cases have been modelled, one considering the highest temperature reached by the bentonite (at 3 m depth in the borehole, where temperatures of 130 and 85 deg C have been recorded near the copper tube and near the granitic host rock, respectively) and the other case assuming a constant temperature of 25 deg C, representing the upper part of borehole, where the bentonite has not been heated. In the LOT A2 test, the initial partially saturated bentonite becomes progressively water saturated, due to the injection of Aespoe granitic groundwater at granite - bentonite interface. The transport of solutes during the bentonite water saturation stage is believed to be controlled by water uptake from the surrounding groundwater to the wetting front and, additionally, in the case of heated bentonite, by a cyclic evaporation

Thermo-hydro-geochemical modelling of the bentonite buffer. LOT A2 experiment

International Nuclear Information System (INIS)

Sena, Clara; Salas, Joaquin; Arcos, David

2010-12-01

The Swedish Nuclear Fuel and waste management company (SKB) is conducting a series of long term buffer material (LOT) tests at the Aespoe Hard Rock Laboratory (HRL) to test the behaviour of the bentonite buffer under conditions similar to those expected in a KBS-3 deep geological repository for high level nuclear waste (HLNW). In the present work a numerical model is developed to simulate (i) the thermo-hydraulic, (ii) transport and (iii) geochemical processes that have been observed in the LOT A2 test parcel. The LOT A2 test lasted approximately 6 years, and consists of a 4 m long vertical borehole drilled in diorite rock, from the ground of the Aespoe HRL tunnel. The borehole is composed of a central heater, maintained at 130 deg C in the lower 2 m of the borehole, a copper tube surrounding the heater and a 100 mm thick ring of pre-compacted Wyoming MX-80 bentonite around the copper tube /Karnland et al. 2009/. The numerical model developed here is a 1D axis-symmetric model that simulates the water saturation of the bentonite under a constant thermal gradient; the transport of solutes; and, the geochemical reactions observed in the bentonite blocks. Two cases have been modelled, one considering the highest temperature reached by the bentonite (at 3 m depth in the borehole, where temperatures of 130 and 85 deg C have been recorded near the copper tube and near the granitic host rock, respectively) and the other case assuming a constant temperature of 25 deg C, representing the upper part of borehole, where the bentonite has not been heated. In the LOT A2 test, the initial partially saturated bentonite becomes progressively water saturated, due to the injection of Aespoe granitic groundwater at granite - bentonite interface. The transport of solutes during the bentonite water saturation stage is believed to be controlled by water uptake from the surrounding groundwater to the wetting front and, additionally, in the case of heated bentonite, by a cyclic evaporation

Stress/strain/time properties of highly compacted bentonite

International Nuclear Information System (INIS)

Pusch, R.

1983-05-01

In this paper, a recently developed creep theory based on statistical mechanics has been used to analyze a number of experimental creep curves, the conclusion being that the creep behavior of dense MX-80 bentonite is in agreement with the physical model, and that the average bond strength is within the hydrogen bond region. The latter conclusion thus indicates that interparticle displacements leading to macroscopic creep takes place in interparticle and intraparticle water lattices. These findings were taken as a justification to apply the creep theory to a prediction of the settlement over a one million year period. It gave an estimated settlement of 1 cm at maximum, which is of no practical significance. The thixotropic and viscous properties of highly compacted bentonite present certain difficulties in the determination and evaluation of the stress/strain/time parameters that are required for ordinary elastic and elasto-plastic analyses. Still, these parameters could be sufficiently well identified to allow for a preliminary estimation of the stresses induced in the metal canisters by slight rock displacements. The analysis, suggests that a 1 cm rapid shear perpendicular to the axes of the canisters can take place without harming them. (author)

Investigation on compression behaviour of highly compacted GMZ01 bentonite with suction and temperature control

International Nuclear Information System (INIS)

Ye, W.M.; Zhang, Y.W.; Chen, B.; Zheng, Z.J.; Chen, Y.G.; Cui, Y.J.

2012-01-01

Highlights: ► Heating induced volumetric change of GMZ01 bentonite depends on suction. ► Suction has significant influence on compressibility. ► Temperature has slight influence on compressibility. - Abstract: In this paper, an oedometer with suction and temperature control was developed. Mechanical compaction tests have been performed on the highly compacted GMZ01 bentonite, which has been recognized as potential buffer/backfill material for construction of Chinese high-level radioactive waste (HLW) geological repository, under conditions of suction ranging from 0 to 110 MPa, temperature from 20 to 80 °C and vertical pressure from 0.1 to 80 MPa. Based on the test results, suction and temperature effects on compressibility parameters are investigated. Results reveal that: (1) at high suctions, heating induced an expansion, while contraction is induced by heating at low suctions. The thermal expansion coefficient of GMZ01 bentonite measured is 1 × 10 −4 °C −1 ; (2) with increasing suction, the elastic compressibility κ and the plastic compressibility λ(s) of the highly compacted GMZ01 bentonite decrease, while the pre-consolidation pressure increases markedly; (3) with increasing temperature, the elastic compressibility of compacted GMZ01 bentonite changes insignificantly, while the plastic compressibility λ(s) slightly decreases and the yield surface tends to shrink.

Modelling bentonite pore waters for the Swiss high-level radioactive waste repository

International Nuclear Information System (INIS)

Curti, E.

1993-11-01

The main objective of this investigation is to contribute to definition of representative compositions of bentonite pore waters in the near-field of the Swiss repository for high-level radioactive waste. Such compositions are necessary for determining the solubility limits of radionuclides for the safety analysis KRISTALLIN I. The model developed here is based on the premise, supported by experimental data, that the composition of bentonite pore waters is largely controlled by the dissolution or precipitation of reactive trace solids in bentonite. Selectivity constants for the exchange equilibria among Na-K, Na-Ca, and Ca-Mg were derived from water-bentonite interaction experiments performed for NAGRA by the British Geological Survey (BGS). An important parameter for the prediction of radionuclide solubilities is the oxidation potential of the bentonite water. Since the BGS experiments yielded no information on this, the oxidation potential had to be estimated from model assumptions. Bentonite pore waters were defined by computer simulation with the geochemical code MINEQL. They have been modelled in a closed system, i.e. assuming the bentonite, once it has reacted with a fixed volume of groundwater, does not exchange further chemical species with an external reservoir. No attempt was made to model the evolution of the pore water by simulating diffusive exchange processes. It can be anticipated that uncertainties in the concentrations of some major elements (e.g. Al, Si) will not significantly affect the calculated radionuclide solubilities. The latter will depend primarily on the concentrations of a few major ligands (OH - , Cl - and CO 3 -2 ) and, for multivalent elements, also on the oxidation potential of the solution. (author) 10 figs., 22 tabs., 40 refs

Bentonite pore structure based on SAXS, chloride exclusion and NMR studies

International Nuclear Information System (INIS)

Muurinen, A.; Carlsson, T.

2013-11-01

Water-saturated bentonite is planned to be used in many countries as an important barrier component in high-level nuclear waste (HLW) repositories. Knowledge about the microstructure of the bentonite and the distribution of water between interlayer and non-interlayer pores is important for modelling of long-term processes. In this work the microstructure of water-saturated samples prepared from Na montmorillonite, Ca-montmorillonite, sodium bentonite MX-80 and calcium bentonite Deponit CaN were studied with nuclear magnetic resonance (NMR) and small-angle xray scattering spectroscopy (SAXS). The sample dry densities ranged between 0.3 and 1.6 g/cm 3 . The NMR technique was used to get information about the volumes of different water types in the bentonite samples. The results were obtained using 1H NMR spin-lattice T 1ρ relaxation time measurements using the short inter-pulse method. The interpretation of the NMR results was made by fitting distributions of exponentials to observed decay curves. The SAXS measurements were used to get information about the size distribution of the interlayer distance of montmorillonite. The chloride porosity measurements and Donnan exclusion calculations were used together with the SAXS results for evaluation of the bentonite microstructure. The NMR studies and SAXS studies coupled with Cl porosity measurements provided very similar pictures of how the porewater is divided in interlayer and non-interlayer water in MX-80 bentonite. In the case where MX-80 of a dry density 1.6 g/cm 3 was equilibrated with 0.1 M NaCl solution, the results indicated an interlayer porosity of 30 % and non-interlayer porosity of 12 %. The interlayer space mainly contained two water layers but also spaces with more water layers were present. The average size of the non-interlayer pores was evaluated to be 120 - 150 A. From the montmorillonite surface area 98 % was interlayer and 2 % non-interlayer. Evaluation of the interlayer and non

Diffusion of 99TcO4- in compacted bentonite: Effect of pH, concentration, density and contact time

International Nuclear Information System (INIS)

Xiangke Wang; Forschungszentrum Karlsruhe; Zuyi Tao

2004-01-01

In order to assess radionuclide diffusion and transport properties in compacted bentonite, the 'in-diffusion' method based on bentonite filled capillaries is used. The effect of 99 TcO 4 - concentration and pH value of the solution, the contact time and the dry density of compacted bentonite on the apparent diffusion coefficient (D a ) and on the distribution coefficient (K d ) values obtained from the capillary test was studied. The D a and K d values decrease with increasing of the bulk dry density of compacted bentonite. Ion exclusion influences the diffusion of 99 TcO 4 - 4 in the same substance. As compared to literature data, the K d values obtained from capillary tests are in most cases lower than those from batch tests, the difference between the two K d values is a strong function of dry density of the compacted bentonite. (author)

Evaluation of permeability of compacted bentonite ground considering heterogeneity by geostatistics

International Nuclear Information System (INIS)

Tanaka, Yukihisa; Nakamura, Kunihiko; Kudo, Kohji; Hironaga, Michihiko; Nakagami, Motonori; Niwase, Kazuhito; Komatsu, Shin-ichi

2007-01-01

The permeability of the bentonite ground as an engineered barrier is possibly designed to the value which is lower than that determined in terms of required performance because of heterogeneous distribution of permeability in the ground, which might be considerable when the ground is created by the compaction method. The effect of heterogeneity in the ground on the permeability of the bentonite ground should be evaluated by overall permeability of the ground, whereas in practice, the effect is evaluated by the distribution of permeability in the ground. Thus, in this study, overall permeability of the bentonite ground is evaluated from the permeability of the bentonite ground is evaluated from the permeability distribution determined using the geostatistical method with the dry density data as well as permeability data of the undisturbed sample recovered from the bentonite ground. Consequently, it was proved through this study that possibility of overestimation of permeability of the bentonite ground can be reduced if the overall permeability is used. (author)

Copper corrosion in bentonite: Studying of parameters (pH, Eh/O2) of importance for Cu corrosion

International Nuclear Information System (INIS)

Carlsson, T.; Muurinen, A.

2007-06-01

The report describes the development of methods and equipment for studying the parameters (pH, Eh/O 2 ) of importance for copper corrosion. The work involved the fabrication of electrodes for determining Eh and pH in compacted water-saturated bentonite. MX-80 and the Indian Asha 505 bentonites were used in the study. The redox-measurements were carried out by using electrodes prepared of Au and Pt wires. The pH measurements were carried out by using solid IrO x electrodes. The report describes testing of electrodes in different solutions and in bentonite. A destructive method for determining oxygen content in compacted bentonite was tested, too. The electrodes were used in measurements inside compacted bentonite with about the same density as is intended to be used in the Finnish repository for spent nuclear fuel. The results indicate that Au and Pt redox-electrodes and IrO x pH electrodes function in compacted bentonite. The oxygen measurement in bentonite seems to work, too, and can complement the Eh measurements. Eh-values in originally aerobic bentonite samples having a dry densitiy of ≤1.5 g/cm 3 , exhibit mostly a decrease during the first days, which may mainly be ascribed to the depletion of oxygen. The Eh-decrease thereafter is probably associated with redox-reactions involving other species than oxygen. In samples with a dry density of 1.8 g/cm 3 , the observed Eh-decrease is mostly slower. No significant difference between the Eh and pH measurements in MX-80 and Asha 505 could be observed. (orig.)

Gas Transport in Bentonite

Energy Technology Data Exchange (ETDEWEB)

Villar, M. V.; Gutierre-Rodrigo, V.; Martin, P. I.; Romero, F. J.; Barcala, J. M.

2013-07-01

The gas permeability of the Spanish FEBEX bentonite compacted at dry densities of between 1.4 and 1.8 g/cm{sup 3} with high water contents was measured for different confining, injection and back pressures. The results were compared with results obtained in previous investigations for lower degrees of saturation. It was checked that gas permeability was greatly affected by dry density, decreasing about three orders of magnitude when it increased from 1.5 to 1.8 g/cm{sup 3} for similar water content. The increase of water content caused also a decrease in gas permeability. It was found that both gas permeability and the relative gas permeability were mainly related to the accessible porosity. These relationships could be fitted to potential expressions with exponents between 3 and 4, as well as the relationship between intrinsic permeability and void ratio. For gas pressures below 1.2 MPa no effect of the injection or confining pressures on the value of permeability was detected. For a given confining pressure the permeability value decreased as the effective pressure increased, especially if the increase in effective pressure was due to a decrease in gas back pressure. It was checked that the Klinkenberg effect was not significant for this material in the range of pressures applied in the tests. The gas breakthrough pressure values in FEBEX saturated bentonite were determined for different dry densities. They increased clearly with dry density and were always higher than the swelling pressure of the bentonite. In high density samples gas flow tended to stop abruptly after breakthrough, whereas in lower density samples gas flow decreased gradually until a given pressure gradient was reached. The permeabilities computed after breakthrough (which usually did not stabilise) were inversely related to dry density. This would indicate that, even if the flow took place predominantly through preferential pathways that sometimes closed quickly after breakthrough and others

Gas Transport in Bentonite

International Nuclear Information System (INIS)

Villar, M. V.; Gutierrez-Rodrigo, V.; Martin, P. L.; Romero, F. J.; Barcala, J. M.

2013-01-01

The gas permeability of the Spanish FEBEX bentonite compacted at dry densities of between 1.4 and 1.8 g/cm 3 with high water contents was measured for different confining, injection and back pressures. The results were compared with results obtained in previous investigations for lower degrees of saturation. It was checked that gas permeability was greatly affected by dry density, decreasing about three orders of magnitude when it increased from 1.5 to 1.8 g/cm 3 for similar water content. The increase of water content caused also a decrease in gas permeability. It was found that both gas permeability and the relative gas permeability were mainly related to the accessible porosity. These relationships could be fitted to potential expressions with exponents between 3 and 4, as well as the relationship between intrinsic permeability and void ratio. For gas pressures below 1.2 MPa no effect of the injection or confining pressures on the value of permeability was detected. For a given confining pressure the permeability value decreased as the effective pressure increased, especially if the increase in effective pressure was due to a decrease in gas back pressure. It was checked that the Klinkenberg effect was not significant for this material in the range of pressures applied in the tests. The gas breakthrough pressure values in FEBEX saturated bentonite were determined for different dry densities. They increased clearly with dry density and were always higher than the swelling pressure of the bentonite. In high density samples gas flow tended to stop abruptly after breakthrough, whereas in lower density samples gas flow decreased gradually until a given pressure gradient was reached. The permeabilities computed after breakthrough (which usually did not stabilise) were inversely related to dry density. This would indicate that, even if the flow took place predominantly through preferential pathways that sometimes closed quickly after breakthrough and others remained

Investigation on compression behaviour of highly compacted GMZ01 bentonite with suction and temperature control

Energy Technology Data Exchange (ETDEWEB)

Ye, W.M., E-mail: ye_tju@tongji.edu.cn [Key Laboratory of Geotechnical and Underground Engineering of Ministry of Education, Tongji University, Shanghai 200092 (China); United Research Center for Urban Environment and Sustainable Development, The Ministry of Education, Shanghai 200092 (China); Zhang, Y.W.; Chen, B.; Zheng, Z.J.; Chen, Y.G. [Key Laboratory of Geotechnical and Underground Engineering of Ministry of Education, Tongji University, Shanghai 200092 (China); Cui, Y.J. [Key Laboratory of Geotechnical and Underground Engineering of Ministry of Education, Tongji University, Shanghai 200092 (China); Ecole des Ponts ParisTech, UR Navier/CERMES 77455 (France)

2012-11-15

Highlights: Black-Right-Pointing-Pointer Heating induced volumetric change of GMZ01 bentonite depends on suction. Black-Right-Pointing-Pointer Suction has significant influence on compressibility. Black-Right-Pointing-Pointer Temperature has slight influence on compressibility. - Abstract: In this paper, an oedometer with suction and temperature control was developed. Mechanical compaction tests have been performed on the highly compacted GMZ01 bentonite, which has been recognized as potential buffer/backfill material for construction of Chinese high-level radioactive waste (HLW) geological repository, under conditions of suction ranging from 0 to 110 MPa, temperature from 20 to 80 Degree-Sign C and vertical pressure from 0.1 to 80 MPa. Based on the test results, suction and temperature effects on compressibility parameters are investigated. Results reveal that: (1) at high suctions, heating induced an expansion, while contraction is induced by heating at low suctions. The thermal expansion coefficient of GMZ01 bentonite measured is 1 Multiplication-Sign 10{sup -4} Degree-Sign C{sup -1}; (2) with increasing suction, the elastic compressibility {kappa} and the plastic compressibility {lambda}(s) of the highly compacted GMZ01 bentonite decrease, while the pre-consolidation pressure increases markedly; (3) with increasing temperature, the elastic compressibility of compacted GMZ01 bentonite changes insignificantly, while the plastic compressibility {lambda}(s) slightly decreases and the yield surface tends to shrink.

Bentonite erosion - Laboratory studies

International Nuclear Information System (INIS)

Jansson, Mats

2010-01-01

Document available in extended abstract form only. Bentonite clay is proposed as buffer material in the KBS-3 concept of storing spent nuclear fuel. Since the clay is plastic it will protect the canisters containing the spent fuel from movements in the rock. Furthermore, the clay will expand when taking up water, become very compact and hence limit the transport of solutes to and from the canister to only diffusion. The chemical stability of the bentonite barrier is of vital importance. If much material would be lost the barrier will lose its functions. As a side effect, lots of colloids will be released which may facilitate radionuclide transport in case of a breach in the canister. There are scenarios where during an ice age fresh melt water may penetrate down to repository depths with relatively high flow rates and not mix with older waters of high salinity. Under such conditions bentonite colloids will be more stable and there is a possibility that the bentonite buffer would start to disperse and bentonite colloids be carried away by the passing water. This work is a part of a larger project called Bentonite Erosion, initiated and supported by SKB. In this work several minor experiments have been performed in order to investigate the influence of for instance di-valent cations, gravity, etc. on the dispersion behaviour of bentonite and/or montmorillonite. A bigger experiment where the real situation was simulated using an artificial fracture was conducted. Two Plexiglas slabs were placed on top of each other, separated by plastic spacers. Bentonite was placed in a container in contact with a fracture. The bentonite was water saturated before deionized water was pumped through the fracture. The evolution of the bentonite profile in the fracture was followed visually. The eluate was collected in five different slots at the outlet side and analyzed for colloid concentration employing Photon Correlation Spectroscopy (PCS) and a Single Particle Counter (SPC). Some

On barrier performance of high compaction bentonite in facilities of disposing high level radioactive wastes in formation

International Nuclear Information System (INIS)

Ikeda, Hidefumi; Komada, Hiroya

1989-01-01

As for the method of disposing high level radioactive wastes generated in the reprocessing of spent fuel, at present formation disposal is regarded as most promising. The most important point in this formation disposal is to prevent the leak of radioactive nuclides within the disposal facilities into bedrocks and their move to the zone of human life. As the method of formation disposal, the canisters containing high level radioactive wastes are placed in the horizontal or vertical holes for disposal dug from horizontal tunnels which are several hundreds m underground, and the tunnels and disposal holes are filled again. For this filling material, the barrier performance to prevent and retard the leak of radioactive nuclides out of the disposal facilities is expected, and the characteristics of low water permeability, the adsorption of nuclides and long term stability are required. However, due to the decay heat of wastes just after the disposal, high temperature and drying condition arises, and this must be taken in consideration. The characteristics required for filling materials and the selection of the materials, the features and classification of bentonite, the properties of high compaction bentonite, and the move of water, heat and nuclides in high compaction bentonite are reported.(Kako, I.)

FEBEX bentonite colloid stability in ground water

Energy Technology Data Exchange (ETDEWEB)

Seher, H.; Schaefer, T.; Geckeis, H. [Inst. fuer Nukleare Entsorgung (INE), Forschungszentrum Karlsruhe, 76021 Karlsruhe (Germany)]. e-mail: holger.seher@ine.fzk .de; Fanghaenel, T. [Ruprecht-Karls-Univ. Heidelberg, Physikalisch-Chemisches In st., D-69120 Heidelberg (Germany)

2007-06-15

Coagulation experiments are accomplished to identify the geochemical conditions for the stability of Febex bentonite colloids in granite ground water. The experiments are carried out by varying pH, ionic strength and type of electrolyte. The dynamic light scattering technique (photon correlation spectroscopy) is used to measure the size evolution of the colloids with time. Agglomeration rates are higher in MgCl{sub 2} and CaCl{sub 2} than in NaCl solution. Relative agglomeration rates follow approximately the Schulze-Hardy rule. Increasing agglomeration rates at pH>8 are observed in experiments with MgCl{sub 2} and CaCl{sub 2} which are, however, caused by coprecipitation phenomena. Bentonite colloid stability fields derived from the colloid agglomeration experiments predict low colloid stabilization in granite ground water taken from Aespoe, Sweden, and relatively high colloid stability in Grimsel ground water (Switzerland)

Evaluation of gas migration characteristics of compacted bentonite considering in-situ conditions of disposal facility

International Nuclear Information System (INIS)

Tanaka, Yukihisa; Hironaga, Michihiko

2012-01-01

In the current concept of repository for radioactive waste disposal, compacted bentonite will be used as an engineered barrier mainly for inhibiting migration of radioactive nuclides. Hydrogen gas can be generated inside the engineered barrier by anaerobic corrosion of metals used for containers, etc. If the gas generation rate exceeds the diffusion rate of gas molecules inside of the engineered barrier, gas will accumulate in the void space inside of the engineered barrier until its pressure becomes large enough for it to enter the bentonite as a discrete gaseous phase. It is expected to be not easy for gas to entering into the bentonite as a discrete gaseous phase because the pore of compacted bentonite is so minute. Therefore it is necessary to investigate the effect of gas pressure generation and gas migration on the engineered barrier, peripheral facilities and ground. CRIEPI already proposed an analytical method for simulating gas migration through the compacted bentonite using the model of two phase flow through deformable porous media. Though validity of the analytical code of CRIEPI was examined by comparing existing gas migration test results with the calculated results, further validation is needed because in situ conditions, such as stress conditions and boundary condition, are different from conventional laboratory gas migration tent. In this study, gas migration tests whose initial axial stress is larger than initial radial stress and gas migration tests whose gas inlet is small. Simulation of the test results is also conducted. Comparing the test results with the calculated results, it is revealed that the analytical code of CRIEPI can simulate gas migration behavior through compacted bentonite with accuracy. (author)

Modeling hydraulic conductivity and swelling pressure of several kinds of bentonites affected by concentration of saline water

International Nuclear Information System (INIS)

Tanaka, Yukihisa; Hasegawa, Takuma; Nakamura, Kunihiko

2007-01-01

In case of construction of repository for radioactive waste near the coastal area, the effect of brine on hydraulic conductivity of bentonite as an engineering barrier should be considered because it is known that the hydraulic conductivity of bentonite increases with increasing in salt concentration of water. Thus, the effect of salinity of water on hydraulic conductivity of bentonite has been conducted experimentally. However, it is necessary to elucidate and to model the mechanism of the phenomenon because various kinds of bentonites may possibly be placed in various salinity of salt water. In this study, a model for evaluating permeability of compacted bentonite is proposed considering a) increase in number of sheets of montomorillonite crystal because of cohesion, b) decrease in viscosity of water in interlayer between sheets of montmorillonite crystal. Quantitative evaluation method for permeability of several kinds of bentonite under brine is proposed based on the model mentioned above. (author)

The effects of bacteria on the corrosion behavior of carbon steel in compacted bentonite

International Nuclear Information System (INIS)

Nishimura, T.; Wada, R.; Nishimoto, H.; Fujiwara, K.; Taniguchi, N.; Honda, A.

1999-10-01

As a part of evaluation of corrosion life of carbon steel overpack, the experimental studies have been performed on the effects of bacteria on the corrosion behavior of carbon steel in compacted bentonite using iron bacteria (IB) as a representative oxidizing bacteria and sulphur reducing bacteria (SRB) as a representative reducing bacteria. The results of the experimental studies showed that; The activity of SRB was low in compacted bentonite in spite of applying suitable condition for the action of bacteria such as temperature and nutritious solution. Although the corrosion behavior of carbon steel was affected by the existence of bacteria in simple solution, the corrosion rates of carbon steel in compacted bentonite were several μ m/year -10 μ m/year irrespective of coexistence of bacteria and that the corrosion behavior was not affected by the existence of bacteria. According to these results, it was concluded that the bacteria would not affect the corrosion behavior of carbon steel overpack under repository condition. (author)

An Evaluation of Models of Bentonite Pore Water Evolution

Energy Technology Data Exchange (ETDEWEB)

Savage, David; Watson, Claire; Wilson, James (Quintessa Ltd, Henley-on-Thames (United Kingdom)); Arthur, Randy (Monitor Scientific LLC, Denver, CO (United States))

2010-01-15

The determination of a bentonite pore water composition and understanding its evolution of with time underpins many radioactive waste disposal issues, such as buffer erosion, canister corrosion, and radionuclide solubility, sorption, and diffusion, inter alia. The usual approach to modelling clay pore fluids is based primarily around assumed chemical equilibrium between Na+, K+, Ca2+, and Mg2+ aqueous species and ion exchange sites on montmorillonite, but also includes protonation- deprotonation of clay edge surface sites, and dissolution-precipitation of the trace mineral constituents, calcite and gypsum. An essential feature of this modelling approach is that clay hydrolysis reactions (i.e. dissolution of the aluminosilicate octahedral and tetrahedral sheets of montmorillonite) are ignored. A consequence of the omission of clay hydrolysis reactions from bentonite pore fluid models is that montmorillonite is preserved indefinitely in the near-field system, even over million-year timescales. Here, we investigate the applicability of an alternative clay pore fluid model, one that incorporates clay hydrolysis reactions as an integral component and test it against well-characterised laboratory experimental data, where key geochemical parameters, Eh and pH, have been measured directly in compacted bentonite. Simulations have been conducted using a range of computer codes to test the applicability of this alternative model. Thermodynamic data for MX-80 smectite used in the calculations were estimated using two different methods. Simulations of 'end-point' pH measurements in batch bentonite-water slurry experiments showed different pH values according to the complexity of the system studied. The most complete system investigated revealed pH values were a strong function of partial pressure of carbon dioxide, with pH increasing with decreasing PCO{sub 2} (log PCO{sub 2} values ranging from -3.5 to -7.5 bars produced pH values ranging from 7.9 to 9.6). A second

Ion diffusion in compacted bentonite

Energy Technology Data Exchange (ETDEWEB)

Lehikoinen, J. [VTT Chemical Technology, Espoo (Finland)

1999-03-01

In the study, a two-dimensional molecular-level diffusion model, based on a modified form of the Gouy-Chapman (GC) theory of the electrical double layers, for hydrated ionic species in compacted bentonite was developed. The modifications to the GC theory, which forms the very kernel of the diffusion model, stem from various non-conventional features: ionic hydration, dielectric saturation, finite ion-sizes and specific adsorption. The principal objectives of the study were met. With the aid of the consistent diffusion model, it is a relatively simple matter to explain the experimentally observed macroscopic exclusion for anions as well as the postulated, but greatly controversial, surface diffusion for cations. From purely theoretical grounds, it was possible to show that the apparent diffusivities of cations, anions and neutral molecules (i) do not exhibit order-or-magnitude differences, and (ii) are practically independent of the solution ionic strength used and, consequently, of the distribution coefficient, K{sub d}, unless they experience specific binding onto the substrate surface. It was also of interest to investigate the equilibrium anionic concentration distribution in the pore geometry of the GMM model as a function of the solution ionic strength, and to briefly speculate its consequences to diffusion. An explicit account of the filter-plate effect was taken by developing a computerised macroscopic diffusion model, which is based upon the very robust and efficient Laplace Transform Finite-Difference technique. Finally, the inherent limitations as well as the potential fields of applications of the models were addressed. (orig.) 45 refs.

Ion diffusion in compacted bentonite

International Nuclear Information System (INIS)

Lehikoinen, J.

1999-03-01

In the study, a two-dimensional molecular-level diffusion model, based on a modified form of the Gouy-Chapman (GC) theory of the electrical double layers, for hydrated ionic species in compacted bentonite was developed. The modifications to the GC theory, which forms the very kernel of the diffusion model, stem from various non-conventional features: ionic hydration, dielectric saturation, finite ion-sizes and specific adsorption. The principal objectives of the study were met. With the aid of the consistent diffusion model, it is a relatively simple matter to explain the experimentally observed macroscopic exclusion for anions as well as the postulated, but greatly controversial, surface diffusion for cations. From purely theoretical grounds, it was possible to show that the apparent diffusivities of cations, anions and neutral molecules (i) do not exhibit order-or-magnitude differences, and (ii) are practically independent of the solution ionic strength used and, consequently, of the distribution coefficient, K d , unless they experience specific binding onto the substrate surface. It was also of interest to investigate the equilibrium anionic concentration distribution in the pore geometry of the GMM model as a function of the solution ionic strength, and to briefly speculate its consequences to diffusion. An explicit account of the filter-plate effect was taken by developing a computerised macroscopic diffusion model, which is based upon the very robust and efficient Laplace Transform Finite-Difference technique. Finally, the inherent limitations as well as the potential fields of applications of the models were addressed. (orig.)

Long-term stability of bentonite. A literature review

International Nuclear Information System (INIS)

Laine, H.; Karttunen, P.

2010-07-01

The long-term thermodynamic stability of the bentonite buffer in the evolving chemical, thermal and hydrological conditions at Olkiluoto has been evaluated by reviewing the relevant experimental data and natural occurrences of bentonite that could serve as analogues for the long-term bentonite stability in the expected repository conditions, especially focussing on mineral transformations due, among others, to thermal effects including cementation. Natural occurrences with stable smectite have been reviewed and compared with Olkiluoto groundwater compositions at present and during the expected hydrogeochemical evolution of the repository. Alteration of the bentonite buffer is expected to be insignificant for natural groundwater conditions at present and for the evolving groundwater conditions at the expected thermal boundary conditions caused by the heat induced from the fuel canisters ( + and SiO 2 and elevated pH due to degradation and dissolution processes. These may alter the conditions in the repository that may favour alteration and cementation processes. The amounts of foreign materials to be used in the repository will be updated along with the progress of the construction. Also the information on their impact on the barriers needs to be evaluated in more detail, including the degradation rate, mobility or dilution of the foreign materials in the repository environment. The exchangeable cation composition of the buffer bentonite is expected to equilibrate with the surrounding groundwater during and after saturation. This process is expected to lead towards Ca-dominant exchangeable cation composition within the montmorillonite interlayer spaces in the buffer. In general it seems that the transformation towards Ca-dominated composition would favour the long-term stability of the buffer as Ca-dominated smectite (compared to Na-dominated type) has larger water retention capacity and anion incorporation to the interlayer space of montmorillonite is more

Comparison between uniaxially and isostatically compacted bentonite

International Nuclear Information System (INIS)

Kalbantner, P.; Sjoeblom, R.; Boergesson, Lennart

2001-12-01

The purpose of the present report is to provide the Swedish Nuclear Fuel and Waste Management Company (SKB) with the knowledge base needed for their selection of reference method for manufacturing of bentonite blocks. The purpose is also to provide support for the direction of the further development work. Three types of blocks are compared in the present report: uniaxially compacted medium high blocks, isostatically compacted medium high blocks, isostatically compacted high blocks. The analyses is based on three process systems relating to the sequence of excavation of bentonite-transport-powder preparation-compaction-handling and emplacement of bentonite blocks. The need for further knowledge has been identified and documented in conjunction with these analyses. The comparison is primarily made with regard to the criteria safety/risk, quality/ technique and economy. It is carried out through identification of issues of significance and subsequent analysis and evaluation as well as more formally in a simplified AHP (AHP = Analytical Hierarchic Process). The result of the analyses is that the isostatic technique is applicable for the production of high as well as medium size blocks. The pressed blocks are assessed to fulfil the basic requirements with a very large margin. The result of the analyses is also that the uniaxial technique is applicable for the preparation of medium size blocks, which are assessed to fulfil the basic requirements with a large margin. The need for development and process control is assessed to be somewhat higher for the uniaxial technique. One example is the friction against the walls of the die during the compaction, including the significance of this friction for the development of stresses and discontinuities in the block. These results support a selection of the isostatic technique as the reference technique as it provides flexibility in the choice of block height. The uniaxial technique can form a second alternative if medium high

Report on Thermo-Hydro-Mechanical Laboratory Tests Performed by CIEMAT on Febex Bentonite 2004-2008

International Nuclear Information System (INIS)

Villar, M. V.; Gomez-Espina, R.

2009-01-01

The results of the laboratory studies performed by CIEMAT with the FEBEX bentonite in the context of WP3.2 of the NF-PRO Project and of the Agreement ENRESA-CIEMAT Anexo V are presented and analysed in this report. They refer to the effect of the hydraulic gradient on the permeability of bentonite, the effect of the thermal gradient on the hydration kinetics of bentonite, and the repercussion of temperature on the hydro-mechanical properties of bentonite (swelling, permeability and water retention capacity). In all the cases the bentonite has been used compacted to densities expected in the engineered barrier of a high-level radioactive waste repository. The existence of threshold and critical hydraulic gradients has been observed, both of them dependent on bentonite density and water pressures. After more than seven years of hydration, the 40-cm high bentonite columns are far from full saturation, the thermal gradient additionally delaying the process, which is very slow. Temperatures below 100 degree centigrade slightly decrease the swelling and the water retention capacity of the bentonite and increase its permeability. The information obtained improves the knowledge on the behaviour of expansive clay and will help the development of constitutive models and the interpretation of the results obtained in the mock-up and the in situ tests. (Author) 35 refs

Report on Thermo-Hydro-Mechanical Laboratory Tests Performed by CIEMAT on Febex Bentonite 2004-2008

Energy Technology Data Exchange (ETDEWEB)

Villar, M. V.; Gomez-Espina, R.

2009-11-25

The results of the laboratory studies performed by CIEMAT with the FEBEX bentonite in the context of WP3.2 of the NF-PRO Project and of the Agreement ENRESA-CIEMAT Anexo V are presented and analysed in this report. They refer to the effect of the hydraulic gradient on the permeability of bentonite, the effect of the thermal gradient on the hydration kinetics of bentonite, and the repercussion of temperature on the hydro-mechanical properties of bentonite (swelling, permeability and water retention capacity). In all the cases the bentonite has been used compacted to densities expected in the engineered barrier of a high-level radioactive waste repository. The existence of threshold and critical hydraulic gradients has been observed, both of them dependent on bentonite density and water pressures. After more than seven years of hydration, the 40-cm high bentonite columns are far from full saturation, the thermal gradient additionally delaying the process, which is very slow. Temperatures below 100 degree centigrade slightly decrease the swelling and the water retention capacity of the bentonite and increase its permeability. The information obtained improves the knowledge on the behaviour of expansive clay and will help the development of constitutive models and the interpretation of the results obtained in the mock-up and the in situ tests. (Author) 35 refs.

Evaluation of phenomena affecting diffusion of cations in compacted bentonite

International Nuclear Information System (INIS)

Muurinen, A.; Lehikoinen, J.

1995-04-01

In a number of diffusion studies, contradictions between the apparent diffusivities of cations and their distribution coefficients in bentonite have been found. Two principal reasons have been offered as explanations for this discrepancy; diffusion of the sorbed cations, often called surface diffusion, and the decrease of sorption in compacted clay compared to a sorption value obtained from a batch experiment. In the study the information available from the literature on sorption-diffusion mechanisms of cations in bentonite has been compiled and re-interpreted in order to improve the understanding of the diffusion process. (103 refs., 23 figs., 8 tabs.)

Coupled behaviour of bentonite buffer results of PUSKURI project; Bentoniittipuskurin kytketty kaeyttaeytyminen PUSKURI-hankkeen tuloksia

Energy Technology Data Exchange (ETDEWEB)

Olin, M.; Rasilainen, K.; Itaelae, A. [and others

2011-08-15

In the report main results form a KYT2010 programme's project Coupled behaviour of bentonite buffer (PUSKURI) are presented. In THC modelling, Aku Itaelae made and published his Master of Science Thesis. Itaelae was able to successfully model the LOT-experiment. Additionally, he also listed problems and development proposals for THC-modelling of bentonite buffer. VTT and Numerola created in collaboration a model coupling saturation, diffusion and cation exchange; the model was implemented and tested in Numerrin, COMSOL and TOUGHREACT. Petri Jussila's PhD THM-model was implemented into COMSOL to facilitate further development. At GTK, the mineralogical characterisation of bentonite was planned. The previous THM model (Jussila's model) including only small deformations was successfully generalized to finite deformations in way at least formally preserving the original formalism. It appears that the theory allows also a possibility to include finite plastic deformations in the theory. In order to measure the relevant mechanical properties of compacted bentonite, two different experiments, namely hydrostatic compression experiment and one-dimensional compression experiment were designed. In the hydrostatic compression experiment, a cylindrical sample of compacted bentonite covered with liquid rubber coating is placed in the sample chamber equipped with a piston. The same device was also used in one-dimensional compression experiment. X-ray microtomographic techniques were used in order to study the basic mechanisms of water transport in bentonite. The preliminary results indicate that in the present experimental set-up, water transport is dominated by a dispersive mechanism such as diffusion of vapour in gas phase or diffusion of water in solid phase. (orig.)

Magnesium incorporated bentonite clay for defluoridation of drinking water

International Nuclear Information System (INIS)

Thakre, Dilip; Rayalu, Sadhana; Kawade, Raju; Meshram, Siddharth; Subrt, J.; Labhsetwar, Nitin

2010-01-01

Low cost bentonite clay was chemically modified using magnesium chloride in order to enhance its fluoride removal capacity. The magnesium incorporated bentonite (MB) was characterized by using XRD and SEM techniques. Batch adsorption experiments were conducted to study and optimize various operational parameters such as adsorbent dose, contact time, pH, effect of co-ions and initial fluoride concentration. It was observed that the MB works effectively over wide range of pH and showed a maximum fluoride removal capacity of 2.26 mg g -1 at an initial fluoride concentration of 5 mg L -1 , which is much better than the unmodified bentonite. The experimental data fitted well into Langmuir adsorption isotherm and follows pseudo-first-order kinetics. Thermodynamic study suggests that fluoride adsorption on MB is reasonably spontaneous and an endothermic process. MB showed significantly high fluoride removal in synthetic water as compared to field water. Desorption study of MB suggest that almost all the loaded fluoride was desorbed (∼97%) using 1 M NaOH solution however maximum fluoride removal decreases from 95.47 to 73 (%) after regeneration. From the experimental results, it may be inferred that chemical modification enhances the fluoride removal efficiency of bentonite and it works as an effective adsorbent for defluoridation of water.

Removal of Radium isotopes from oil co-produced water using Bentonite

International Nuclear Information System (INIS)

Al Masri, M.S.; Al Attar, L.; Budeir, Y.; Al Chayah, O.

2010-01-01

In view of environmental concern, sorption of radium on natural bentonite mineral (Aleppo, Syria) was investigated using batch-type method. Data were expressed in terms of distribution coefficients. An attempt to increase the selectivity of bentonite for radium was made by preparing M-derivatives. Loss of mineral crystallinity in acidic media and the formation of new phase, such as BaCO 3 , in Ba-derivative were imposed by XRD characterisations. Of the cationic forms, Na-bentonite had shown the highest affinity. Mechanisms of radium uptake were pictured using M-derivatives and simulated radium solutions. The obtained results indicated that surface sorption/surface ion exchange were the predominated processes. The distinct sorption behaviour observed with Ba-form was, possibly, a reflection of radium co-precipitation with barium carbonate. The competing order of macro component, likely present in waste streams, was drawn by studying different concentrations of the corresponding salt media. As an outcome, sodium was the weakest inhibitor. The performance of natural bentonite and the most selective forms, i.e. Ba- and Na-derivatives, to sorb radium from actual oil co-produced waters, collected form Der Ezzor Petroleum Company (DEZPC), was studied. This mirrored the influential effect of waters pH over other comparable parameters. (author)

Monitoring of bentonite pore water with a probe based on solid-state microsensors

International Nuclear Information System (INIS)

Orozco, Jahir; Baldi, Antoni; Martin, Pedro L.; Bratov, Andrei; Jimenez, Cecilia

2006-01-01

Repositories for the disposal of radioactive waste generally rely on a multi-barrier system to isolate the waste from the biosphere. This multi-barrier system typically comprises Natural geological barrier provided by the repository host rock and its surroundings and an engineered barrier system (EBS). Bentonite is being studied as an appropriated porous material for an EBS to prevent or delay the release and transport of radionuclides towards biosphere. The study of pore water chemistry within bentonite barriers will permit to understand the transport phenomena of radionuclides and obtain a database of the bentonite-water interaction processes. In this work, the measurement of some chemical parameters in bentonite pore water using solid-state microsensors is proposed. Those sensors are well suited for this application since in situ measurements are feasible and they are robust enough for the long periods of time that monitoring is needed in an EBS. A probe containing an ISFET (ion sensitive field effect transistor) for measuring pH, and platinum microelectrodes for measuring conductivity and redox potential was developed, together with the required instrumentation, to study the chemical changes in a test cell with compacted bentonite. Response features of the sensors' probe and instrumentation performance in synthetic samples with compositions similar to those present in bentonite barriers are reported. Measurements of sensors stability in a test cell are also presented

Long-term alteration of bentonite in the presence of metallic iron

Energy Technology Data Exchange (ETDEWEB)

Kumpulainen, Sirpa; Kiviranta, Leena (BandTech Oy (Finland)); Carlsson, Torbjoern; Muurinen, Arto (VTT (Finland)); Svensson, Daniel (Svensk Kaernbraenslehantering AB (Sweden)); Sasamoto, Hiroshi; Yui, Mikatzu (JAEA (Japan)); Wersin, Paul; Rosch, Dominic (Gruner Ltd (Switzerland))

2010-05-15

According to the KBS-3H concept, each copper canister containing spent nuclear fuel will be surrounded by a bentonite buffer and a perforated steel cylinder. Since steel is unstable in wet bentonite, it will corrode and the corrosion products will interact with the surrounding bentonite in ways that are not fully understood. Such interaction may seriously impair the bentonite's functioning as a buffer material, e.g. by lowering its CEC or decreasing its swelling capacity. This report presents results from two iron-bentonite experiments carried out under quite different conditions at VTT (Finland) and JAEA (Japan). Both studies focused on long-term iron-bentonite interactions under anaerobic conditions. The study at VTT comprised eight years long experiments focused on diffusive based interactions between solid cast-iron and compacted MX-80 bentonite (dry density 1.5-1.6 g/cm3) in contact with an aqueous 0.5 M NaCl solution. The study at JAEA comprised ten years long batch experiments, each involving a mixture of metallic iron powder (25 g), an industrially refined Na bentonite, Kunipia F, which contains more than 99% montmorillonite (25 g), and an aqueous solution (250 mL). Samples were sent to B+Tech in airtight steel vessels filled with N{sub 2} and subsequently analyzed at various laboratories in Finland and Sweden. The JAEA samples differed with regard to the initial solution chemistry, which was either distilled water, 0.3 M NaCl, 0.6 M NaCl, 0.1 M NaHCO{sub 3}, or 0.05 M Na{sub 2}SO{sub 4}. The analyses of the MX-80 bentonite samples were carried out on samples containing a cast iron cylinder and also on corresponding background samples with no cast iron. In addition, the external solution and gas phase in contact with the bentonite were analyzed. Briefly, the gas contained H{sub 2}, most possibly caused by corrosion of the cast iron, and CO{sub 2}, mainly as a result of carbonate dissolution. The eight years old external solution exhibited, inter alia

Long-term alteration of bentonite in the presence of metallic iron

International Nuclear Information System (INIS)

Kumpulainen, Sirpa; Kiviranta, Leena; Carlsson, Torbjoern; Muurinen, Arto; Svensson, Daniel; Sasamoto, Hiroshi; Yui, Mikatzu; Wersin, Paul; Rosch, Dominic

2010-05-01

According to the KBS-3H concept, each copper canister containing spent nuclear fuel will be surrounded by a bentonite buffer and a perforated steel cylinder. Since steel is unstable in wet bentonite, it will corrode and the corrosion products will interact with the surrounding bentonite in ways that are not fully understood. Such interaction may seriously impair the bentonite's functioning as a buffer material, e.g. by lowering its CEC or decreasing its swelling capacity. This report presents results from two iron-bentonite experiments carried out under quite different conditions at VTT (Finland) and JAEA (Japan). Both studies focused on long-term iron-bentonite interactions under anaerobic conditions. The study at VTT comprised eight years long experiments focused on diffusive based interactions between solid cast-iron and compacted MX-80 bentonite (dry density 1.5-1.6 g/cm 3 ) in contact with an aqueous 0.5 M NaCl solution. The study at JAEA comprised ten years long batch experiments, each involving a mixture of metallic iron powder (25 g), an industrially refined Na bentonite, Kunipia F, which contains more than 99% montmorillonite (25 g), and an aqueous solution (250 mL). Samples were sent to B+Tech in airtight steel vessels filled with N 2 and subsequently analyzed at various laboratories in Finland and Sweden. The JAEA samples differed with regard to the initial solution chemistry, which was either distilled water, 0.3 M NaCl, 0.6 M NaCl, 0.1 M NaHCO 3 , or 0.05 M Na 2 SO 4 . The analyses of the MX-80 bentonite samples were carried out on samples containing a cast iron cylinder and also on corresponding background samples with no cast iron. In addition, the external solution and gas phase in contact with the bentonite were analyzed. Briefly, the gas contained H 2 , most possibly caused by corrosion of the cast iron, and CO 2 , mainly as a result of carbonate dissolution. The eight years old external solution exhibited, inter alia, reducing conditions, a pH of

Transport of water and ions in partially water-saturated porous media. Part 2. Filtration effects

Science.gov (United States)

Revil, A.

2017-05-01

A new set of constitutive equations describing the transport of the ions and water through charged porous media and considering the effect of ion filtration is applied to the problem of reverse osmosis and diffusion of a salt. Starting with the constitutive equations derived in Paper 1, I first determine specific formula for the osmotic coefficient and effective diffusion coefficient of a binary symmetric 1:1 salt (such as KCl or NaCl) as a function of a dimensionless number Θ corresponding to the ratio between the cation exchange capacity (CEC) and the salinity. The modeling is first carried with the Donnan model used to describe the concentrations of the charge carriers in the pore water phase. Then a new model is developed in the thin double layer approximation to determine these concentrations. These models provide explicit relationships between the concentration of the ionic species in the pore space and those in a neutral reservoir in local equilibrium with the pore space and the CEC. The case of reverse osmosis and diffusion coefficient are analyzed in details for the case of saturated and partially saturated porous materials. Comparisons are done with experimental data from the literature obtained on bentonite. The model predicts correctly the influence of salinity (including membrane behavior at high salinities), porosity, cation type (K+ versus Na+), and water saturation on the osmotic coefficient. It also correctly predicts the dependence of the diffusion coefficient of the salt with the salinity.

Hydro-mechanical behaviour of bentonite-based materials used for high-level radioactive waste disposal

International Nuclear Information System (INIS)

Wang, Q.

2012-01-01

This study deals with the hydro-mechanical behaviour of compacted bentonite-based materials used as sealing materials in high-level radioactive waste repositories. The pure MX80 bentonite, mixtures of MX80/crushed clay-stone and MX80/sand were used in the investigation. An experimental study on the swelling pressure of the bentonite-based materials was first performed. The results evidenced the effects of water chemistry, hydration procedure and duration, pre-existing technological void and experimental methods. Emphasis was put on the relationship between the swelling pressure and the final dry density of bentonite. Afterwards, the water retention test, hydration test and suction controlled oedometer test were conducted on samples with different voids including the technological void and the void inside the soil. By introducing the parameters as bentonite void ratio and water volume ratio, an overall analysis of the effects of voids on the hydro-mechanical response of the compacted material was performed. To get better insight into the seal evolution in case of technological void, the effects of final dry density and hydration time on the microstructure features were also characterized. Then, the hydraulic properties under unsaturated state were investigated by carrying out water retention test and infiltration test as well as the microstructure observation. The results obtained allowed relating the variation of hydraulic conductivity to the microstructure changes. A small scale (1/10) mock up test of the SEALEX in situ experiment was also performed to study the recovery capacity of bentonite-based material with consideration of a technological void. The results were used for interpreting the in-situ observations. With a reduced time scale, it provides useful information for estimating the saturation duration and sealing effectiveness of the field design. Finally, the experimental data obtained in the laboratory on bentonite/sand mixture were interpreted in the

Modelling gas migration in compacted bentonite. A report produced for the GAMBIT club

International Nuclear Information System (INIS)

Nash, P.J.; Swift, B.T.; Goodfield, M.; Rodwell, W.R.

1998-08-01

This report describes the first phase of a programme of work that has as its overall objective the development of a computational model that can simulate the results of experiments on gas migration through highly compacted bentonite, and will provide the basis of a model suitable to assess the effects of bentonite barriers on the build-up of pressure and the escape of hydrogen gas from disposal canisters in a radioactive waste repository. In this first phase of the project, the possible mechanisms and controlling features of gas migration through compacted bentonite have been reviewed, and a preliminary computational model of the process has been implemented and evaluated. In the model it is assumed that gas invasion of the clay occurs by induced microfissuring, and that the permeability of the pathways thus created depends on the gas pressure (or the effective stress). Experimental data on gas migration in compacted bentonite that was collected under well controlled conditions by Horseman and Harrington was used in a preliminary evaluation of the new model. The model was able to reproduce qualitatively all the features seen in the subset of the experimental data used in the evaluation, and to provide quantitative agreement to substantial sections of the results of test sequences, but quantitative agreement between simulation and experimental results over a whole test sequence was not obtained. As part of the model evaluation, the dependence of the results obtained on key model parameters is reported. Outline plans for a further phase of work are suggested. (orig.)

Modelling gas migration in compacted bentonite. A report produced for the GAMBIT club

Energy Technology Data Exchange (ETDEWEB)

Nash, P.J.; Swift, B.T.; Goodfield, M.; Rodwell, W.R. [AEA Technology plc, Dorchester (United Kingdom)

1998-08-01

This report describes the first phase of a programme of work that has as its overall objective the development of a computational model that can simulate the results of experiments on gas migration through highly compacted bentonite, and will provide the basis of a model suitable to assess the effects of bentonite barriers on the build-up of pressure and the escape of hydrogen gas from disposal canisters in a radioactive waste repository. In this first phase of the project, the possible mechanisms and controlling features of gas migration through compacted bentonite have been reviewed, and a preliminary computational model of the process has been implemented and evaluated. In the model it is assumed that gas invasion of the clay occurs by induced microfissuring, and that the permeability of the pathways thus created depends on the gas pressure (or the effective stress). Experimental data on gas migration in compacted bentonite that was collected under well controlled conditions by Horseman and Harrington was used in a preliminary evaluation of the new model. The model was able to reproduce qualitatively all the features seen in the subset of the experimental data used in the evaluation, and to provide quantitative agreement to substantial sections of the results of test sequences, but quantitative agreement between simulation and experimental results over a whole test sequence was not obtained. As part of the model evaluation, the dependence of the results obtained on key model parameters is reported. Outline plans for a further phase of work are suggested. (orig.) 32 refs.

Depth optimization for the Korean HLW repository System within a discontinuous and saturated granitic rock mass

International Nuclear Information System (INIS)

Kim, Jhin Wung; Bae, Dae Seok; Choi, Jong Won

2005-12-01

The present study is to evaluate the material properties of the compacted bentonite, backfill material, canister cast iron insert, and the rock mass for the Korean HLW repository system. These material properties are either measured, or taken from other countries, through the evaluation of the thermal, hydraulic, and mechanical interaction behavior of a repository. After the evaluation of the material properties, the most appropriate and economical depth as well as the layout of a single layer repository is to be recommended. Material properties used for the granitic rock mass, rock joints, PWR spent fuel, disposal canister, compacted bentonite, backfill material, and ground water are the data collected domestically, and foreign data are used for some of the data not available domestically. The repository model includes a saturated granitic rock mass with joints, PWR spent fuel in a disposal canister surrounded by compacted bentonite inside a deposition hole, and backfill material in the rest of the space within a repository cavern

Microbial activity in bentonite buffers. Literature study

Energy Technology Data Exchange (ETDEWEB)

Ratto, M.; Itavaara, M.

2012-07-01

The proposed disposal concept for high-level radioactive wastes involves storing the wastes underground in copper-iron containers embedded in buffer material of compacted bentonite. Hydrogen sulphide production by sulphate-reducing prokaryotes is a potential mechanism that could cause corrosion of waste containers in repository conditions. The prevailing conditions in compacted bentonite buffer will be harsh. The swelling pressure is 7-8 MPa, the amount of free water is low and the average pore and pore throat diameters are small. This literature study aims to assess the potential of microbial activity in bentonite buffers. Literature on the environmental limits of microbial life in extreme conditions and the occurrence of sulphatereducing prokaryotes in extreme environments is reviewed briefly and the results of published studies characterizing microbes and microbial processes in repository conditions or in relevant subsurface environments are presented. The presence of bacteria, including SRBs, has been confirmed in deep groundwater and bentonite-based materials. Sulphate reducers have been detected in various high-pressure environments, and sulphate-reduction based on hydrogen as an energy source is considered a major microbial process in deep subsurface environments. In bentonite, microbial activity is strongly suppressed, mainly due to the low amount of free water and small pores, which limit the transport of microbes and nutrients. Spore-forming bacteria have been shown to survive in compacted bentonite as dormant spores, and they are able to resume a metabolically active state after decompaction. Thus, microbial sulphide production may increase in repository conditions if the dry density of the bentonite buffer is locally reduced. (orig.)

Long-term alteration of bentonite in the presence of metallic iron

International Nuclear Information System (INIS)

Kumpulainen, S.; Kiviranta, L.; Carlsson, T.; Muurinen, A.; Svensson, D.; Sasamoto, Hiroshi; Yui, Mikatzu; Wersin, P.; Rosch, D.

2011-12-01

According to the KBS-3H concept, each copper canister containing spent nuclear fuel will be surrounded by a bentonite buffer and a perforated steel cylinder. Since steel is unstable in wet bentonite, it will corrode and the corrosion products will interact with the surrounding bentonite in ways that are not fully understood. Such interaction may seriously impair the bentonite's functioning as a buffer material, e.g. by lowering its CEC or decreasing its swelling capacity. This report presents results from two ironbentonite experiments carried out under quite different conditions at VTT (Finland) and JAEA (Japan). Both studies focused on long-term iron-bentonite interactions under anaerobic conditions. The study at VTT comprised eight years long experiments focused on diffusive based interactions between solid cast-iron and compacted MX-80 bentonite (dry density 1.5- 1.6 g/cm 3 ) in contact with an aqueous 0.5 M NaCl solution. The study at JAEA comprised ten years long batch experiments, each involving a mixture of metallic iron powder (25 g), an industrially refined Na bentonite, Kunipia F, which contains more than 99% montmorillonite (25 g), and an aqueous solution (250 mL). Samples were sent to B and Tech in airtight steel vessels filled with N 2 and subsequently analyzed at various laboratories in Finland and Sweden. The JAEA samples differed with regard to the initial solution chemistry, which was either distilled water, 0.3 M NaCl, 0.6 M NaCl, 0.1 M NaHCO 3 , or 0.05 M Na 2 SO 4 . The analyses of the MX-80 bentonite samples were carried out on samples containing a cast iron cylinder and also on corresponding background samples with no cast iron. In addition, the external solution and gas phase in contact with the bentonite were analyzed. Briefly, the gas contained H 2 , most possibly caused by corrosion of the cast iron, and CO 2 , mainly as a result of carbonate dissolution. The eight years old external solution exhibited, inter alia, reducing conditions, a p

Modeling erosion of unsaturated compacted bentonite by groundwater flow; pinhole erosion test case

International Nuclear Information System (INIS)

Laurila, T.; Sane, P.; Olin, M.; Koskinen, K.

2012-01-01

Document available in extended abstract form only. Erosion of compacted clay material by water flow is a critical factor affecting the performance of radioactive waste confinement. Our emphasis in this work is the buffer of KBS-3V concept, proposed to be compacted MX-80 bentonite. Unsaturated erosion occurs during the saturation phase of the EBS, and the main quantity of interest is the total buffer mass carried away by a groundwater flow that induces erosion by forming piping channels near the buffer/rock interface. The purpose of this work is to provide modeling tools to support erosion experiments. Role of modeling is first to interpret experimental observations in terms of processes, and to estimate robustness of experimental results. Secondly, we seek to scale up results from the laboratory scale, particularly to time scales longer than those experimentally accessible. We have performed modeling and data analysis pertaining to tests of unsaturated clay erosion. Pinhole experiments were used to study this erosion case. The main differences to well-understood pinhole erosion tests are that the material is strongly swelling and that the water flow is not determined by the pressure head but by the total flux. Groundwater flow in the buffer is determined by the flux because pressure losses occur overwhelmingly in the surrounding rock, not in the piping channel. We formulate a simple model that links an effective solid diffusivity -based swelling model to erosion by flow on the solid/liquid interface. The swelling model is similar in concept to that developed at KTH, but simpler. Erosion in the model is caused by laminar flow in the pinhole, and happens in a narrow region at the solid/liquid interface where velocity and solid volume fraction overlap. The erosion model can be mapped to erosion by wall shear, and can thus be considered as extension of that classic erosion model. The main quantity defining the behavior of clay erosion in the model is the ratio of

Modelling gas migration in compacted bentonite: GAMBIT Club Phase 2. Final report

Energy Technology Data Exchange (ETDEWEB)

Swift, B.T.; Hoch, A.R.; Rodwell, W.R. [AEA Technology (United Kingdom)

2001-01-01

This report describes the second phase of a programme of work to develop a computational model of gas migration through highly compacted bentonite. Experimental data that have appeared since the earlier report are reviewed for the additional information they might provide on the mechanism of gas migration in bentonite. Experiments carried out by Horseman and Harrigton (British Geological Survey) continued to provide the main data sets used in model evaluation. The earlier work (POSIVA Report 98-08) had resulted in a preliminary model of gas migration whose main features are gas invasion by microcrack propagation, and dilation of the pathways formed with increasing gas pressure. New work was carried out to further explore the capabilities of this model. In addition, a feature was added to the model to simulate gas pathway creation by water displacement rather than crack propagation. The development of a new alternative gas migration model is described. This is based on a volume-averaged representation of gas migration rather than on a description of flow in discrete pathways. Evaluation of this alternative model showed that it can produce similar agreement with experimental results to the other models examined. The implications of flow geometry, confining conditions and flow boundary conditions on gas migration behaviour in bentonite are reviewed. Proposals are made for the development of the new model into a tool for simulating gas migration through a bentonite buffer around a waste canister, and for possible enhancements to the model that might remove some of its currently perceived deficiencies. (orig.)

Modelling interaction of deep groundwaters with bentonite and radionuclide speciation

International Nuclear Information System (INIS)

Wanner, H.

1986-04-01

In the safety analysis recently reported for a potential Swiss high-level waste repository, radionuclide speciation and solubility limits are calculated for expected granitic groundwater conditions. With the objective of deriving a more realistic description of radionuclide release from the near-field, an investigation has been initiated to quantitatively specify the chemistry of the near-field. In the Swiss case, the main components of the near-field are the glass waste-matrix, a thick steel canister horizontally emplaced in a drift, and a backfill of highly compacted sodium bentonite. This report describes a thermodynamic model which is used to estimate the chemical composition of the pore water in compacted sodium bentonite. Solubility limits and speciation of important actinides and the fission product technetium in the bentonite pore water are then calculated. The model is based on available experimental data on the interaction of sodium bentonite and groundwater and represents means of extrapolation from laboratory data to repository conditions. The modelled composition of the pore water of compacted sodium bentonite, as well as the various compositions resulting from the long-term extrapolation, are used to estimate radionuclide solubilities in the near-field of a deep repository. From the chemical point of view, calcium bentonite seems to be more stable than sodium bentonite in the presence of Swiss Reference Groundwater. Since the effect of calcium bentonite on the groundwater chemical composition will be considerably less marked than that of sodium bentonite, especially with respect to key parameters for the nuclide speciation like carbonate concentration and pH, the use of calcium bentonite instead of sodium bentonite will improve the reliability in the prediction of source terms for radionuclide transport in the geosphere. (author)

Magnesium incorporated bentonite clay for defluoridation of drinking water.

Science.gov (United States)

Thakre, Dilip; Rayalu, Sadhana; Kawade, Raju; Meshram, Siddharth; Subrt, J; Labhsetwar, Nitin

2010-08-15

Low cost bentonite clay was chemically modified using magnesium chloride in order to enhance its fluoride removal capacity. The magnesium incorporated bentonite (MB) was characterized by using XRD and SEM techniques. Batch adsorption experiments were conducted to study and optimize various operational parameters such as adsorbent dose, contact time, pH, effect of co-ions and initial fluoride concentration. It was observed that the MB works effectively over wide range of pH and showed a maximum fluoride removal capacity of 2.26 mgg(-1) at an initial fluoride concentration of 5 mg L(-1), which is much better than the unmodified bentonite. The experimental data fitted well into Langmuir adsorption isotherm and follows pseudo-first-order kinetics. Thermodynamic study suggests that fluoride adsorption on MB is reasonably spontaneous and an endothermic process. MB showed significantly high fluoride removal in synthetic water as compared to field water. Desorption study of MB suggest that almost all the loaded fluoride was desorbed ( approximately 97%) using 1M NaOH solution however maximum fluoride removal decreases from 95.47 to 73 (%) after regeneration. From the experimental results, it may be inferred that chemical modification enhances the fluoride removal efficiency of bentonite and it works as an effective adsorbent for defluoridation of water. Copyright 2010 Elsevier B.V. All rights reserved.

Development of numerical simulation method for gas migration through highly-compacted bentonite using model of two-phase flow through deformable porous media

International Nuclear Information System (INIS)

Tanaka, Yukihisa

2011-01-01

In the current concept of repository for radioactive waste disposal, compacted bentonite will be used as an engineered barrier mainly for inhibiting migration of radioactive nuclides. Hydrogen gas can be generated inside of the engineered barrier by anaerobic corrosion of metals used for containers, etc. It is expected to be not easy for gas to entering into the bentonite as a discrete gaseous phase because the pore of compacted bentonite is so minute. Therefore it is necessary to investigate the effect of gas pressure generation and gas migration on the engineered barrier, peripheral facilities and ground. In this study, a method for simulating gas migration through the compacted bentonite is proposed. The proposed method can analyze coupled hydrological-mechanical processes using the model of two-phase flow through deformable porous media. Validity of the proposed analytical method is examined by comparing gas migration test results with the calculated results, which revealed that the proposed method can simulate gas migration behavior through compacted bentonite with accuracy. (author)

Freezing of bentonite. Experimental studies and theoretical considerations

Energy Technology Data Exchange (ETDEWEB)

Birgersson, Martin; Karnland, Ola; Nilsson, Ulf (Clay Technology AB, Lund (Sweden))

2010-01-15

During its lifetime, a KBS-3 repository will be subject to various ambient temperatures. Backfilled tunnels, shafts and investigation bore holes closest to ground level will experience periods of temperature below 0 deg C. From a safety assessment perspective, it is therefore essential to understand the behavior of compacted bentonite below 0 deg C. A theoretical framework for predicting the pressure response in compacted water saturated bentonite due to temperature changes has been developed based on thermodynamics and a single pore-type. This model predicts an approximately linear temperature dependence of swelling pressure P{sub s}(w,DELTAT) = P{sub s}(w,0 deg C) + DELTAs(w)DELTAT/nu{sub clay}(w) where DELTAT denotes a temperature difference from 0 deg C, DELTAs(w) is the difference in partial molar entropy between clay water and bulk water, nu{sub clay} (w) is the partial molar volume of the clay water and w denotes the water/solid mass ratio of the clay. As bulk water changes phase at 0 deg C, DELTAs(w) has a different value dependent on whether DELTAT is negative or positive. Above 0 deg C DELTAs(w) is a small value for all relevant densities which means that the pressure response due to temperature changes is small. A further consequence of this fact is that DELTAs(w) is a large positive number below 0 deg C when the external water phase is transformed to ice. Consequently, the model predicts a large drop of swelling pressure with temperature below 0 deg C, in the order of 1.2 MPa/deg C. Specifically, the swelling pressure is zero at a certain (negative) temperature T{sub C}. T{sub C} also quantifies the freezing point of the bentonite sample under consideration, as ice formation in the bentonite does not occur until swelling pressure is lost. A large set of laboratory tests have been performed where fully water saturated samples of bentonites have been exposed to temperatures in the range -10 deg C to +25 deg C. The swelling pressure response has been

BaM bentonite and some of its properties

International Nuclear Information System (INIS)

Matal, Oldřich; Vávra Michal; Kachlík, Martin; Maca, Karel; Kotnour, Petr; Pospíšková, Ilona

2018-01-01

BaM bentonite is lime-magnesium bentonite of domestic origin. Its properties were measured experimentally with focus on the following parameters: composition, morphology and particle size distribution, powder bulk density, powder pressing parameters, shear strength, and water saturation. The findings will find use in nuclear safety assessments of engineered bentonite barriers in underground nuclear waste disposal facilities. (orig.)

Influence of ionic strength on the viscosities and water loss of bentonite suspensions containing polymers

Directory of Open Access Journals (Sweden)

Luciana Viana Amorim

2007-03-01

Full Text Available A study was made of the influence of ionic strength (S on the apparent (AV and plastic (PV viscosities and water loss (WL of sodium bentonite suspension with polymers. Na-bentonite was dispersed in water (4.86% w/w of different ionic strengths (S = 0.0, 0.015, 0.030 and 0.045 M followed by the addition of polymer. Three polymer samples were studied, i.e., low viscosity carboxymethyl cellulose (CMC BV, polyanionic cellulose (PAC, and partially hydrolyzed polyacrylamide (HPAM. The results indicated that the presence of salts and increased salinity greatly influence the apparent and plastic viscosities and water loss of bentonite suspensions with polymer.

Geochemical processes and compacted bentonite FEBEX with a thermohydraulic gradient with a thermohydraulic gradient

International Nuclear Information System (INIS)

Leguey Jimenez, S.; Cuevas Rodriguez, J.; Martin Barca, M.; Vigil de la Villa Mencia, R.; Ramirez Martin, S.; Garcia Gimenez, R.

2002-01-01

At present, the main source of High Level radioactive Waste (HLW) is the electrical energy production during all sep of developing. In almost all the countries with nuclear programs, the option for the final management of HLW is the Deep Geological Repository (DGR), based on the concept of multi barrier. According to this concept, the wastes is isolated from biosphere by the interposition of confinement barrier. In the context of an investigation of the near field for a repository of HLW, the FEBEX Project, a set of laboratory test has been designed to give a better understanding of the thermo-hydro-mechanical and geochemical behaviour of the compacted bentonite as a confinement barrier. The object of these work is to analyse the properties of the bentonite and its behaviour under conditions that will be found in a repository. The precipitation of mineral phases, due to local changes in the chemical equilibrium and the hydration itself, can produce changes in the salinity of the interstitial water and in the microstructural organisation of the clay particles. the hydraulic and mechanical properties of the bentonite can be modified by the special conditions of the barrier. (Author)

Bentonite erosion. Laboratory studies

Energy Technology Data Exchange (ETDEWEB)

Jansson, Mats (Div. of Nuclear Chemistry, Royal Inst. of Technology, Stockholm (Sweden), School of Chemical Science and Engineering)

2009-11-15

This report covers the laboratory studies that have been performed at Nuclear Chemistry, KTH in the project 'Bentonite Erosion'. Many of the experiments in this report were performed to support the work of the modelling group and were often relatively simple. One of the experiment series was performed to see the impact of gravity and concentration of mono- and di-valent cations. A clay suspension was prepared in a test tube. A net was placed in contact with the suspension, the test tube was filled with solutions of different concentrations and the system was left overnight to settle. The tube was then turned upside down and the behaviour was visually observed. Either the clay suspension fell through the net or stayed on top. By using this method surprisingly sharp determinations of the Critical Coagulation (Flocculation) Concentration (CCC/CFC) could be made. The CCC/CFC of Ca2+ was for sodium montmorillonite determined to be between 1 and 2 mM. An artificial fracture was manufactured in order to simulate the real case scenario. The set-up was two Plexiglas slabs separated by 1 mm thick spacers with a bentonite container at one side of the fracture. Water was pumped with a very low flow rate perpendicular to bentonite container and the water exiting the fracture was sampled and analyzed for colloid content. The bentonite used was treated in different ways. In the first experiment a relatively montmorillonite rich clay was used while in the second bentonite where only the readily soluble minerals had been removed was used. Since Plexiglas was used it was possible to visually observe the bentonite dispersing into the fracture. After the compacted bentonite (1,000 kg/m3) had been water saturated the clay had expanded some 12 mm out into the fracture. As the experiment progressed the clay expanded more out into the fracture and seemed to fractionate in two different phases with less material in the outmost phase. A dark rim which was later analyzed to contain

Research program to study the gamma radiation effects in Spanish bentonites

International Nuclear Information System (INIS)

Dies, J.; Tarrasa, F.; Cuevas de las, C.; Miralles, L.; Pueyo, J. J.

2000-01-01

The engineering barrier of a radioactive waste underground disposal facility, placed in a granitic host rock, will consist of a backfill of compacted bentonite blocks. At first, this material will be subjected to a gamma radiation field, from the waste canister, and heat from the spent fuel inside the canister. Moreover, any groundwater that reaches the repository will saturate the bentonite. For these reasons the performance of the engineered barrier must be carefully assessed in laboratory experiments. (Author)

Experimental characterization of cement-bentonite interaction using core infiltration techniques coupled with 4D X-ray tomography

International Nuclear Information System (INIS)

Dolder, F.; Maeder, U.; Jenni, A.

2012-01-01

Document available in extended abstract form only. Deep geological disposal of radioactive waste foresee cementitious materials as reinforcement of tunnels, backfill, or as waste matrix. Bentonite, or sand-bentonite mixtures, are proposed as backfill material enclosing spent fuel drums, or as drift seals. The emplacement of cementitious material next to clay material generates an enormous chemical gradient in pore water, which drives diffusive transport. Laboratory studies and reactive transport modeling predict significant mineral alteration on both sides of interfaces, mainly resulting in a decrease of porosity in bentonite. The goal of the project is to characterize and quantify the cement/bentonite skin effects spatially and temporally. The expected analytical data set will be amenable to interpretation by reactive transport modeling. The project focuses on the advective-diffusive transport domain, resolved at intermediate spatial scales. The experiments are carried out in a newly developed X-ray transparent core infiltration apparatus, constructed from carbon fiber compounds and suitable for confining and infiltration pressures up to 80 bars. This setup allows to performing X-ray computed tomography scans (CT) periodically without interrupting the running core infiltration experiment. The experiment is performed on cylindrical bentonite samples (50 by 50 mm) compacted and saturated in-house with a dedicated device (Fig. 1, top). A sample is mounted in the core infiltration apparatus (Fig. 1, bottom) and subjected to a confining pressure in order to simulate underground repository conditions proposed by NAGRA (Swiss National Cooperative for the Disposal of Radioactive Waste). The infiltration of high-pH cement pore-fluids into the bentonite plug is expected to alter the mineral assemblage over time as an advancing reaction front. The related change in phase densities, porosity and bulk density is tracked over time recording periodically non-destructive CT scans

A coupled THMC model of a heating and hydration laboratory experiment in unsaturated compacted FEBEX bentonite

Energy Technology Data Exchange (ETDEWEB)

Zheng, L.; Samper, J.; Montenegro, L.; Fernandez, A.M.

2010-05-01

Unsaturated compacted bentonite is foreseen by several countries as a backfill and sealing material in high-level radioactive waste repositories. The strong interplays between thermal (T), hydrodynamic (H), mechanical (M) and chemical (C) processes during the hydration stage of a repository call for fully coupled THMC models. Validation of such THMC models is prevented by the lack of comprehensive THMC experiments and the difficulties of experimental methods to measure accurately the chemical composition of bentonite porewater. We present here a non-isothermal multiphase flow and multicomponent reactive solute transport model for a deformable medium of a heating and hydration experiment performed on a sample of compacted FEBEX bentonite. Besides standard solute transport and geochemical processes, the model accounts for solute cross diffusion and thermal and chemical osmosis. Bentonite swelling is solved with a state-surface approach. The THM model is calibrated with transient temperature, water content and porosity data measured at the end of the experiment. The reactive transport model is calibrated with porewater chemical data derived from aqueous extract data. Model results confirm that thermal osmosis is relevant for the hydration of FEBEX bentonite while chemical osmosis can be safely neglected. Dilution and evaporation are the main processes controlling the concentration of conservative species. Dissolved cations are mostly affected by calcite dissolution-precipitation and cation exchange reactions. Dissolved sulphate is controlled by gypsum/anhydrite dissolution-precipitation. pH is mostly buffered by protonation/deprotonation via surface complexation. Computed concentrations agree well with inferred aqueous extract data at all sections except near the hydration boundary where cation data are affected by a sampling artifact. The fit of Cl{sup -} data is excellent except for the data near the heater. The largest deviations of the model from inferred aqueous

Long-term alteration of bentonite in the presence of metallic iron

Energy Technology Data Exchange (ETDEWEB)

Kumpulainen, S.; Kiviranta, L. [B and Tech Oy, Helsinki (Finland); Carlsson, T.; Muurinen, A. [VTT Technical Research Centre of Finland, Espoo (Finland); Svensson, D. [Svensk Kaernbraenslehantering AB (SKB), Stockholm (Sweden); Sasamoto, Hiroshi; Yui, Mikatzu [Japan Atomic Energy Agency (JAEA) (Japan); Wersin, P.; Rosch, D. [Gruner Ltd, Basel (Switzerland)

2011-12-15

According to the KBS-3H concept, each copper canister containing spent nuclear fuel will be surrounded by a bentonite buffer and a perforated steel cylinder. Since steel is unstable in wet bentonite, it will corrode and the corrosion products will interact with the surrounding bentonite in ways that are not fully understood. Such interaction may seriously impair the bentonite's functioning as a buffer material, e.g. by lowering its CEC or decreasing its swelling capacity. This report presents results from two ironbentonite experiments carried out under quite different conditions at VTT (Finland) and JAEA (Japan). Both studies focused on long-term iron-bentonite interactions under anaerobic conditions. The study at VTT comprised eight years long experiments focused on diffusive based interactions between solid cast-iron and compacted MX-80 bentonite (dry density 1.5- 1.6 g/cm{sup 3}) in contact with an aqueous 0.5 M NaCl solution. The study at JAEA comprised ten years long batch experiments, each involving a mixture of metallic iron powder (25 g), an industrially refined Na bentonite, Kunipia F, which contains more than 99% montmorillonite (25 g), and an aqueous solution (250 mL). Samples were sent to B and Tech in airtight steel vessels filled with N{sub 2} and subsequently analyzed at various laboratories in Finland and Sweden. The JAEA samples differed with regard to the initial solution chemistry, which was either distilled water, 0.3 M NaCl, 0.6 M NaCl, 0.1 M NaHCO{sub 3}, or 0.05 M Na{sub 2}SO{sub 4}. The analyses of the MX-80 bentonite samples were carried out on samples containing a cast iron cylinder and also on corresponding background samples with no cast iron. In addition, the external solution and gas phase in contact with the bentonite were analyzed. Briefly, the gas contained H{sub 2}, most possibly caused by corrosion of the cast iron, and CO{sub 2}, mainly as a result of carbonate dissolution. The eight years old external solution exhibited

Sorption properties of bentonite clays towards Pu(IV), U(VI), Np(V) and Cs: experimental and surface complexation study

Energy Technology Data Exchange (ETDEWEB)

Sabodina, M.N. [Institute of Physical Chemistry of Russian Academy of Science, Moscow 119192 (Russian Federation); Kalmykov, St.N.; Sapozhnikov, Yu.A. [Radiochemistry div., Chemistry dept., Lomonosov Moscow State University, Moscow 119992, (Russian Federation); Gupalo, T.A.; Beigul, V.P. [VNIPI Promtechnology, Moscow (Russian Federation)

2005-07-01

Full text of publication follows: Sorption of radionuclides, their diffusion in bentonite as well as its solubility are the major factors that define bentonite as a geochemical barrier. Sorption of cations by bentonite could be governed by two mechanisms including ion exchange with interlayer cations and formation of surface complexes with either silanol or aluminol groups. The aim of this work was to study mechanisms of {sup 137}Cs, Pu(IV), Np(V) and U(VI) sorption by bentonite and their solubility in bentonite pore waters. Bentonite (Khakassiya deposit) used in the experiments was taken in Na-form and characterized by powder X-ray diffraction, scanning electron microscopy, potentiometric titration. The cation exchange capacities of bentonite at pH=6 were measured by isotopic exchange with {sup 22}Na{sup +} and Cs{sup +} saturation. Sorption experiments were performed in N{sub 2} atmosphere in plastic vials. Bentonite samples were left in the working solutions to swell for few days before sorption experiments were performed. After the desired concentration of radionuclide ({sup 137}Cs, {sup 238}Pu, {sup 239}Pu, {sup 237}Np, {sup 239}Np, {sup 238}U) was added to the suspension, the required pH values are established and samples were left until the equilibrium was reached. Separation of solution after the sorption was performed using micro- and ultrafiltration techniques. The sorption of Pu(IV), U(VI) and Np(V) was highly pH dependent that indicates predominant surface complexation mechanism of sorption. For {sup 137}Cs the pH dependence of sorption was less pronounced and significant decrease of sorption occurs at pH<1.7 that indicate the ion exchange as the major mechanism. The equilibrium constant of Na{sup +}/Cs{sup +} exchange was calculated form sorption isotherms and pH dependence of sorption. It is established using micro- and ultra-filtrations, that sorption of radionuclides onto bentonite nano colloids is essential. Surface complexation modeling exercises

Diffusion, sorption, and retardation processes of anions in bentonite and organo-bentonites for multibarrier systems

Science.gov (United States)

Schampera, Birgit; Dultz, Stefan

2013-04-01

The low permeability, high cation exchange capacity (CEC) and plasticity of bentonites favor their use in multibarrier systems of waste deposits [1]. Bentonites have a high CEC but their ability to sorb anions is very low. There is, however, need for retardation of anions and organic pollutants in many applications. Bentonites, modified with certain organic cations, have the capacity to sorb anions and non-polar organic compounds in addition to cations. Investigations on organically modified clays address a wide variety of applications including immobilization of pollutants in contaminated soils, waste water treatment and in situ placement for the protection of ground water [2]. Many experiments on anion and cation sorption of organo-clays were conducted in the batch mode which does not reflect solid-liquid ratios and material densities in barrier systems. Diffusion experiments on compacted clays allow the evaluation of transport processes and sorption of pollutants at conditions relevant for repositories. For organo-clays only few diffusion studies are published e.g. [3] measured the diffusion of tritium and [4] the diffusion of H2O in bentonite and organo-bentonites. The organic cation hexadecylpyridinium (HDPy) was added to Wyoming bentonite (MX-80) in amounts corresponding to 2-400 % of the CEC. The uptake of organic cations was determined by the C-content, XRD and IR-spectroscopy. Wettability was analyzed by the contact angle. Physical, chemical and mineralogical properties of clays were characterized. Diffusion experiments were carried out in situ in a cell attached to the ATR-unit of a FTIR-spectrometer. For H2O-diffusion the compacted organo-clays are saturated first with D2O, afterwards H2O is supplied to the surface at the top of the clay platelet. Anion-diffusion was conducted with NO3--solution instead of H2O only having characteristic IR band positions at 1350 cm-1. Three different concentrations (0.25M, 0.5M and 1M) were used. Additional batch

Effect of material parameters on the compactibility of backfill materials

International Nuclear Information System (INIS)

Keto, P.; Kuula-Vaeisaenen, P.; Ruuskanen, J.

2006-05-01

The effect of different parameters on compactibility of mixture of bentonite and ballast as well as Friedland-clay was studied in laboratory with two different types of compaction tests. The material parameters varied were grain size distribution of the ballast material, grain shape, water ratio and bentonite content (15/30%). The other parameters varied were salinity of the mixing water, mixing process and compaction method and energy. Ballast materials with varying grain size distributions were produced from Olkiluoto mica-gneiss with different type of crushing processes. In addition, sand was chosen for ballast material due to its uniform grain size distribution and rounded grain shape. The maximum grain size of the ballast materials was between 5-10 mm. When comparing the compactibility of ballast materials, the highest dry densities were gained for ballast materials with graded grain size distribution. The compaction behaviour of the tested bentonite ballast mixtures is dominated by the bentonite content. The other parameters varied did not have significant effect on the compactibility of the mixtures with bentonite content of 30%. This can be explained with the amount of bentonite that is higher than what is needed to fill up the volume between the ballast grains. The results gained with the two different compaction tests are comparable. Both the bentonite/ballast mixtures and the Friedland clay behaved similarly when compacted with three different compaction pressures (180, 540 and 980 kPa). (orig.)

Physico-chemical properties of water in bentonite

International Nuclear Information System (INIS)

Torikai, Yuji; Sato, Seichi; Ohashi, Hiroshi

1994-01-01

As a part of safety analysis on ground layer disposal, in order to estimate nuclides migration behavior from engineering shielding materials, it is required to modelize migration process of nuclides in bentonite and chemical species relating to corrosion, to estimate solubility and to specify application condition of geochemical calculation code. In this study, as a part of elucidation of nuclide migration process, physico-chemical properties of water in bentonite and montmorillonite using steam pressure method were determined. As a result, following items were found: (1) Even if 1/3 of water in bentonite is near free water, it is far from a region dealable with dilute solution in the electrolyte solution theory. And, (2) the water in bentonite has generally small activity in comparison with dilute solution, then has smaller solubility than estimation value of calculation code. (G.K.)

γ-radiation induced corrosion of copper in bentonite-water systems under anaerobic conditions

Science.gov (United States)

Karin Norrfors, K.; Björkbacka, Åsa; Kessler, Amanda; Wold, Susanna; Jonsson, Mats

2018-03-01

In this work we have experimentally studied the impact of bentonite clay on the process of radiation-induced copper corrosion in anoxic water. The motivation for this is to further develop our understanding of radiation-driven processes occurring in deep geological repositories for spent nuclear fuel where copper canisters containing the spent nuclear fuel will be embedded in compacted bentonite. Experiments on radiation-induced corrosion in the presence and absence of bentonite were performed along with experiments elucidating the impact irradiation on the Cu2+ adsorption capacity of bentonite. The experiments presented in this work show that the presence of bentonite clay has no or very little effect on the magnitude of radiation-induced corrosion of copper in anoxic aqueous systems. The absence of a protective effect similar to that observed for radiation-induced dissolution of UO2 is attributed to differences in the corrosion mechanism. This provides further support for the previously proposed mechanism where the hydroxyl radical is the key radiolytic oxidant responsible for the corrosion of copper. The radiation effect on the bentonite sorption capacity of Cu2+ (reduced capacity) is in line with what has previously been reported for other cations. The reduced cation sorption capacity is partly attributed to a loss of Al-OH sites upon irradiation.

Corrosion behavior of carbon steel in wet Na-bentonite medium

International Nuclear Information System (INIS)

Yeon, Jae-Won; Ha, Young-Kyoung; Choi, In-Kyu; Chun, Kwan-Sik

1996-01-01

Corrosion behaviors of carbon steel in wet Na-bentonite medium were studied. Corrosion rate of carbon steel in wet bentonite was measured to be 20 μm/yr at 25 deg C using the AC impedance technique. This value is agreed with that obtained by weight loss at 40 deg C for 1 year. The effect of bicarbonate ion on the corrosion of carbon steel in wet bentonite was also evaluated. The carbon steels in wet bentonite having 0.001, 0.01, and 0.1 M concentration of bicarbonate ion gave corrosion rates of 20, 8, and 0.2 μm/yr, respectively. Corrosion potentials of specimens were also measured and compared with the AC impedance results. Both results indicated that bicarbonate ion could effectively reduce the corrosion rate of carbon steels in bentonite due to the formation of protective layer on the carbon steel. (author)

Modelling gas migration in compacted bentonite: gambit club phase 3. Final report

International Nuclear Information System (INIS)

Hoch, A.R.; Cliffe, K.A.; Swift, B.T.; Rodwell, W.R.

2004-04-01

This report describes the third phase of a programme of work to develop a computational model of gas migration through highly compacted water-saturated bentonite. One difficulty with this endeavour is the definitive determination of the mechanism of the gas migration from the available experimental data. The report contains a brief review of the experimental data and their interpretation. The model development work reported involves the investigation of two ways of enhancing a model proposed in the previous phase of the programme. This model was based on the concept that gas migration pathways were created by consolidating the clay fabric by application of gas pressure to create porosity through which the gas could flow. The two developments of this model that are separately explored in this work are: (a) The incorporation of a proper treatment of the stress-strain behaviour of the clay in (b) response to gas migration. The previous model had only considered stress effects through simple volume changes to the clay fabric. The inclusion of a dual-porosity feature into the model in an attempt to address the role that the clay fabric might play in gas migration through the clay, in particular the role that pre-existing interstack voids might have in gas migration. The consideration of hysteresis effects was also included in this study. As in previous GAMBIT Club work, the models are tested against the results of laboratory experiments. (orig.)

Evaluation for swelling characteristics of buffer and backfill materials for high-level nuclear waste disposal. Influence of sand-bentonite content and cation compositions in bentonite

International Nuclear Information System (INIS)

Komine, Hideo; Ogata, Nobuhide

1999-01-01

Compacted bentonite and sand-bentonite mixture are attracting greater attention as buffer and backfill materials for disposal pits and access tunnels in the underground facilities for repositories of high-level nuclear waste. Buffer and backfill materials must have the swelling characteristics and are expected to fill up the space between these materials and surrounding ground by swelling. This role is called as 'Self-sealing'. To design the specifications, such as dry density, bentonite content and size, of buffer and backfill materials for the disposal facilities of high-level nuclear wastes described above, we must evaluate the swelling characteristics of compacted bentonite and sand-bentonite mixtures. For this purpose, this study proposed the evaluation formula for swelling characteristics of buffer and backfill materials containing bentonite. This study derived new equations for evaluating the relationship between the swelling deformation of compacted bentonite and sand-bentonite mixtures, and the swelling behavior of montmorillonite minerals, which are swelling clay minerals. This study also proposed new equations for evaluating the ion compositions of bentonite, ion concentration of pore water and the specific surface of bentonite, which significantly influence the swelling characteristics of buffer and backfill materials. The evaluation formula proposed in this study is presented by combining the above-mentioned new equations with theoretical equations, of which are the Gouy-Chapman diffuse double layer theory and the van der Waals force, of repulsive and attractive forces of montmorillonite minerals. (author)

Experimental studies on the interactions between anaerobically corroding iron and bentonite

Energy Technology Data Exchange (ETDEWEB)

Carlson, Liisa (Geological Survey of Finland, Espoo (Finland)); Karnland, Ola; Olsson, Siv (Clay Technology AB, Lund (Sweden)); Rance, Andy; Smart, Nick (Serco Assurance, Hook (United Kingdom))

2008-06-15

Anaerobic corrosion experiments using compacted bentonite, carbon steel and cast iron coupons, and carbon steel wires, were performed at temperatures of 30 deg C and 50 deg C. Dry Wyoming bentonite MX-80 powder was mixed with pieces of wire, and then compacted in stainless steel holders. The samples were evacuated and placed in test cells under nitrogen. For the coupon tests, the coupons were placed in the upper and lower part of cells filled with compacted bentonite. The compacted bentonite samples were immersed in deaerated artificial ground water containing sodium chloride and sodium carbonate at pH 10.4. The experiments with coupons ran for 356 days at 50 deg C and for 900 days at 30 deg C and the experiments with wires ran for 829 days at 30 deg C and for 911 days at 50 deg C. Corrosion products on the surface of wires and coupons were examined using Raman spectroscopy, scanning electron microscopy and electron microprobe analysis. A mixture of magnetite, hematite and goethite was found on the surface of coupons. Only magnetite was observed on the surface of wires. The bentonite was examined using X-ray diffraction (XRD), scanning electron microscopy (SEM), electron microprobe analysis (EPMA), Raman spectroscopy, Moessbauer transmission spectroscopy, Fourier transform infrared spectroscopy (FTIR) and transmission electron microscopy (TEM) with energy dispersive spectroscopy (EDS) and selected area electron diffraction. In addition, cation exchange capacity and exchangeable cations as well as total chemical composition were determined. Hydraulic conductivity and swelling pressure were also measured. In the coupon tests, increased iron contents could be observed in a thin contact zone. Sodium from the synthetic ground water had substituted for a fraction of the calcium in the interlayer positions of montmorillonite, which could be seen also in the total contents of these elements. A small increase in hydraulic conductivity was observed. In the wire tests a high

Studies on mechanical behavior of bentonite for development of the constitutive model

International Nuclear Information System (INIS)

Sasakura, Tsuyoshi; Kuroyanagi, Mikio; Okamoto, Michitaka

2002-02-01

To integrate the system for evaluation of long-term hydraulic condition in near field of TRU waste disposal, series of laboratory tests were conducted to investigate the effect of (1) cation exchange of Na-bentonite for Ca ion, and (2) the swelling behavior of bentonite, on its mechanical and hydraulic properties. For the purpose of this study, same lot of bentonite was used in a series of tests to obtain consistent data. A constitutive model of clayey materials, called Cam-clay model, was expanded conceptually to express the effects mentioned above. The research results of this year are summarized below; 1) Some basic properties such as cation exchange capacity, particle density, grain size distribution, compaction-characteristics and water content were obtained. To examine the effect of previous swelling history of bentonite on its swelling characteristics and hydraulic and mechanical properties, specimens, which generated swelling deformation to various volumetric strain levels, were specially prepared and used in the following tests. Swelling pressure tests, swelling deformation tests, permeability tests were conducted to observe one dimensional swelling characteristics and hydraulic properties of Na-bentonite and Ca-bentonite. High-pressured triaxial consolidated-undrained (CU) compression tests and high-pressured consolidation tests were also carried out to investigate the compression, swelling, and shearing behavior of each type of bentonite. 2) As indicated in previous studies, two important phenomena (1) bentonite possesses remarkable swelling capacity, (2) cation exchange of Na-bentonite for Ca-ion lead increasing of hydraulic conductivity, were confirmed in the test results. From the swelling deformation test results and published data, it was found that swelling capacity of bentonite has no dependency on previous swelling history and it could be easily expressed as a function of void ratio e. It was also confirmed that swelling pressure and water

Permeability of highly compacted bentonite

International Nuclear Information System (INIS)

Pusch, R.

1980-12-01

The object of the study was the water flow through the bentonite which is caused by hydraulic gradients. The study comprised laboratory tests and theoretical considerations. It was found that high bulk densities reduced the permeability to very low values. It was concluded that practically impervious conditions prevail when the gradients are low. Thus with a regional gradient of 10 -2 and a premeability of 10 -13 m/s the flow rate will not be higher than approximately 1 mm in 30 000 years. (G.B.)

Effects of repository environment on diffusion behavior of radionuclides in buffer materials

International Nuclear Information System (INIS)

Kozaki, Tamotsu; Sato, Seichi

2004-03-01

Compacted bentonite is considered as a candidate buffer material in the geological disposal of high-level radioactive waste. An important function of the compacted bentonite is to retard the transport of radionuclides from waste forms to the surrounding host rock after degradation of an overpack. Therefore, diffusion behavior of radionuclides in the compacted bentonite has been extensively studied by many researchers for the performance assessments of the geological disposal. However, diffusion mechanism of radionuclides in the bentonite cannot be fully understood, and most experimental data have been obtained at room temperature for the bentonite saturated with low salinity water, which would disagree often with real repository conditions. In this study, therefore, apparent diffusion coefficients were determined at various diffusion temperatures for chloride ions in Na-montmorillonite samples saturated with NaCl solution of high salinity. Activation energies for the apparent diffusion were also obtained from the temperature dependence of the diffusion coefficients at different salinity. As the salinity increased, the apparent diffusion coefficients of chloride ions in montmorillonite were found to increase slightly. On the other hand, the activation energies for the chloride diffusion were found to be almost constant (approximately 12 kJ mol -1 ) and less than that in free water (17.4 kJ mol -1 ). Effects of salinity on diffusion behavior of radionuclides in montmorillonite were discussed from the viewpoints of microstructure of montmorillonite and distribution of ions in the montmorillonite. As a result, the diffusion behavior of sodium ions could be explained by the changes of the predominant diffusion process among pore water diffusion, surface diffusion, and interlayer diffusion that could be caused by the increase of salinity. (author)

Swelling and hydraulic properties of Ca-bentonite for the buffer of a waste repository

International Nuclear Information System (INIS)

Lee, J.O.; Cho, W.J.; Kang, C.H.; Chun, K.S.

2001-01-01

Swelling and hydraulic tests were carried out to provide the information for the selection of buffer material in a radioactive waste repository. Ca-bentonite and de-ionized water were used for the tests. The swelling pressures of compacted bentonite were in the wide range of 0.7 Kg/cm 2 to 190.2 Kg/cm 2 , and they largely increased with an increase in the dry density and bentonite content. However, the swelling pressures decreased with increasing the initial water content and beyond about 12 wt.% of the initial water content, leveled off to a nearly constant value. The hydraulic conductivities were lower than 10 -11 m/s for the compacted bentonite with the dry density higher than 1.4 Mg/m 3 . They increased with increasing temperature in the range of 20 deg. C to 150 deg. C. (author)

Mineralogical behaviour of bentonites in open and closed systems

International Nuclear Information System (INIS)

Herbert, H.J.; Kasbohm, J.

2004-01-01

Mineralogical and chemical changes of bentonites were investigated in a natural analogue study and in laboratory experiments. As a working hypothesis we assumed that in geological, i.e. open systems, bentonites may be penetrated over geological time scales by larger water volumes than high compacted bentonites used as technical barriers in repositories in salt formations. Under this assumption open geological systems are characterised by low solid/liquid ratios and closed repository systems by high solid/liquid ratios. Consequently in laboratory experiments the mineralogical changes were investigated under different solid/liquid ratios and compared with results of a natural analogue study. In the natural analogue study in deep boreholes in the East Slovakian Basin the expandability of montmorillonite and the degree of transformation in illite-smectite (IS) mixed layer structures was found to be dependent not only on depth and temperature but also on the salinity of the pore waters. In this open geological system with a comparatively low solid/liquid ratio the observed changes in the montmorillonite were significantly different than those observed in the laboratory study on compacted MX-80 bentonite. (authors)

Influence factors of sand-bentonite mixtures on hydraulic conductivity

International Nuclear Information System (INIS)

Chen Yonggui; Ye Weimin; Chen Bao; Wan Min; Wang Qiong

2008-01-01

Buffer material is a very important part of the engineering barrier for geological disposal of high-level radioactive nuclear waste. Compacted bentonite is attracting greater attention as buffer and backfill material because it offer impermeability and swelling properties, but the pure compacted bentonite strength decreases with increasing hydration and these will reduce the buffer capability. To solve this problem, sand is often used to form compacted sand-bentonite mixtures (SBMs) providing high thermal conductivity, excellent compaction capacity, long-time stability, and low engineering cost. As to SBMs, hydraulic conductivity is a important index for evaluation barrier capability. Based on the review of research results, the factors affecting the hydraulic conductivity of SBMs were put forward including bentonite content, grain size distribution, moisture content, dry density, compacting method and energy, and bentonite type. The studies show that the hydraulic conductivity of SBMs is controlled by the hydraulic conductivity of the bentonite, it also decreases as dry density and bentonite content increase, but when the bentonite content reach a critical point, the influence of increasing bentonite to decrease the hydraulic conductivity is limited. A fine and well-graded SBMs is likely to have a lower hydraulic conductivity than a coarse and poorly graded material. The internal erosion or erodibility based on the grain size distribution of the SBMs has a negative effect on the final hydraulic conductivity. The lowest hydraulic conductivity is gained when the mixtures are compacted close to optimum moisture content. Also, the mixtures compacted at moisture contents slightly above optimum values give lower hydraulic conductivity than when compacted at slightly under the optimum moisture content. Finally, discussion was brought to importance of compaction method, compacting energy, and bentonite type to the hydraulic conductivity of SBMs. (authors)

Bentonite in the repository - Manufacture of bentonite blocks. A literature study

International Nuclear Information System (INIS)

Hultgren, Aa.

1995-09-01

Activities in nuclear power countries are reviewed, concerning developments in the use of bentonite for backfilling in nuclear waste repositories, in particular regarding manufacture of bentonite-blocks. Only one report was found which in detail describes the manufacture of highly compacted blocks of bentonite. Use of bentonite for sealing boreholes etc in the oil- and gas industry was also covered in the literature study. 19 refs, 3 tabs

Near Field sorption Data Bases for Compacted MX-80 Bentonite for Performance Assessment of a High-Level Radioactive Waste Repository in Opalinus Clay Host Rock

Energy Technology Data Exchange (ETDEWEB)

Bradbury, M.; Baeyens, B

2003-08-01

Bentonites of various types and compacted forms are being investigated in many countries as backfill materials in high-level radioactive waste disposal concepts. Nagra is currently considering an Opalinus clay (OPA) formation in the Zuercher Weinland as a potential location for a high-level radioactive waste repository. A compacted MX-80 bentonite is foreseen as a potential backfill material. Performance assessment studies will be performed for this site and one of the requirements for such an assessment are sorption data bases (SDB) for the bentonite near-field. The purpose of this report is to describe the procedures used to develop the SDB. One of the pre-requisites for developing a SDB is a water chemistry for the compacted bentonite porewater. For a number of reasons mentioned in the report, and discussed in more detail elsewhere, this is not a straightforward task. There are considerable uncertainties associated with the major ion concentrations and in particular with the system pH and Eh. The MX-80 SDB was developed for a reference bentonite porewater (pH = 7.25) which was calculated using the reference OPA porewater. In addition, two further SDBs are presented for porewaters calculated at pH values of 6.9 and 7.9 corresponding to lower and upper bound values calculated for the range of groundwater compositions anticipated for the OPA host rock. 'In house' sorption isotherm data were measured for Cs(I), Ni(II), Eu(III), Th(IV), Se(IV) and 1(-1) on the 'as received' MX-80 material equilibrated with a simulated porewater composition. Complementary 'in house' sorption edge and isotherm measurements on conditioned Na/Ca montmorillonites were also available for many of these radionuclides. These data formed the core of the SDB. Nevertheless, some of the required sorption data still had to be obtained from the open literature. An important part of this report is concerned with describing selection procedures and the modifications

Thermodynamic understanding on swelling pressure of bentonite buffer

International Nuclear Information System (INIS)

Sato, Haruo

2007-01-01

Smectite (montmorillonite) is a major clay mineral constituent of the bentonite buffer and backfilling materials to be used for the geological disposal of high-level radioactive waste. Swelling pressure of the bentonite buffer occurring in the permeation process of moisture was estimated based on thermodynamic theory and the thermodynamic data of interlayer water in smectite in this study. The relative partial molar Gibbs free energies (ΔG H2O ) of water on the smectite surface were measured as a function of water content (0-83%) in a dry density range of 0.6-0.9 Mg/m 3 . Purified Na-smectite of which interlayer cations were exchanged with Na + ions and soluble salts were completely removed, was used in this study. Obtained ΔG H2O decreased with an increase of water content in the range of water content lower than about 40%, and similar trends were obtained to data of Kunipia-F bentonite (Na-bentonite) of which smectite content was approximately 100 wt.%. From the specific surface area of smectite (ca. 800 m 2 /g) and the correlation between ΔG H2O and water content, water affected from the surface of smectite was estimated to be up to approximately 2 water layers. Swelling pressure versus smectite partial density (montmorillonite partial density) was estimated based on ΔG H2O from the chemical potential balance of water in equilibrium between the free water and moisturized smectite, and compared to data measured for various kinds of bentonites of which smectite contents were respectively different. The estimated swelling pressures were in good agreement with the measured data. (author)

Multi-scale Study of Pollutant Transport and Uptake in Compacted Bentonite

OpenAIRE

Bouchelaghem , Fatiha; Pusch , R.

2018-01-01

International audience; In a previous work, a multiscale model was developed in order to investigate the impact of cation exchange and surface complexation on the hydraulic conductivity of compacted bentonite. Simulation of lead nitrate percolation tests has displayed the strong connection between hydraulic conductivity increase and textural and structural evolutions at different scales. The present developments deal with the modeling of pollutant transport by advection, molecular diffusion w...

Interaction between rock, bentonite buffer and canister. FEM calculations of some mechanical effects on the canister in different disposal concepts

International Nuclear Information System (INIS)

Boergesson, L.

1992-07-01

An important task of the buffer of highly compacted bentonite is to offer a mechanical protection to the canister. This role has been investigated by a number of finite element calculations using the complex elasto plastic material models for the bentonite that have been developed on the basis of laboratory tests and adapted to the code ABAQUS. The following main functions and scenarios have been investigated for some different canister types and repository concepts: - The effect of the water and swelling pressure, - The effect of a rock shear perpendicular to the canister axis, - The effect of creep in the copper after a rock shear displacement, - The thermomechanical effects when an initially saturated buffer is used

Numerical modeling of radionuclide migration in water-saturated planar fracture: study of performance of bentonite in the far-field region

Energy Technology Data Exchange (ETDEWEB)

Silveira, Claudia S. da; Alvim, Antonio C.M., E-mail: csilveira@con.ufrj.b [Universidade Federal do Rio de Janeiro (PEN/COPPE/UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-Graduacao de Engenharia. Programa de Energia Nuclear

2011-07-01

The analysis of radionuclide migration in fractured porous media is an important part of the safety assessment of a deep geologic disposal for high level radioactive wastes. In this work, numerical solution for simple geometry was developed to study radionuclide migration, including decay chain from a hypothetical repository, whereas the initial region of fracture is filled with bentonite which expanded from EBS (Engineered Barrier System). The following cases were considered: convective transport with constant velocity along the fracture, longitudinal hydrodynamic dispersion in the fracture along the fracture axis, molecular diffusion from fracture into rock matrix, sorption within rock matrix, sorption onto the surface of the fracture, radioactive decay, decay chain, and diffusion in bentonite extrusion region. For conservative analysis, the porous matrix adjacent to the fracture was subdivided into two different subdomains, each with different set of parameters and considering that the radionuclides were available for migration in the solubility limit, at fracture inlet, from the initial time. The partial differential equations that govern the physical system were discretized by finite differences, by using the Implicit Euler Method with forward scheme in the convective term. In this study, numerical simulation was performed for 100, 1000 and 10000 years, with and without bentonite extrusion, in order to compare the migration retardation obtained by bentonite located at the beginning of the fracture in saturated environment. The numerical simulation results showed the importance of extruded area in the far field region of the fractured host rock. (author)

Numerical modeling of radionuclide migration in water-saturated planar fracture: study of performance of bentonite in the far-field region

International Nuclear Information System (INIS)

Silveira, Claudia S. da; Alvim, Antonio C.M.

2011-01-01

The analysis of radionuclide migration in fractured porous media is an important part of the safety assessment of a deep geologic disposal for high level radioactive wastes. In this work, numerical solution for simple geometry was developed to study radionuclide migration, including decay chain from a hypothetical repository, whereas the initial region of fracture is filled with bentonite which expanded from EBS (Engineered Barrier System). The following cases were considered: convective transport with constant velocity along the fracture, longitudinal hydrodynamic dispersion in the fracture along the fracture axis, molecular diffusion from fracture into rock matrix, sorption within rock matrix, sorption onto the surface of the fracture, radioactive decay, decay chain, and diffusion in bentonite extrusion region. For conservative analysis, the porous matrix adjacent to the fracture was subdivided into two different subdomains, each with different set of parameters and considering that the radionuclides were available for migration in the solubility limit, at fracture inlet, from the initial time. The partial differential equations that govern the physical system were discretized by finite differences, by using the Implicit Euler Method with forward scheme in the convective term. In this study, numerical simulation was performed for 100, 1000 and 10000 years, with and without bentonite extrusion, in order to compare the migration retardation obtained by bentonite located at the beginning of the fracture in saturated environment. The numerical simulation results showed the importance of extruded area in the far field region of the fractured host rock. (author)

Small-scale bentonite injection test on rock

International Nuclear Information System (INIS)

Pusch, R.

1978-03-01

When radiactive waste is disposed a sealing of the rock is very valuable since it reduces the rate of water percolation and diffusion. In an earlier report injection of bentonite gels by means of over-pressure and subsequent electrophoresis has been suggested. The present report describes a rock test series where bentonite injection was applied. For the test an approximately cubical block of about 1 m 3 was selected. The rock type was diorite with a fairly high frequency of quartz denses. The block was kept in a basin during the test in order to maintain the water saturation. Holes were bored in the block. A bentonite slurry with 1000 percent water content was injected. It was shown that the bentonite had a sealing effect but the depth of extrusion into rock joints was not large because of gelation. Electro-Kinetic injection of montmorillonite was found to be a more promising technique for rock lightening

Effect of pH to adsorption behavior of Pu on bentonite in aqueous environment

International Nuclear Information System (INIS)

Wang Xiaoqiang; Tuo Xianguo; Li Pingchuan; Leng Yangchun; Su Jilong; Yueping

2013-01-01

The effects of pH to the adsorption behavior of Pu in GMZ-bentonite, Lingshou Ca-bentonite, Na-bentonite and bleaching earth were tested by static adsorption experiments in aqueous environment. The results show that the adsorption equilibrium time of Pu is four days in GMZ-bentonite and 5-6 days in bleaching earth, Ca-bentonite and Na-bentonite. In aqueous environment, the adsorption capacity of bentonite to Pu increases with pH in water phase, and it is weak in acidic aqueous environment and strong in alkaline aqueous environment extremely. (authors)

Hydro-mechanical and gas transport properties of bentonite blocks - role of interfaces

International Nuclear Information System (INIS)

Popp, Till; Roehlke, Christopher; Salzer, Klaus; Gruner, Matthias

2012-01-01

sealing elements. The investigations consist of: - long-term water injection tests in a new designed oedometer cell with different sample constellations under well controlled stress and swelling conditions to provide data about - time dependent interface 'permeability' changes during long-term compaction and fluid injection - gas entry pressures and relative gas permeability changes during pressure dependent gas injection; - shear tests to quantify mechanical interface properties of pre-saturated bentonite blocks under well controlled shear forces or displacements. As initial characterization both, triaxial and direct strength tests were performed, which allow to separate between matrix and interface properties. The investigations are being performed in the framework of the pan-European project FORGE project which aims on the generation and movement of repository gases. Results and interpretation The performed lab investigations cover a wide field of hydro-mechanical properties of bentonite blocks, which represent a favorable option for constructing sealing plugs in different host rock environments. Based on the experimental results the following conclusions can be drawn: - At dry conditions gas flow along interfaces is at least 4 orders higher than through the matrix. Increase of confinement significantly lowers the gas flow but the effect is more pronounced for interfaces → crack sealing. - Saturation of bentonite block assembly, i.e. blocks with a common interface, is not affected by the interfaces and only weakly by the acting confining pressure. - During gas injection a significant effect is only observed if the minimal stress is passed resulting in some minor gas flow. - The gas break through results in stationary inflow but no significant effect on the total stress is measured, probably due to the central gas injection. - The measured gas threshold pressures under constant volume conditions significantly exceed the sum of the swelling pressure and externally

Evaluation of hydraulic conductivities of bentonite and rock under hyper alkaline and nitrate conditions. 2

International Nuclear Information System (INIS)

Iriya, Keishiro; Fujii, Kensuke; Kubo, Hiroshi

2003-02-01

Circumstance of TRU waste repository shows alkaline condition due to leaching of cementitious materials. The waste containing significant soluble nitrate may changes ground water chemistry to high ion strength. Several experimental studies have been carried out in this study in order to assess quantitatively water conductivity of bentonite which is altered by hyper alkaline and nitrate. Modeling for previous results is carried out and several requirements to be defined are proposed. The conclusion of this study is summarized as below. Secondary minerals of bentonite alteration due to hyper alkaline with nitrate: 1) CSH and CAH were observed corresponding to solving montmorillonite in AWN solution. 2) Na 2 O Al 2 O 3 1.68SiO 2 generated from 90 days in batch experiment and it was observed in 360 days. Assessment of swelling and water conductivity changing by hyper alkaline with nitrate: 1) Little changing of water conductivity of bentonite was observed by saturated Ca(OH) 2 solution and hyper alkaline solution. The conductivity significantly increased by penetrating sodium nitrate solution. 2) Water conductivity of ion exchanged bentonite by hyper alkaline solution significantly increased. It increased more by penetrating AWN solution. Modeling of tuff alteration by hyper alkaline solution: 1) Flow through test is proposed since soluble velocity to hyper alkaline solution should be defined. (author)

Aespoe Hard Rock Laboratory. The use of focused ion beams for structural characterisation of bentonite. A feasibility study

Energy Technology Data Exchange (ETDEWEB)

Wegden, Marie; Kristiansson, Per (Division of Nuclear Physics, Lund Inst. of Technology (Sweden)); Svensson, Daniel; Sjoeland, Anders (Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden))

2009-07-01

Bentonite clay is planned to be used in the KBS-3 concept for future nuclear high level waste (HLW) repository in Sweden. In the concept the spent nuclear fuel is placed in an iron insert, which is encapsulated in a copper canister. The copper canister is embedded in compacted bentonite and deposited at 500 m depth in granite bedrock. The compacted bentonite will act as a buffer material, giving mechanical support for the copper canister, reducing water movements and capturing potentially escaping radionuclides. Bentonite contains high amounts of smectite minerals (most common is montmorillonite), which are swelling clay minerals. The smectite minerals are layered and have the ability to store water in its structure. This is done by intercalating water between the layers and expanding the interlayer distance. The exceptional swelling capacity makes bentonite a suitable buffer material that works as a sealant and barrier. Heterogeneity in the material, compaction and in swelling may result in porosity, both on the nano- and micrometre scale. This may affect the permeability of the clay and may mediate the transport of radionuclides, cations and corrosion products. The aim of this work is to investigate the feasibility of using common ion beam techniques for structural characterisation of bentonite, including studying the mineral composition and the coarse porosity. The analytical techniques used were scanning transmission ion microscopy (STIM), particle-induced X-ray emission (PIXE) and elastic p-p scattering, performed at the Lund Nuclear Microprobe. On-axis STIM analysis was performed in order to measure and map the areal mass density of the sample. Since it was impossible to differentiate an increase in thickness from an area of higher mass density, as well as discerning depth variations, the STIM analysis was also performed in tomographic mode, in an attempt to obtain 3D structural information. The tomographic reconstruction showed that the bentonite had an

Aespoe Hard Rock Laboratory. The use of focused ion beams for structural characterisation of bentonite. A feasibility study

International Nuclear Information System (INIS)

Wegden, Marie; Kristiansson, Per; Svensson, Daniel; Sjoeland, Anders

2009-01-01

Bentonite clay is planned to be used in the KBS-3 concept for future nuclear high level waste (HLW) repository in Sweden. In the concept the spent nuclear fuel is placed in an iron insert, which is encapsulated in a copper canister. The copper canister is embedded in compacted bentonite and deposited at 500 m depth in granite bedrock. The compacted bentonite will act as a buffer material, giving mechanical support for the copper canister, reducing water movements and capturing potentially escaping radionuclides. Bentonite contains high amounts of smectite minerals (most common is montmorillonite), which are swelling clay minerals. The smectite minerals are layered and have the ability to store water in its structure. This is done by intercalating water between the layers and expanding the interlayer distance. The exceptional swelling capacity makes bentonite a suitable buffer material that works as a sealant and barrier. Heterogeneity in the material, compaction and in swelling may result in porosity, both on the nano- and micrometre scale. This may affect the permeability of the clay and may mediate the transport of radionuclides, cations and corrosion products. The aim of this work is to investigate the feasibility of using common ion beam techniques for structural characterisation of bentonite, including studying the mineral composition and the coarse porosity. The analytical techniques used were scanning transmission ion microscopy (STIM), particle-induced X-ray emission (PIXE) and elastic p-p scattering, performed at the Lund Nuclear Microprobe. On-axis STIM analysis was performed in order to measure and map the areal mass density of the sample. Since it was impossible to differentiate an increase in thickness from an area of higher mass density, as well as discerning depth variations, the STIM analysis was also performed in tomographic mode, in an attempt to obtain 3D structural information. The tomographic reconstruction showed that the bentonite had an

Bentonite engineered barrier building method for radioactive waste on sub-surface disposal test project

International Nuclear Information System (INIS)

Mori, Takuo; Takahashi, Shinichi; Takeuchi, Kunifumi; Namiki, Kazuto

2008-01-01

The engineering barriers such as clay and concrete materials are planned to use for covering radioactive waste in cavern-type disposal facility. The requirement to clay barrier is very low permeability, which could be satisfied by high density Bentonite, and such a compaction method will be needed. Two methods, compaction and air shot, were tested in engineering scale for constructing a high-density clay barrier. Two types of compaction equipments, 'Teasel plate' and 'Plate compacter', were developed and engineering scale experiments were performed for compacting Bentonite only and Bentonite-sand-aggregate mixture. As a result, the Teasel plate can reach higher density Bentonite in relatively short time in comparison to other equipments. While, regarding air shot method, an air-shot machine in a tunnel construction site was tested by different water adding methods (wet, dry, and half wet). It is concluded that the dry and half wet constructing methods will achieve reasonable workability. As a result, the best construction option can be chosen according to the locations of radioactive waste facility. (author)

Changes in hydraulic conductivity of sand-bentonite mixtures accompanied with alkaline alteration

International Nuclear Information System (INIS)

Yamaguchi, Tetsuji; Sawaguchi, Takuma; Tsukada, Manabu; Tanaka, Tadao

2012-01-01

Document available in extended abstract form only. Montmorillonite is the main constituent of bentonite clay buffer materials in radioactive waste repositories. Highly alkaline environments induced by cement based materials are likely to alter montmorillonite, and to deteriorate the physical and/or chemical properties of the buffer materials. The deterioration may cause variation in hydraulic conductivity of the buffer and induce major uncertainties in the radionuclide migration analysis. Empirical data on the variation of hydraulic conductivity are, however, scarce mainly because the alteration of compacted buffer materials, sand-bentonite mixture specimen, is extremely slow (1). In this study, laboratory experiments were performed to observe changes in hydraulic conductivity of sand-bentonite mixtures accompanied with their alkaline alteration using NaOH based solutions at 80 - 90 deg. C. Our preliminary attempt to degrade sand-bentonite mixture by permeating alkaline solutions was unsuccessful, in which the flow rate of water became unstable. This was interpreted as an artifact due to generation and stagnation of air in the mixture specimen. The water conduction experimental apparatus was modified by removing membrane filter and leaving only sintered stainless steel filter, and by equipping the pressurizing tank with a preheater. Three types of experiments were performed afterwards. Series-1: Multi step alteration / water-conduction experiments. Two sand-bentonite mixture specimens with 50 mm in diameter, 10 mm in thickness and 1,600 kg m -3 in dry density were applied to hydraulic conductivity measurement and alkaline alteration process alternately. The mixture ratio was 1:1 in dry weight. The hydraulic conductivity was determined by permeating the specimens with 1.0 mol L -1 NaCl solution at 40 deg. C. While the specimens were immersed in Si, Al and Ca-adjusted 1.0 mol L -1 NaOH solution at 90 deg. C to allow alteration. In the final water-conduction step, the

Thermodynamic modelling of bentonite-groundwater interaction and implications for near field chemistry in a repository for spent fuel

International Nuclear Information System (INIS)

Wanner, H.; Wersin, P.; Sierro, N.

1992-11-01

Predictions of near field geochemistry are made using a thermodynamic model for bentonite/ground interaction. This model is a refinement and extension of the model developed by the senior author. It is based on recent experiments performed at high solid/water ratio and adapted to the Swedish type of HLW repository design. Thus, from the obtained experimental results on solution composition, the model includes chemical reactions resulting from both the impurities and the main clay fraction within the bentonite. Ion exchange reactions are treated both with and without the contribution of edge sites. Due to its thermodynamic basis, the model exhibits prediction capability over a wide range of conditions in terms of solid/water ratio. The modelling of repository conditions implies, due to the lack of experimental information, simplifications with regard to thermodynamic properties of the bentonite. This mainly involves the non-consideration of the temperature effects and of the acid/base properties of the solid. Nevertheless, our results yield insight into important processes affecting porewater chemistry. Thus, the model suggests that proton exchange reactions may exert a strong control on calcite dissolution within highly compacted bentonite. Estimations of chemical changes over time in the bentonite were done in the basis of a mixing tank model. These results indicate transformation of Na-bentonite to Ca-bentonite over time. The extent of this process, however, critically depends on the amount of carbonate present in the bentonite. (authors) (34 refs.)

Laboratory studies on the effect of freezing and thawing exposure on bentonite buffer performance: Closed-system tests

Energy Technology Data Exchange (ETDEWEB)

Schatz, T.; Martikainen, J. [B and Tech Oy, Helsinki (Finland)

2010-12-15

This report presents a set of results from laboratory studies on the effect of freezing and thawing on compacted bentonite buffer material. In order to evaluate the effect of freezing and thawing on compacted bentonite buffer performance a series of experiments were conducted using closed, constant-volume cells as follows: Pre- and post-freezing swelling pressure measurements were performed on fully saturated MX-80 and Deponit CA-N bentonite samples, at dry density values of approximately 1.6 g/cm{sup 3}, over five freeze/thaw cycles from room temperature to -18 deg C with rapid (instantaneous) temperature exposure. Pressure measurements were performed on fully saturated MX-80 bentonite samples, at dry density values of 1.470 and 1.501 g/cm{sup 3}, during a temperature run from room temperature to -10 deg C with step-change temperature exposure and back from -10 deg C to room temperature under continuous temperature change exposure at 0.1 deg C/h. Pressure measurements were performed on fully saturated MX-80 bentonite samples, encompassing a range of dry density values from 0.940 to 1.534 g/cm{sup 3}, during repeated temperature runs from room temperature to -10 deg C and back with continuous temperature change exposure at 0.1 deg C/h. Pressure measurements were performed on a fully saturated Deponit CA-N bentonite sample, at a dry density of 1.484 g/cm{sup 3}, during a temperature run from room temperature to -10 deg C and back with continuous temperature change exposure at 0.1 deg C/h. In some cases, hydraulic conductivity measurements were performed before and after freeze/thaw exposure. In general, exposure to freezing temperatures, down to an average temperature of -10 deg C, results in the development of significant internal pressures in compacted bentonite samples, which is attributed to the formation of ice. The specific test results are summarised as follows: Increases in pressure by factors of 1.5 to 2.2 were observed for MX-80 samples at dry densities

Geochemical investigation of iron transport into bentonite as steel corrodes

International Nuclear Information System (INIS)

Hunter, Fiona; Bate, Fiona; Heath, Tim; Hoch, Andrew

2007-09-01

some experiments. Using the experimental data as a guide, a modelling investigation has been carried out. The objectives of the modelling investigation were: To develop a geochemical model of the transport of iron into bentonite based on the clear experimental evidence of the penetration of iron into bentonite. To improve our understanding of the desaturation of the bentonite as water is consumed during the corrosion process and the resultant gas(es) escapes. The production of iron from the corroding source was modelled using a rate of gas evolution that had been fitted. It was shown that ion exchange and surface complexation processes do not provide sufficient sorption to predict the high amount of iron observed in the solid phase. Therefore alternative processes, such as iron-containing mineral formation or mineral transformations, were also suggested to account for the amount of iron observed within the bentonite phase. Magnetite was identified as the most thermodynamically stable solubility limiting phase under the experimental conditions. A one-dimensional transport model was constructed to include all relevant processes. The simulations considered the diffusive transport of Fe 2+ ions away from a corroding source, using the rate of gas evolution resulting from the corrosion process. Ion exchange and surface complexation processes were allowed within the bentonite which would provide sorption of iron onto and within the bentonite solid. The pH was buffered by allowing protonation and deprotonation of the surface sites of the bentonite solid. In addition, saturation of iron-containing minerals was permitted. The base case model suggests that about 4.4 wt % of iron could form in the bentonite if the formation of magnetite was allowed. However, the maximum theoretical amount of iron available from the source term is limited to 4.5 wt % of iron by the cumulative gas evolution rate, which is lower than the observed amount of iron in the bulk bentonite (6.6 wt %). A

Geochemical investigation of iron transport into bentonite as steel corrodes

Energy Technology Data Exchange (ETDEWEB)

Hunter, Fiona; Bate, Fiona; Heath, Tim; Hoch, Andrew [Serco Assurance, Harwe ll (United Kingdom)

2007-09-15

some experiments. Using the experimental data as a guide, a modelling investigation has been carried out. The objectives of the modelling investigation were: To develop a geochemical model of the transport of iron into bentonite based on the clear experimental evidence of the penetration of iron into bentonite. To improve our understanding of the desaturation of the bentonite as water is consumed during the corrosion process and the resultant gas(es) escapes. The production of iron from the corroding source was modelled using a rate of gas evolution that had been fitted. It was shown that ion exchange and surface complexation processes do not provide sufficient sorption to predict the high amount of iron observed in the solid phase. Therefore alternative processes, such as iron-containing mineral formation or mineral transformations, were also suggested to account for the amount of iron observed within the bentonite phase. Magnetite was identified as the most thermodynamically stable solubility limiting phase under the experimental conditions. A one-dimensional transport model was constructed to include all relevant processes. The simulations considered the diffusive transport of Fe{sup 2+} ions away from a corroding source, using the rate of gas evolution resulting from the corrosion process. Ion exchange and surface complexation processes were allowed within the bentonite which would provide sorption of iron onto and within the bentonite solid. The pH was buffered by allowing protonation and deprotonation of the surface sites of the bentonite solid. In addition, saturation of iron-containing minerals was permitted. The base case model suggests that about 4.4 wt % of iron could form in the bentonite if the formation of magnetite was allowed. However, the maximum theoretical amount of iron available from the source term is limited to 4.5 wt % of iron by the cumulative gas evolution rate, which is lower than the observed amount of iron in the bulk bentonite (6.6 wt

Review on cation exchange selectivity coefficients for MX-80 bentonite

International Nuclear Information System (INIS)

Domenech, C.; Arcos, D.; Duro, L.; Sellin, P.

2005-01-01

Full text of publication follows: Bentonite is considered as engineered barrier in the near field of a nuclear waste repository due to its low permeability, what impedes groundwater flow to the nuclear waste, and its high retention capacity (sorption) of radionuclides in the eventuality of groundwater intrusion. One of the main retention processes occurring at the bentonite surface is ion exchange. This process may exert a strong control on the mobility of major pore water cations. Changes in major cation concentration, especially calcium, can affect the dissolution-precipitation of calcite, which in turn controls one of the key parameters in the system: pH. The cation exchange process is usually described according to the Gaines-Thomas convention: Ca 2+ + 2 NaX = CaX 2 + 2 Na + , K Ca = (N Ca x a 2 Na + )/(N 2 Na x a Ca 2+ ) where K Ca is the selectivity coefficient for the Ca by Na exchange, ai is the activity of cation 'i' in solution and NJ the equivalent fractional occupancy of cation 'J' in bentonite. Parameters such as solid to liquid (S:L) ratio and dry density of the solid have an important influence on the value of selectivity coefficients (K ex ). Although in most geochemical modelling works, K ex values are directly taken from experiments conducted at low S:L ratios and low dry densities, the expected conditions in a deep geological nuclear waste repository are higher S:L and higher bentonite density (1.6 g.cm -3 in the SKB design to obtain a fully water saturated density of around 2.0 g.cm -3 ). Experiments focused at obtaining selectivity coefficients under the conditions of interest face the difficulty of achieving a proper extraction and analyses of pore water without disturbing the system by the sampling method itself. In this work we have conducted a complete analyses of published data on MX-80 bentonite cationic exchange in order to assess the effect of the S:L ratio and dry density on the value of the selectivity coefficients determined so far

Diffusion in compacted betonite

International Nuclear Information System (INIS)

Muurinen, A.; Rantanen, J.

1985-01-01

The objective of this report is to collect the literature bearing on the diffusion in compacted betonite, which has been suggested as possible buffer material for the disposal of spent fuel. Diffusion in a porous, water-saturated material is usually described as diffusion in the pore-water where sorption on the solid matter can delay the migration in the instationary state. There are also models which take into consideration that the sorbed molecules can also move while being sorbed. Diffusion experiments in compacted bentonite have been reported by many authors. Gases, anions, cations and actinides have been used as diffusing molecules. The report collects the results and the information on the measurement methods. On the basis of the results can be concluded that different particles possibly follow different diffusion mechanisms. The parameters which affect the diffusion seem to be for example the size, the electric charge and the sorption properties of the diffusing molecule. The report also suggest the parameters to be used in the diffusion calculation of the safety analyses of spent fuel disposal. (author)

Diffusion of strongly sorbing cations (60Co and 152Eu) in compacted FEBEX bentonite

International Nuclear Information System (INIS)

Garcia-Gutierrez, M.; Cormenzana, J. L.; Missana, T.; Alonso, U.; Mingarro, M.

2011-01-01

Diffusion experiments in compacted FEBEX bentonite were performed with strongly sorbing radionuclides, 60 Co and 152 Eu. Diffusion experiments with these radionuclides present several difficulties: first of all these tests are very time consuming because of the high sorption on the clays, secondly these elements not only present high sorption onto clays but also on diffusion cells, tubing, filters and reservoirs, typically used in the classical through-diffusion or in-diffusion methods, which makes difficult the interpretation of the results. In this study, the experiments were performed using the instantaneous planar source method, where a paper filter tagged with a tracer is placed between two tablets of compacted bentonite. The apparent diffusion coefficient (D a ) is obtained analysing the tracer concentration profile in the samples at the end of the experiment, both with an analytical and a numerical approach. The ranges of D a values obtained from these experiments in the FEBEX clay compacted at 1.65 g/cm 3 are (0.5-2.3) x 10 -13 m 2 /s for Co and (0.8-2.5) x 10 -14 m 2 /s for Eu. Results showed that the analytical solution is able to fit reasonably well the Eu concentration profiles, whereas Co concentration profiles show a different behavior, not straightforward to explain, which was also analyzed by numerical methods. (authors)

Modifications in Compacted MX-80 Bentonite Due to Thermo-Hydraulic Treatment

International Nuclear Information System (INIS)

Gomez-Espina, R.; Villar, M. V.

2013-01-01

The thermo-hydraulic tests reproduce the thermal and hydraulic conditions to which bentonite is subjected in the engineered barrier of a deep geological repository of radioactive waste. The results of thermo-hydraulic test TBT1500, which was running for approximately 1500 days, are presented. This is a continuation to the Technical Report Ciemat 1199, which presented results of test TBT500, performed under similar conditions but with duration of 500 days. In both tests the MX-80 bentonite was used with initial density and water content similar to those of the large-scale test TBT. The bentonite column was heated at the bottom at 140 degree centigrade and hydrated on top with deionized water. At the end of the test a sharp water content gradient was observed along the column, as well as an inverse dry density gradient. Hydration modified also the bentonite microstructure. Besides, an overall decrease of the smectite content with respect to the initial value took place, especially in the most hydrated areas where the percentage of interest ratified illite increased and in the longer test. On the other hand, the content of cristobalite, feldspars and calcite increased. Smectite dissolution processes (probably colloidal) occurred, particularly in the more hydrated areas and in the longer test. Due to the dissolution of low-solubility species and to the loss of exchangeable positions in the smectite, the content of soluble salts in the pore water increased with respect to the original one, especially in the longer test. The solubilized ions were transported; sodium, calcium, magnesium and sulphate having a similar mobility, which was in turn lower than that of potassium and chloride. The cationic exchange complex was also modified. (Author)

Transport and leaching of technetium and uranium from spent UO2 fuel in compacted bentonite clay

International Nuclear Information System (INIS)

Ramebaeck, H.; Albinsson, Y.; Skaalberg, M.; Eklund, U.B.; Kjellberg, L.; Werme, L.

2000-01-01

The transport properties of Tc and U in compacted bentonite clay and the leaching behaviour of these elements from spent nuclear fuel in the same system were investigated. Pieces of spent UO 2 fuel were embedded in bentonite clay (ρ d =2100 kg/m 3 ). A low saline synthetic groundwater was used as the aqueous phase. After certain experimental times, the bentonite clay was cut into 0.1 mm thick slices, which were analysed for their content of Tc and U. Measurements were made using inductively coupled plasma mass spectrometry. Tc analysis comprised chemical separation. The analysis of U was done by means of detecting 236 U, since the natural content of U in bentonite clay made it impossible to distinguish between U originating from the fuel and the clay. The influence of different additives mixed into the clay was studied. The results showed an influence on both transport and leaching behaviour when metallic Fe was mixed into the clay. This indicates that Tc and U are reduced to their lower oxidation states as a result of this additive

Geochemical modelling of bentonite porewater in high-level waste repositories

Science.gov (United States)

Wersin, Paul

2003-03-01

The description of the geochemical properties of the bentonite backfill that serves as engineered barrier for nuclear repositories is a central issue for perfomance assessment since these play a large role in determining the fate of contaminants released from the waste. In this study the porewater chemistry of bentonite was assessed with a thermodynamic modelling approach that includes ion exchange, surface complexation and mineral equilibrium reactions. The focus was to identify the geochemical reactions controlling the major ion chemistry and acid-base properties and to explore parameter uncertainties specifically at high compaction degrees. First, the adequacy of the approach was tested with two distinct surface complexation models by describing recent experimental data performed at highly varying solid/liquid ratios and ionic strengths. The results indicate adequate prediction of the entire experimental data set. Second, the modelling was extended to repository conditions, taking as an example the current Swiss concept for high-level waste where the compacted bentonite backfill is surrounded by argillaceous rock. The main reactions controlling major ion chemistry were found to be calcite equilibrium and concurrent Na-Ca exchange reactions and de-protonation of functional surface groups. Third, a sensitivity analysis of the main model parameters was performed. The results thereof indicate a remarkable robustness of the model with regard to parameter uncertainties. The bentonite system is characterised by a large acid-base buffering capacity which leads to stable pH-conditions. The uncertainty in pH was found to be mainly induced by the pCO 2 of the surrounding host rock. The results of a simple diffusion-reaction model indicate only minor changes of porewater composition with time, which is primarily due to the geochemical similarities of the bentonite and the argillaceous host rock. Overall, the results show the usefulness of simple thermodynamic models to

Thermo-hydro-mechanical tests of buffer material

International Nuclear Information System (INIS)

Pintado, X.; Hassan, Md. M.; Martikainen, J.

2013-10-01

MX-80 bentonite is the reference clay material for the buffer component planned to be used in the deep geological repository for the disposal of spent nuclear fuel in Finland. The buffer presents complex thermo-hydro-mechanical behavior which is modeled with different constitutive models for heat flow, water flow and stress-strain evolution in the buffer. Thermo, hydro and mechanical models need parameters to evaluate the THM-behavior. These modeling parameters were determined by performing series of laboratory experiments as follows: Water retention curve tests were performed on compacted bentonite samples, encompassing a range of initial dry density values from 1397 to 1718 kg/m 3 as the initial water content was around of 5-8 %. The water retention curve was determined by imposing different suctions to the samples and the suctions were then checked using capacitive hygrometer and chilled mirror psychrometer. Oedometer tests were performed on compacted bentonite samples, encompassing a range of initial dry density values from 1590 to 1750 kg/m 3 as the initial water content was around of 6 %. Samples were saturated with tap water, 35 or 70 g/L salt solutions. Infiltration tests were performed on compacted unsaturated bentonite samples, encompassing a range of initial dry density values from 1400 to 1720 kg/m 3 as the initial water content was approximately between 4-7 %. Samples were saturated with tap water, 0.87, 35 or 70 g/L salt solutions. Tortuosity tests were performed on bentonite samples, encompassing a range of dry density values from 1460 to 1750 kg/m 3 and the degree of saturation varied between 33-93 %. Thermal conductivity tests were performed on compacted bentonite samples, encompassing a range of dry density values from 1545 to 1715 kg/m 3 and the degree of saturation varied between 31-88 %. The measurement was performed using a thermal needle probe. The general trend of all analyzed parameters was as expected when dry density, water content, and

Thermo-hydro-mechanical tests of buffer material

Energy Technology Data Exchange (ETDEWEB)

Pintado, X.; Hassan, Md. M.; Martikainen, J. [B and Tech Oy, Helsinki (Finland)

2013-10-15

MX-80 bentonite is the reference clay material for the buffer component planned to be used in the deep geological repository for the disposal of spent nuclear fuel in Finland. The buffer presents complex thermo-hydro-mechanical behavior which is modeled with different constitutive models for heat flow, water flow and stress-strain evolution in the buffer. Thermo, hydro and mechanical models need parameters to evaluate the THM-behavior. These modeling parameters were determined by performing series of laboratory experiments as follows: Water retention curve tests were performed on compacted bentonite samples, encompassing a range of initial dry density values from 1397 to 1718 kg/m{sup 3} as the initial water content was around of 5-8 %. The water retention curve was determined by imposing different suctions to the samples and the suctions were then checked using capacitive hygrometer and chilled mirror psychrometer. Oedometer tests were performed on compacted bentonite samples, encompassing a range of initial dry density values from 1590 to 1750 kg/m{sup 3} as the initial water content was around of 6 %. Samples were saturated with tap water, 35 or 70 g/L salt solutions. Infiltration tests were performed on compacted unsaturated bentonite samples, encompassing a range of initial dry density values from 1400 to 1720 kg/m{sup 3} as the initial water content was approximately between 4-7 %. Samples were saturated with tap water, 0.87, 35 or 70 g/L salt solutions. Tortuosity tests were performed on bentonite samples, encompassing a range of dry density values from 1460 to 1750 kg/m{sup 3} and the degree of saturation varied between 33-93 %. Thermal conductivity tests were performed on compacted bentonite samples, encompassing a range of dry density values from 1545 to 1715 kg/m{sup 3} and the degree of saturation varied between 31-88 %. The measurement was performed using a thermal needle probe. The general trend of all analyzed parameters was as expected when dry

Leaching of spent fuel in simulated disposal condition and separation of plutonium species as a function of oxidation state

International Nuclear Information System (INIS)

Kim, Seung Soo; Chun, Kwan Sik; Kang, Chul Hyung

2000-11-01

The influences of compacted bentonite on the leaching of spent fuel in bentonite-saturated ground water at room temperature were investigated by analyzing the components of leachates as well as the alterated surface of them. And the plutonium species was separated by ion exchangers. The amounts of Cs, Sb, Sr, Am, Ru, Pu and U released from spent fuel by bentonite-saturated solution for the initial 165 days were 2.0, 0.2, 0.2, 0.02, 0.005, 5x10 - 4, 0.05 % of inventory, respectively. These values correspond to several ∼ several tens times as much as those through bentonite block which were compacted to 1.4 g/cm 3 . The comparison of the cesium released in groundwater and bentonite-saturated solution through bentonite block is simular values, whose lower concentration in leachant indicates that most of radionuclides are retained by compacted bentonite, even though alkali metal such as Cs. The separation of plutonium species as a function of oxidation state by ion exchanger was succeed by two columns' method with packing materials as SiO - , SiO-SO 3 -

Sealing efficiency of an argillite-bentonite plug subjected to gas pressure, in the context of deep underground nuclear waste storage

International Nuclear Information System (INIS)

Liu, Jiang-Feng

2013-01-01

In France, the deep underground nuclear waste repository consists of a natural barrier (in an argillaceous rock named argillite), associated to artificial barriers, including plugs of swelling clay (bentonite)-sand for tunnel sealing purposes. The main objective of this thesis is to assess the sealing efficiency of the bentonite-sand plug in contact with argillite, in presence of both water and gas pressures. To assess the sealing ability of partially water-saturated bentonite/sand plugs, their gas permeability is measured under varying confining pressure (up to 12 MPa). It is observed that tightness to gas is achieved under confinement greater than 9 MPa for saturation levels of at least 86-91%. We than assess the sealing efficiency of the bentonite-sand plug placed in a tube of argillite or of Plexiglas-aluminium (with a smooth or a rough interface). The presence of pressurized gas affects the effective swelling pressure at values P gas from 4 MPa. Continuous gas breakthrough of fully water-saturated bentonite-sand plugs is obtained for gas pressures on the order of full swelling pressure (7-8 MPa), whenever the plug is applied along a smooth interface. Whenever a rough interface is used in contact with the bentonite-sand plug, a gas pressure significantly greater than its swelling pressure is needed for gas to pass continuously. Gas breakthrough tests show that the interface between plug/argillite or the argillite itself are two preferential pathways for gas migration, when the assembly is fully saturated. (author)

HM modelling of in-situ gas injection tests in bentonite and argillite: the PGZ experiment

International Nuclear Information System (INIS)

Gerard, P.; Charlier, R.; Radu, J.P.; La Vaissiere, R. de; Talandier, J.; Collin, F.

2010-01-01

Document available in extended abstract form only. During long-term repository of high and intermediate level nuclear waste in deep argillaceous geological formation, steel containers will corroded and organic material will be irradiated. The two processes lead mostly to hydrogen production. This study deals with the numerical modelling of the gas migration in both the host formation and a bentonite plug, with an emphasis on coupling between the gas transfer and the mechanical strains and stresses. More particularly the study aims to support the design of the PGZ in situ experiment that will be performed by Andra in its underground laboratory at Bure. The objective of the experiment is the analysis of the dynamics of the bentonite plug re-saturation, studying the competition between the liquid water coming from the argillite and a gas injection. The modelled experiment consists of a borehole drilled in rock clay, inside which a plug of MX-80 bentonite is set. The bentonite is naturally re-saturated by water coming from the host formation. At the same time a gas pressure, higher than the initial water pressure in the host rock, is imposed at both ends of the plug. The developed model takes into account the coupling between the mechanical behaviour and the water and gas transfers in undisturbed geo-materials. It manages explicitly liquid and vapour water, gaseous and dissolved hydrogen. Elastoplastic and non-linear elastic model are used to model the behaviour of, respectively, the argillaceous rock and the bentonite. The numerical results show the small desaturation obtained in bentonite and argillite. The influence of the coupling of the mechanic on the water and gas transfers is thus limited (due to the Bishop's effective stress). The swelling of the bentonite plug is not hindered by the gas migration and the confining effect of the engineered barrier is maintained. An analysis is made of the influence of the main transfer rock properties on the gas pressure

Calculation of saturated hydraulic conductivity of bentonite

International Nuclear Information System (INIS)

He Jun

2006-01-01

Hydraulic conductivity test has some defects such as weak repeatability, time-consuming. Taking bentonite as dual porous media, the calculation formula of the distance, d 2 , between montmorillonite in intraparticle pores is deduced. Improved calculated method of hydraulic conductivity is obtained using d 2 and Poiseuille law. The method is valid through the comparison with results of test and other methods. The method is very convenient to calculate hydraulic conductivity of bentonite of certain montmorillonite content and void ratio. (authors)

Quality control and characterization of bentonite materials

International Nuclear Information System (INIS)

Kiviranta, L.; Kumpulainen, S.

2011-12-01

Before bentonite material is taken into use in performance testing, the quality of the material needs to be checked. Three high grade bentonite materials: two natural Nabentonites from Wyoming, and one natural Ca-bentonite from Milos, were characterized. Each material was characterized using duplicate or triplicate samples in order to study variability in material quality in batches. The procedure consisted of basic acceptance testing (water ratio, CEC, swelling index, liquid limit, and granule size distribution), advanced acceptance testing (exchangeable cations, chemical and mineralogical composition, density, swelling pressure and hydraulic conductivity) and complementary testing (herein surface area, water absorption capacity, montmorillonite composition, grain size distribution and plastic limit). All three materials qualified the requirements set for buffer bentonite for CEC, smectite content, swelling pressure, and hydraulic conductivity. Wyoming bentonites contained approximately 88 wt.% of smectite, and Milos bentonite 79 wt.% of smectite and 3 wt.% of illite. Precision of smectite analyses was ±2 %, and variances in composition of parallel samples within analytical errors, at least for Wyoming bentonites. Accuracy of quantitative analyses for trace minerals such as gypsum, pyrite or carbonates, was however low. As the concentrations of these trace minerals are important for Eh or pH buffering reactions or development of bentonite pore water composition, normative concentrations are recommended to be used instead of mineralogically determined concentrations. The swelling pressures and hydraulic conductivities of different materials were compared using EMDD. Swelling pressure was relatively higher for studied Cabentonite than for the studied Na-bentonites and the difference could not be explained with different smectite contents. Hydraulic conductivities seemed to be similar for all materials. The results of index tests correlated with the smectite content

Thermal conductivity tests on buffermasses of bentonite/silt

International Nuclear Information System (INIS)

Knutsson, S.

1977-09-01

The investigation concerns the thermal conductivity of the bentonite/quartz buffer mass suggested as embedding substance for radioactive canisters. The first part presents the theoretical relationships associated with the various heat transfer mechanisms in moist granular materials. Chapter 3 describes the author's experimental determination of the thermal conductivity of the buffer mass. The tested mass consisted of 10 percent (by weight) bentonite and 90 percent natural silt. Four tests were made with different water content values and degree of water saturation. A comparison between the measured and calculated thermal conductivities is given. It is shown that the conductivity can be calculated with an accuracy of +-20 percent. (author)

MX-80 Bentonite. Thermal-Hydro-Mechanical Characterisation Performed at CIEMAT in the Context of the Prototype Project

International Nuclear Information System (INIS)

Villar, M. V.

2005-01-01

This document details the results of the thermo-hydro-mechanical (THM) characterisation of the commercial MX-80 bentonite performed by CIEMAT from 2001 to 2004 in the context of a project carried out at the AEspoe Hard Rock Laboratory (Sweden), the Prototype Repository. The swelling pressure and the permeability of the bentonite compacted to different dry densities has been determined, as well as the influence of the permeant salinity on hydraulic conductivity. The influence of salinity on the retention capacity of the compacted bentonite has been studied. For that, a new methodology has been designed. Water retention curves have been determined at temperatures of 20 and 60 0 C. Suction controlled odometer tests have been performed at 20oC. Finally, the behaviour of the MX-80 bentonite has been compared to that of the Spanish FEBEX bentonite. (Author) 13 refs

MX-80 Bentonite. thermal-Hydro-Mechanical Characterisation Performed at CIEMAT in the Context of the Prototype Project

Energy Technology Data Exchange (ETDEWEB)

Villar, M. V.

2005-07-01

This document details the results of the thermo-hydro-mechanical (THM) characterisation of the commercial MX-80 bentonite performed by CIEMAT from 2001 to 2004 in the context of a project carried out at the AEspoe Hard Rock Laboratory (Sweden), the Prototype Repository. The swelling pressure and the permeability of the bentonite compacted to different dry densities has been determined, as well as the influence of the permeant salinity on hydraulic conductivity. The influence of salinity on the retention capacity of the compacted bentonite has been studied. For that, a new methodology has been designed. Water retention curves have been determined at temperatures of 20 and 60oC. Suction controlled odometer tests have been performed at 20oC. Finally, the behaviour of the MX-80 bentonite has been compared to that of the Spanish FEBEX bentonite. (Author) 13 refs.

Ca/Na selectivity coefficients from the Poisson-Boltzmann theory

International Nuclear Information System (INIS)

Hedstroem, Magnus; Karnland, Ola

2010-01-01

Document available in extended abstract form only. A possible scenario in the post-glacial evolution of the bentonite buffer used in a KBS-3 repository for spent nuclear fuel is that parts of the buffer may erode due to sol formation caused by the extensive swelling of, in particular, Na-montmorillonite in water of low ionic strength. Presence of calcium in the interlayer has been shown to promote gel formation even in electrolytes with ionic strengths in the vicinity of those in glacial melt waters. In order to estimate the amount of calcium in the clay at the onset of glaciation one needs information of the selectivity coefficient for Ca/Na exchange. Hitherto, most experimental data for evaluating the Gaines-Thomas selectivity coefficient, K GT have been obtained in batch experiments, i.e. at high water-to-solid ratios. The conditions in highly compacted bentonite are, however, radically different in many respects, e.g. the interlayer space is on the nanometre scale and the concentration of counterions is in molar range. Therefore we would like to theoretically investigate the transferability of the selectivity coefficients, determined in batch experiments, to compacted conditions. We solve the Poisson-Boltzmann (PB) equation for two parallel charged surfaces in equilibrium with an external NaCl/CaCl 2 mixed solution. Integration of the ion concentration profiles obtained from the PB equation gives the occupancy of Na + and Ca 2+ in the clay. That information together with the composition of the external electrolyte is all that is needed for the calculation of K GT . With a surface layer-charge density of one charge per 145 A 2 , which is close to the value for Wyoming montmorillonite, we find a variation of the selectivity coefficient from about 4 M in batch to 8 M for compacted montmorillonite with dry density 1700 kg/m 3 . The significance as well as the physics behind these results will be presented in detail. The predictions, based on the PB theory, will

Retention of redox sensitive waste elements in compacted bentonite

International Nuclear Information System (INIS)

Torstenfelt, B.; Allard, B.

1984-01-01

The diffusion of technetium, iodine, uranium and neptunium in compacted bentonite has been studied. The possible reduction of the transport rate of these elements (i.e. redoxsensitive elements) by mixing the clay with metallic iron (for technetium, uranium and neptunium) or by adding a chemisorbent (for iodine) to the clay is reported. Technetium has an apparent diffusivity about 5 times higher in the heptavalent state (TcO 4 - ) than in the tetravalent state (TcO(OH) 2 or TcO 2 ), uranium and neptunium in their higher oxidation state (VI and V) have apparent diffusivities about 6 and 50 times higher, respectively, than in the tetravalent state. Iodine, as I - (or IO 3 - ), has a transport rate more than one order of magnitude lower than TcO 4 - . 10 references, 5 figures, 3 tables

Effect Of Coir Fibres On The Compaction And Unconfined Compressive Strength Of Bentonite-Lime-Gypsum Mixture

Directory of Open Access Journals (Sweden)

Tilak B. Vidya

2015-06-01

Full Text Available This paper presents the effect of coir fibres on the compaction and unconfined compressive strength of a bentonite-lime-gypsum mixture. The coir fiber content varied from 0.5 to 2 %. The results indicated that the dry unit weight and the optimum moisture content of a bentonite – lime mix increased with the addition of gypsum. The unconfined compressive strength of the bentonite increased with the increase in the lime content up to 8 %. Beyond 8 %, the unconfined compressive strength decreased. The dry unit weight of the reference mix decreased, and the optimum moisture content increased with the addition of coir fibre. The unconfined compressive strength of the bentonite + 8 % lime mix increased up to 4 % with the gypsum. Beyond 4 %, the unconfined compressive strength decreased. The unconfined compressive strength of the reference mix increased with the addition of coir fibre up to a fibre content of 1.5 %. The unconfined compressive strength of the reference mix-coir fibre composite was less in comparison to the reference mix. The unconfined compressive strength of the bentonite increased with the addition of lime and gypsum and with the increase in the curing period. The improvement in the post-peak region was better for the reference mix with reinforced coir fibres as compared to the unreinforced reference mix. The improved post-peak behaviour of the bentonite-lime-gypsum-coir fibre mixture could boost the construction of temporary roads on such problematic soils. Further, its use will also provide an environmental motivation for providing a means of consuming large quantities of coir fibres.

Swelling characteristics of sand-bentonite mixtures under one-dimensional stress

International Nuclear Information System (INIS)

Cui, Hongbin; Sun, De'an; Matsuoka, Hajime; Xu Yongfu

2004-01-01

Based on the concept that the maximum water volume absorbed by unit volume of montmorillonite is constant, the swelling deformation of sand-bentonite mixtures is uniquely characterized using the void ratio of montmorillonite, which is defined by the ratio of water volume to montomorillonite volume. The relationship between the montmorillonite void ratio and overburden pressure at fully swelling is independent of the initial compaction condition and the sand-bentonite mixture ratio, and is a linear line in their log scale. When overburden pressure is large enough and/or the bentonite ratio of the mixture is small, the measured plots deviate from the line. A method for predicting the limited overburden pressure which is linearly correlated with the montmorillonite void ratio is proposed and verified using the concept of the skeleton void ratio. (author)

Bentonite swelling pressure in strong NaCl solutions. Correlation of model calculations to experimentally determined data

International Nuclear Information System (INIS)

Karnland, O.

1998-01-01

A number of quite different quantitative models concerning swelling pressure in bentonite clay have been proposed. This report discusses a number of models which possibly can be used also for saline conditions. A discrepancy between calculated and measured values was noticed for all models at brine conditions. In general the models predicted a too low swelling pressure compared to what was experimentally found. An osmotic component in the clay/water system is proposed in order to improve the previous conservative use of the thermodynamic model. Calculations of this osmotic component is proposed to be made by use of the clay cation exchange capacity and Donnan equilibrium. Calculations made by this approach showed considerably better correlation to literature laboratory data, compared to calculations made by the previous conservative use of the thermodynamic model. A few verifying laboratory tests were made and are briefly described in the report. The improved model predicts a substantial bentonite swelling pressure also in a saturated sodium chloride solution if the density of the system is sufficiently high. This means in practice that the buffer in a KBS-3 repository will give rise to an acceptable swelling pressure, but that the positive effects of mixing bentonite into a backfill material will be lost if the system is exposed to brines. (orig.)

Bentonite maturation with 'Águas de Lindóia' water (SP)

Energy Technology Data Exchange (ETDEWEB)

Torrecilha, Jefferson K.; Silva, Paulo S.C., E-mail: jeffkoy@usp.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

2017-07-01

This study aims to characterize the artificial peloid obtained by maturing bentonite with Águas de Lindóia water for periods of three, six and nine months. The pH, moisture, organic matter content, loss on ignition and swelling power of matured and non-matured samples were measured for physicochemical characterization. The elemental concentration was determined by instrumental neutron activation analysis. Results showed that water adsorption capacity, organic matter and swelling power is related to the maturation time and no significant differences occurs in the elemental concentration except for Na. (author)

bentonite-sand mixture as new backfill/buffer material

International Nuclear Information System (INIS)

Cui Suli; Liu Jisheng; Zhang Huyuan; Liang Jian

2008-01-01

The mixture of bentonite and quartz sand is suggested as a new backfill/buffer material for geological disposal of HLW. To improve the further design of underground laboratory and in-situ industrial construction test, the optimization of sand addition to bentonite is focused at present research stage. Based on summarizing the research results abroad, laboratory tests were conducted on the mixture of GMZ001 bentonite and quartz sand, such as compaction test and swelling tests etc. Test data shows that GMZ bentonite-sand mixture exhibits a favorite compaction with a 30% sand addition, a highest swelling pressure with a 20% sand addition, and a decreasing plasticity with increases in sand addition and pore liquid concentration. (authors)

Properties of the bentonite from Lieskovec deposit and their possible environmental applications

International Nuclear Information System (INIS)

Andrejkovicova, S.

2008-01-01

liners. However, low permeability coefficients of the order 10-11 m.s-1 fulfill the primary requirement for sealing purposes. Natrification process of Ca 2+ -Lieskovec samples to their Na + -counterparts resulted in increased liquid limit values by 95 % and water adsorption by Enslin test by 65 % in comparison with the Ca 2+ -forms. Addition of Ca-JP bentonite of higher quality (smectite content 64 %) to Ca-L bentonite caused enhancement of the geotechnical properties: liquid limit increases by 20 %, water adsorption by Enslin test by 50 % in comparison with the raw Ca-L samples. After natrification of the blends with soda ash the geotechnical parameters were markedly improved. Permeability coefficients of all the blends were satisfactorily low, of the order of 10-11 m.s -1 . The liquid limit and water absorption values of the blend containing 65 mass % of Na(L11 and L15) and 35 mass % of Na-JP bentonites meet all requirements on geotechnical parameters of bentonites used in GCLs. Partial substitution of smectite-richer and more expensive Na-JP bentonite with the less expensive and lower in smectite Na-L bentonite would reduce the expenses for the bentonite filler by about 12 % compared to commonly used Tatrabent GCL filler. (author)

Sorption and diffusion of FE(II) in bentonite

International Nuclear Information System (INIS)

Muurinen, A.; Tournassat, C.; Hadi, J.; Greneche, J.-M.

2014-02-01

The iron in the engineering barrier system of a nuclear waste repository interacts via the corrosion process with the swelling clay intended as the buffer material. This interaction may affect the sealing properties of the clay. In the case of iron-bentonite interaction, redox reactions, dissolution/precipitation, the diffusion and sorption are coupled together. In a combined study different processes are difficult to distinguish from each other, and more specific studies are needed for the separate processes. In particular, there is a need for well-controlled diffusion and sorption experiments where iron is kept as Fe(II). In this project, sorption and diffusion of Fe(II) in bentonite have been studied. The experiments were carried out under low-oxygen conditions in an anaerobic glove-box. The radioactive isotope ( 55 Fe) was used as a tracer in the experiments. The sorption experiments were carried out with two batches of purified MX-80 bentonite. One was purified at Bureau de Recherches Geologiques et Minieres, French Geological Survey (BRGM) and the other one at VTT Technical Research Centre of Finland (VTT). Experiments were also carried out with synthetic smectite, which did not include iron, which was prepared at LMPC (ENSC, F 68093 Mulhouse, France). The sorption experiments were carried out in 0.3 M and 0.05 M NaCl solutions as a function of pH, and in 0.3 M NaCl solution buffered at pH 5 as a function of added Fe(II) concentration. The separation of bentonite and solution at the end of the sorption experiment was carried out in the early phase by centrifuging only. In the later phase, ultrafiltering was added in order to improve the separation. The diffusion experiments were carried out in compacted samples prepared from MX-80 purified at VTT and saturated with 0.3 M NaCl at pH 8 and 5. A non-steady-state diffusion experiment method, where the tracer was introduced as an impulse source between two bentonite plugs was used in the measurements

Sorption and diffusion of FE(II) in bentonite

Energy Technology Data Exchange (ETDEWEB)

Muurinen, A. [VTT Technical Research Centre of Finland, Espoo (Finland); Tournassat, C.; Hadi, J. [BRGM, Orleans (France); Greneche, J.-M. [LPCE, Le Mans (France)

2014-02-15

The iron in the engineering barrier system of a nuclear waste repository interacts via the corrosion process with the swelling clay intended as the buffer material. This interaction may affect the sealing properties of the clay. In the case of iron-bentonite interaction, redox reactions, dissolution/precipitation, the diffusion and sorption are coupled together. In a combined study different processes are difficult to distinguish from each other, and more specific studies are needed for the separate processes. In particular, there is a need for well-controlled diffusion and sorption experiments where iron is kept as Fe(II). In this project, sorption and diffusion of Fe(II) in bentonite have been studied. The experiments were carried out under low-oxygen conditions in an anaerobic glove-box. The radioactive isotope ({sup 55}Fe) was used as a tracer in the experiments. The sorption experiments were carried out with two batches of purified MX-80 bentonite. One was purified at Bureau de Recherches Geologiques et Minieres, French Geological Survey (BRGM) and the other one at VTT Technical Research Centre of Finland (VTT). Experiments were also carried out with synthetic smectite, which did not include iron, which was prepared at LMPC (ENSC, F 68093 Mulhouse, France). The sorption experiments were carried out in 0.3 M and 0.05 M NaCl solutions as a function of pH, and in 0.3 M NaCl solution buffered at pH 5 as a function of added Fe(II) concentration. The separation of bentonite and solution at the end of the sorption experiment was carried out in the early phase by centrifuging only. In the later phase, ultrafiltering was added in order to improve the separation. The diffusion experiments were carried out in compacted samples prepared from MX-80 purified at VTT and saturated with 0.3 M NaCl at pH 8 and 5. A non-steady-state diffusion experiment method, where the tracer was introduced as an impulse source between two bentonite plugs was used in the measurements

Study for the water penetration chemistry of bentonite under temperature gradation environment

International Nuclear Information System (INIS)

Hara, Naohiro; Imakita, Tsuyoshi

2003-02-01

This work have been studied for the water fluctuation in time and space in case of the ground water penetration into the unsaturated bentonite with development of the necessary test equipment. The test equipment necessary for this test, was designed on consideration of the adiabatic condition, sensors for pH, salt and water measurement. The thickness of the bentonite specimen was set to 10 cm and the temperature slope was enable to set between 80degC and 100degC at the both end of the specimen. The water for penetration was pushed by gas constant pressure up to 1 MPa. The glass electrode for pH, electric conductivity for salinity and moisture sensor for lower water content and water sensor for higher were used as the sensors. The fluctuation of salt and water in the ground water penetration test to bentonite was estimated. The sensor data were treated as parametric data, because those data could not calibrated in those high temperature and under those high bentonite swollen pressure. For another development should be needed for water sensor. (author)

Na-smectite s in the Cala de Tomate bentonite deposit (Spain): a natural analogue of the salinity effect on the bentonite barrier of a rad waste disposal

Energy Technology Data Exchange (ETDEWEB)

Perez del Villar, L.; Pelayo, M.; Fernandez, A.M.; Cozar, J.S. [CIEMAT - Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas (CIEMAT/DIRE/CEAGP), Madrid (Spain); Delgado, A.; Reyes, E. [Ciencias de la Tierra y Quimica Ambiental Estacion Experimental del Zaidin Dpt., Granada (Spain); Fernandez-Soler, J.M. [Granada Univ., Dpt. de Mineralogia y Petrologia (Spain); Tsige, M. [Facultad de Ciencias Geologicas, Dpt. de Geodinamica, Madrid (Spain)

2005-07-01

Within the framework of the ENRESA programme for the assessment of the long-term behaviour of the bentonite-engineered barrier for a deep radwaste geological repository, analogue studies on several bentonite deposits are conducted at CIEMAT. Among these analogue studies, the thermal effect induced by volcanic intrusions on bentonite deposits is highlighted. In the Cabo de Gata volcanic region, there are several analogue scenarios where these studies have been performed, such as the Cala de Tomate bentonite deposit that was intruded by a pyroxene andesite volcanic dome. However, geological, mineralogical, physicochemical, geochemical and stable isotopic data obtained from the smectites do not allow to establish any analogy with the thermal effect expected on the bentonite-engineered barrier of a deep geological repository after burial. Thus, the bentonitisation processes took place after the intrusion of the dome, as a result of meteoric diagenesis intensively developed on faulting zone affecting the parent pyroclastic acid tuffs. This faulting process occurred after the dome intrusion. However, the physicochemical characteristics of these smectites, specially the exchangeable cations, allow to consider this bentonite deposit as a natural analogue of the saline effect on the clayey barrier. This analogy has been established because Na-smectites are present in this deposit and, up to our present knowledge, it is the first time that these smectites occur naturally in the Cabo de Gata-La Serrata de Nijar volcanic region. As a consequence, the main objectives of this work are: i) to characterise these smectites; ii) to establish their genesis and processes affecting them after their formation and iii) to identify the effects on the bentonite-engineered barrier should it were affected by a Na-rich saline waterfront. (authors)

Report on hydro-mechanical and chemical-mineralogical analyses of the bentonite buffer in Canister Retrieval Test

Energy Technology Data Exchange (ETDEWEB)

Dueck, Ann; Johannesson, Lars-Erik; Kristensson, Ola; Olsson, Siv [Clay Technology AB (Sweden)

2011-12-15

The effect of five years of exposure to repository-like conditions on compacted Wyoming bentonite was determined by comparing the hydraulic, mechanical, and mineralogical properties of samples from the bentonite buffer of the Canister Retrieval Test (CRT) with those of reference material. The CRT, located at the Swedish Aspo Hard Rock Laboratory (HRL), was a full-scale field experiment simulating conditions relevant for the Swedish KBS-3 concept for disposal of high-level radioactive waste in crystalline host rock. The compacted bentonite, surrounding a copper canister equipped with heaters, had been subjected to heating at temperatures up to 95 deg C and hydration by natural Na-Ca-Cl type groundwater for almost five years at the time of retrieval. Under the thermal and hydration gradients that prevailed during the test, sulfate in the bentonite was redistributed and accumulated as anhydrite close to the canister. The major change in the exchangeable cation pool was a loss in Mg in the outer parts of the blocks, suggesting replacement of Mg mainly by Ca along with the hydration with groundwater. Close to the copper canister, small amounts of Cu were incorporated in the bentonite. A reduction of strain at failure was observed in the innermost part of the bentonite buffer, but no influence was seen on the shear strength. No change of the swelling pressure was observed, while a modest decrease in hydraulic conductivity was found for the samples with the highest densities. No coupling was found between these changes in the hydro-mechanical properties and the montmorillonite . the X-ray diffraction characteristics, the cation exchange properties, and the average crystal chemistry of the Na-converted < 1 {mu}m fractions provided no evidence of any chemical/structural changes in the montmorillonite after the 5-year hydrothermal test.

Sorption of strontium on bentonites from Slovak deposits

International Nuclear Information System (INIS)

Kufcakova, J.; Galambos, M.; Rajc, P.

2005-01-01

Sorption on bentonite from different Slovak deposits / Jelsovy potok, Kopernica and Lieskove has been investigated under various experimental conditions, such as contact time, pH, sorbate concentrations, presence of complementary cation. The sorption of strontium from aqueous solutions was investigated using a radiometric determination of distribution coefficient, Kd. The individual solutions were labelled with radiotracer. Radiation stability has been investigated, the higher sorption parameters were observed for the irradiated bentonites /tab.l/ , which can be explained by the increase of specific surface and change of solubility of the irradiated samples of bentonite. The presence of complementary cations, Na + , K + , NH 4 + , Ca 2+ , Mg 2+ and Ba 2+ depresses the sorption of Sr on bentonite. In the case of bentonite Kopernica the effectiveness in reducing the sorption of strontium by cations followed the order K + 4 + + 2+ 2+ 2+ . Results indicate that the sorption of Sr + on bentonite will be affected by the presence of high concentrations of various salts in the waste water effluents. (author)

Corrosion of high-level radioactive waste iron-canisters in contact with bentonite.

Science.gov (United States)

Kaufhold, Stephan; Hassel, Achim Walter; Sanders, Daniel; Dohrmann, Reiner

2015-03-21

Several countries favor the encapsulation of high-level radioactive waste (HLRW) in iron or steel canisters surrounded by highly compacted bentonite. In the present study the corrosion of iron in contact with different bentonites was investigated. The corrosion product was a 1:1 Fe layer silicate already described in literature (sometimes referred to as berthierine). Seven exposition test series (60 °C, 5 months) showed slightly less corrosion for the Na-bentonites compared to the Ca-bentonites. Two independent exposition tests with iron pellets and 38 different bentonites clearly proved the role of the layer charge density of the swelling clay minerals (smectites). Bentonites with high charged smectites are less corrosive than bentonites dominated by low charged ones. The type of counterion is additionally important because it determines the density of the gel and hence the solid/liquid ratio at the contact to the canister. The present study proves that the integrity of the multibarrier-system is seriously affected by the choice of the bentonite buffer encasing the metal canisters in most of the concepts. In some tests the formation of a patina was observed consisting of Fe-silicate. Up to now it is not clear why and how the patina formed. It, however, may be relevant as a corrosion inhibitor. Copyright © 2014 Elsevier B.V. All rights reserved.

Characterization of bentonite clay from Cubati, PB, Brazil

International Nuclear Information System (INIS)

Batista, A.P.; Marques, L.N.; Campos, L.A.; Neves, G.A.; Ferreira, H.C.; Menezes, R.R.

2009-01-01

The bentonite of the State of Paraiba are commercially used in numerous technological sectors, particularly in oil drilling muds. However, these bentonite deposits are becoming exhausted after decades of exploitation. Thus, the aim of this work was to characterize physically, mineralogically and technologically bentonite clays from Cubati city, PB. The samples were dried at 60 deg C and characterized through X-ray fluorescence, particle size distribution, X-ray diffraction, differential thermal and gravimetric analyzes and scanning electronic microscopy. The natural bentonite clays were transformed into sodium bentonite by Na_2CO_3 solution treatment. It was estimated the rheological properties of the suspensions: apparent and plastic viscosities and water loss. The results showed that the samples are polycationic bentonite clays, containing amounts of MgO, CaO and K_2O similar to those of bentonite from Boa Vista, PB, and are composed of smectite, kaolinite and quartz. The samples presented fractions of particles size under 2 μm of 30 and 32%. The rheological properties showed that the samples presented technological potential to be used in drilling muds. (author)

Bentonite swelling pressure in strong NaCl solutions. Correlation of model calculations to experimentally determined data

Energy Technology Data Exchange (ETDEWEB)

Karnland, O. [Clay Technology, Lund (Sweden)

1998-01-01

A number of quite different quantitative models concerning swelling pressure in bentonite clay have been proposed. This report discusses a number of models which possibly can be used also for saline conditions. A discrepancy between calculated and measured values was noticed for all models at brine conditions. In general the models predicted a too low swelling pressure compared to what was experimentally found. An osmotic component in the clay/water system is proposed in order to improve the previous conservative use of the thermodynamic model. Calculations of this osmotic component is proposed to be made by use of the clay cation exchange capacity and Donnan equilibrium. Calculations made by this approach showed considerably better correlation to literature laboratory data, compared to calculations made by the previous conservative use of the thermodynamic model. A few verifying laboratory tests were made and are briefly described in the report. The improved model predicts a substantial bentonite swelling pressure also in a saturated sodium chloride solution if the density of the system is sufficiently high. This means in practice that the buffer in a KBS-3 repository will give rise to an acceptable swelling pressure, but that the positive effects of mixing bentonite into a backfill material will be lost if the system is exposed to brines. (orig.). 14 refs.

Review of the interactions between bentonite and cement

International Nuclear Information System (INIS)

Duerden, S.L.

1992-01-01

Properties of bentonite may be significantly affected by reaction with cement. This report reviews the literature to identify the reactions that may occur and considers their effects on the performance of bentonite in these applications. The dominant reactions expected under alkaline conditions prevalent in an underground repository where cement is used extensively are zeolitization, beidellitization, and ion exchange. Zeolitisation will occur at high temperatures (200 o C) or after long periods (500-1000 years) when the pH is high (pH>9). Beidellitization may occur at high pH (pH>9). The silica may reprecipitate in situ due to low hydraulic conductivity or in regions of low pH or temperature. This may result in reduced porosity/permeability and plasticity. Ion exchange reactions are virtually instantaneous. The rate of the reaction depends on the concentration and rate of access of ground water. Substitution of Ca 2+ ions from cement for Na + ions in sodium-bentonites will result in reduced swelling pressure and plasticity, and increased hydraulic conductivity of the bentonite. The effect of Na-bentonite on the properties of cement is the formation of an Al-substituted 11A tobermorite, which results in improved Cs + sorption. In cements reacted with Calcium-bentonite the main product was found to be a hydroxyapatite layer on the cement surface. (author)

Research program to study the gamma radiation effects in Spanish bentonites; Programa de investigacion para estudiar los efectos de la radiacion gamma en bentonitas calcicas espanolas

Energy Technology Data Exchange (ETDEWEB)

Dies, J; Tarrasa, F [Universidad Politecnica de Catalunya (Spain); Cuevas de las, C; Miralles, L; Pueyo, J J [Universidad de Barcelona (Spain)

2000-07-01

The engineering barrier of a radioactive waste underground disposal facility, placed in a granitic host rock, will consist of a backfill of compacted bentonite blocks. At first, this material will be subjected to a gamma radiation field, from the waste canister, and heat from the spent fuel inside the canister. Moreover, any groundwater that reaches the repository will saturate the bentonite. For these reasons the performance of the engineered barrier must be carefully assessed in laboratory experiments. (Author)

BENTONITE PROCESSING

Directory of Open Access Journals (Sweden)

Anamarija Kutlić

2012-07-01

Full Text Available Bentonite has vide variety of uses. Special use of bentonite, where its absorbing properties are employed to provide water-tight sealing is for an underground repository in granites In this paper, bentonite processing and beneficiation are described.

Survey on current status of laboratory test method and experimental consideration for establishing standardized procedure of material containing bentonite. Report of collaboration research between JAEA and CRIEPI (Joint research)

International Nuclear Information System (INIS)

Tanai, Kenji; Kikuchi, Hirohito; Nakamura, Kunihiko; Tanaka, Yukihisa; Hironaga, Michihiko

2010-08-01

In the current concept of repository for radioactive waste disposal, compacted bentonite as well as bentonite based material will be used as an engineered barrier mainly for inhibiting migration of radioactive nuclides. In most cases, properties of bentonite, such as low permeability etc., are obtained by laboratory tests. However, results of laboratory tests of bentonite often vary considerably even if index parameter, such as effective clay density, is constant. One of the causes of the variability is considered to be lack of standardized method of laboratory test for bentonite. Thus standardization of laboratory test methods for bentonite is needed. So, investigation for establishing standardized laboratory test method of bentonite is conducted based on the results of survey on current status of laboratory test method for bentonite. In particular, the literature survey as well as laboratory tests were conducted to find factors affecting the results of laboratory tests for bentonite and to estimate their degree of influence. The following conclusions are obtained through this study. (1) Hydraulic conductivity test. According to the results of literature survey, it is revealed that constant pressure permeability test and consolidation test are currently used for measuring hydraulic conductivity of bentonite and that (a) hydraulic gradient, (b) local seepage flow between lateral surface of the specimen and lateral wall of the container, (c) water pressure which is applied to the specimen, (d) degree of saturation and (e) size of the specimen possibly affect the results of the constant pressure permeability test, while (f) friction between lateral surface of the specimen and lateral wall of the container accompanied by deformation of the specimen, (g) consolidation pressure together with factors (d), (e) affect the results of the consolidation test. Literature which describes that factors (a), (b) and (e) affect the results of the constant pressure permeability test

Modeling early in situ wetting of a compacted bentonite buffer installed in low permeable crystalline bedrock

Science.gov (United States)

Dessirier, B.; Frampton, A.; Fransson, À.; Jarsjö, J.

2016-08-01

The repository concept for geological disposal of spent nuclear fuel in Sweden and Finland is planned to be constructed in sparsely fractured crystalline bedrock and with an engineered bentonite buffer to embed the waste canisters. An important stage in such a deep repository is the postclosure phase following the deposition and the backfilling operations when the initially unsaturated buffer material gets hydrated by the groundwater delivered by the natural bedrock. We use numerical simulations to interpret observations on buffer wetting gathered during an in situ campaign, the Bentonite Rock Interaction Experiment, in which unsaturated bentonite columns were introduced into deposition holes in the floor of a 417 m deep tunnel at the Äspö Hard Rock Laboratory in Sweden. Our objectives are to assess the performance of state-of-the-art flow models in reproducing the buffer wetting process and to investigate to which extent dependable predictions of buffer wetting times and saturation patterns can be made based on information collected prior to buffer insertion. This would be important for preventing insertion into unsuitable bedrock environments. Field data and modeling results indicate the development of a de-saturated zone in the rock and show that in most cases, the presence or absence of fractures and flow heterogeneity are more important factors for correct wetting predictions than the total inflow. For instance, for an equal open-hole inflow value, homogeneous inflow yields much more rapid buffer wetting than cases where fractures are represented explicitly thus creating heterogeneous inflow distributions.

Diffusion in crushed rock and in bentonite clay

International Nuclear Information System (INIS)

Olin, M.

1994-04-01

Diffusion theories for porous media with sorption are reviewed to serve as a basis for considering diffusion in simple systems like sand of crushed rock. A Fickian diffusion and linear sorption model is solved both by analytical Laplance transform and Green's function methods and by numerical methods, and then applied to small-scale experiments for Finnish low- and medium-level operating waste repositories. The main properties of bentonite are reviewed. The hydraulic conductivity of compacted bentonite is so low that the major transport mechanism is diffusion. A Fickian diffusion and linear sorption model is applied to bentonite. The main component of bentonite, montmorillonite, has a high ion-exchange capacity and thus, transport in bentonite consists of interactive chemical and diffusion phenomena. A chemical equilibrium model, CHEQ, is developed for ion-exchange reactions in bentonite water systems. CHEQ is applied to some bentonite experiments with success, especially for monovalent ions. The fitted log-binding constants for sodium exchange with potassium, magnesium, and calcium were 0.27, 1.50, and 2.10, respectively. A coupled chemical and diffusion model, CHEQDIFF, is developed to take account of diffusion in pore water, surface diffusion and ion-exchange reactions. The model is applied to the same experiments as CHEQ, and validation is partly successful. In the diffusion case, the above-mentioned values for binding constants are used. The apparent diffusion (both anions and cations) and surface diffusion (only for cations) constants used are 3.0*10 -11 m 2 /s and 6.0*10 -12 m 2 /s, respectively, but these values are questionable, as experimental results good enough for fitting are not available. (orig.). (74 refs., 27 figs., 12 tabs.)

Modelling Ni diffusion in bentonite using different sorption models

International Nuclear Information System (INIS)

Pfingsten, W.; Baeyens, B.; Bradbury, M.

2010-01-01

Document available in extended abstract form only. An important component of the multi barrier disposal concept for a radioactive waste repository is the bentonite backfill surrounding the canisters containing vitrified high-level waste and spent fuel located in the tunnels deep within the chosen host rock. The effectiveness of the compacted bentonite barrier is such that calculations have indicated that many radionuclides have decayed to insignificant levels before having diffused through the thickness of bentonite. These calculations are performed using the simple Kd sorption concept in which the values are taken from batch type experiments performed on dispersed systems performed for a single metal at a time, usually at trace concentrations. However, in such complex systems many radionuclides, inactive metal contaminants/ground water components may be simultaneously present in the aqueous phase at a range of concentrations varying with time during the temporal evolution of the repository system. An important aspect influencing the sorption of any radioactive metal under a set of given geochemical conditions is its competition with other metals present, and how this may vary as a function of concentration. Competitive sorption effects are not currently included in safety assessments and are thus an issue which needs to be addressed. Here we provide some first estimates of the potential influence of competitive sorption effects on the migration of radioactive metals through compacted bentonite as a function of their concentration and the concentration of competing metals. Ni(II) and Fe(II) were chosen as possible competing cations since their concentration levels are expected to have values greater than trace levels and effects might be maximal and canister corrosion represents a permanent Fe source at the bentonite interface which could influence bivalent radionuclide diffusion. The modelling of the Ni(II) diffusion/sorption has been carried out using three

Alkali-activated fly ash-based geopolymers with zeolite or bentonite as additives

Energy Technology Data Exchange (ETDEWEB)

Hu, Mingyu; Zhu, Xiaomin; Long, Fumei [Nanchang University, Nanchang (China). College of Civil Engineering

2009-11-15

Geopolymers were synthesized by using fly ash as the main starting material, zeolite or bentonite as supplementary materials, and NaOH and CaO together as activator. An orthogonal array testing protocol was used to analyze the influence of the mix proportion on the properties of the geopolymers. The results indicate that the concentration of NaOH solution and the CaO content play an important role on the strength of the materials. Especially, with zeolite as additive, the fly ash-based geopolymer shows the highest strength and the best sulfate resistance. Infrared spectroscopy, X-ray, and SEM-EDX demonstrate that supplementary zeolite may involve the process of geopolymerization to form a stable zeolitic structure and improve the properties of the geopolymer. Bentonite simply acts as a filler to make the geopolymer more compact, but shows no improvement on the compositions and the microstructures of the geopolymer.

Evaluation of long-term interaction between cement and bentonite for geological disposal (1) - Project Overview

International Nuclear Information System (INIS)

Owada, Hitoshi; Hayashi, Daisuke; Yahagi, Ryoji; Ishii, Tomoko

2012-01-01

the Ca/Na ratio of exchangeable cations, calculations of the dissolution rate of montmorillonite under cementitious conditions and quantitative analysis of the secondary minerals near the cement-bentonite interface were carried out. The results were then used to perform a coupled calculation of the long term alteration of the bentonite buffer. The type of secondary minerals and their spatial distribution are important issues for predicting the long term alteration of EBS materials. The secondary minerals that precipitated near the interfaces between the cementitious and bentonitic materials have not been identified before because of their minute quantity, the confined area, and their amorphous phases. In this study we attempted to identify the secondary minerals near the cementitious-bentonitic interfaces through the use of CaKa-XAFS spectroscopy. These secondary minerals were identified as C-S-H. Because the swelling and watertight properties of bentonite material strongly depend on its montmorillonite content, the dissolution rate of montmorillonite is an important issue for long term assessment of EBS performance. Although the dissolution rate of montmorillonite in suspension has been already obtained in other research, the rates in compacted bentonite are still in dispute. A lower dissolution rate was obtained in this study by using in-situ vertical scanning interferometry (VSI). Although there is empirical evidence that the mechanical and hydraulic properties of bentonite depend strongly on its montmorillonite content, the alteration of those properties has not been theoretically described very thoroughly. The relationship between montmorillonite content and mechanical properties was obtained by using a mixture of high-purity montmorillonite and silica sand. The change in hydraulic properties caused by chemical degradation such as cation exchange was modeled by applying the Cozeny-Carman equation to the specific surface area of montmorillonite before and after

Physicochemical, mineralogical and mechanical properties of domestic bentonite and bentonite-sand mixture as a buffer material in the high-level waste repository

International Nuclear Information System (INIS)

Cho, Won Jin; Lee, Jae Owan; Kang, Chul Hyung; Chun, Kwan Sik

1999-09-01

The physicochemical properties such as specific weight, free swell rate, chemical composition, cation exchange capacity (CEC), surface area and distribution coefficient of Kyunggju bentonite were measured, and the mineralogical analysis was performed to investigate the mineralogical composition. For the compacted bentonite and the mixture of bentonite and sand, the liquid and plastic limit, the linear shrinkage, and compaction property, the compression property, the shear property, and the consolidation property were investigated and analyzed. The bentonite contains montmorillonite (70 percent), feldspar (29 percent), and small amounts of quartz(-1 percent). The compressive strengths of bentonites are increased from 0.53 MPa to 8.83 MPa rapidly with increasing dry density of 1.4 g/cm 3 to 1.8 g/cm 3 . The cohesion and internal friction angles of bentonites with the dry density of 1.4 g/cm 3 to 1.8 g/cm 3 are in the range of 500 to 1100 kPa and 27 to 50 degree, respectively. (Author). 21 refs., 20 tabs., 46 figs

Physicochemical, mineralogical and mechanical properties of domestic bentonite and bentonite-sand mixture as a buffer material in the high-level waste repository

Energy Technology Data Exchange (ETDEWEB)

Cho, Won Jin; Lee, Jae Owan; Kang, Chul Hyung; Chun, Kwan Sik

1999-09-01

The physicochemical properties such as specific weight, free swell rate, chemical composition, cation exchange capacity (CEC), surface area and distribution coefficient of Kyunggju bentonite were measured, and the mineralogical analysis was performed to investigate the mineralogical composition. For the compacted bentonite and the mixture of bentonite and sand, the liquid and plastic limit, the linear shrinkage, and compaction property, the compression property, the shear property, and the consolidation property were investigated and analyzed. The bentonite contains montmorillonite (70 percent), feldspar (29 percent), and small amounts of quartz(-1 percent). The compressive strengths of bentonites are increased from 0.53 MPa to 8.83 MPa rapidly with increasing dry density of 1.4 g/cm{sup 3} to 1.8 g/cm{sup 3}. The cohesion and internal friction angles of bentonites with the dry density of 1.4 g/cm{sup 3} to 1.8 g/cm{sup 3} are in the range of 500 to 1100 kPa and 27 to 50 degree, respectively. (Author). 21 refs., 20 tabs., 46 figs.

The adsorption of Cu(II) on sodium bentonite in a synthetic saline groundwater

International Nuclear Information System (INIS)

Ryan, S.R.; King, F.

1994-10-01

The adsorption of Cu(II) on Na-bentonite has been studied under conditions that simulate those expected in a nuclear fuel waste disposal vault located deep underground in the Canadian Shield. Adsorption isotherms have been determined for loose and compacted clay (compacted clay dry density 1.2 g.cm -3 ) over a wide range of copper concentrations (1 x 10 -6 mol.dm -3 to 1.0 mol.dm -3 ) at temperatures of 25 degrees C, 50 degrees C and 95 degrees C. Studies were carried out in a Na + - /Ca 2+ -based chloride solution ([Cl - ] = 0.97 mol.dm -3 ), with a clay-to-solution ratio of 1.6 g:360 cm 3 . For loose clays, the adsorption behaviour follows a Langmuir isotherm. The maximum adsorbate surface coverage increases with temperature, and exceeds the cation exchange capacity for Cu 2+ at temperatures of 50 degrees C and 95 degrees C. For compacted clays, the data follow a Freundlich-type isotherm, and exhibit no apparent temperature dependence. At a given pore-water copper concentration, the extent of adsorption on compacted clay is less than on loose clay. The difference between the behaviour of loose and compacted clays is explained in terms of the inaccessibility of some of the adsorption sites in compacted media. The significance of the results for calculating the corrosion rate of copper nuclear fuel waste containers is discussed. The adsorption results are used to analyze the shape and temperature dependence of copper concentration profiles observed in diffusion and corrosion experiments. 1 ref., 12 figs. 6 tabs., 1 appendix

Removal of Chromium from Waste Water of Tanning Industry Using Bentonite

International Nuclear Information System (INIS)

Abbasi, S.; Wahba, H.; AL-Masri, M.S.

2009-01-01

Tanning industry is considered as one of the oldest industries in the world, which produces solid and liquid wastes, where the Chromium-containing liquid wastes are considered to be as the main liquid pollutant to the environment. In this research, a new method is applied to remove the chromium from the industrial water wastes, which are produced by tanning industry using the Aleppo Bentonite.The experiments on laboratory- prepared samples and collected samples from some tanning factories in Damascus have proved that chromium removal from tanning waste water is very effective for solution of 85-98 %. Moreover, the optimal conditions for the treatment process of tanning waste water by Aleppo Bentonite have determined and found to be (pH=4, Bentonite concentration = 20 g l -1 when chromium concentration is 0.8 g l -1 , solution temperature = 30 degree centigrade, and Bentonite particle size < 90 μm). However, the proposed method can be considered to be an environmental solution for the treatment of tanning industrial wastes in Syria. (author)

Conceptual modeling coupled thermal-hydrological-chemical processes in bentonite buffer for high-level nuclear waste repository

Energy Technology Data Exchange (ETDEWEB)

Choi, Byoung Young; Park, Jin Young [Korea Institute of Geoscience and Mineral Resources, Daejeon (Korea, Republic of); Ryu, Ji Hun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-03-15

In this study, thermal-hydrological-chemical modeling for the alteration of a bentonite buffer is carried out using a simulation code TOUGHREACT. The modeling results show that the water saturation of bentonite steadily increases and finally the bentonite is fully saturated after 10 years. In addition, the temperature rapidly increases and stabilizes after 0.5 year, exhibiting a constant thermal gradient as a function of distance from the copper tube. The change of thermal-hydrological conditions mainly results in the alteration of anhydrite and calcite. Anhydrite and calcite are dissolved along with the inflow of groundwater. They then tend to precipitate in the vicinity of the copper tube due to its high temperature. This behavior induces a slight decrease in porosity and permeability of bentonite near the copper tube. Furthermore, this study finds that the diffusion coefficient can significantly affect the alteration of anhydrite and calcite, which causes changes in the hydrological properties of bentonite such as porosity and permeability. This study may facilitate the safety assessment of high-level radioactive waste repositories.

Layout Optimization for the Repository within a discontinuous and saturated granitic rock mass

International Nuclear Information System (INIS)

Kim, Jhin Wung; Choi, Jong Won; Bae, Dae Seok

2005-12-01

The objective of the present study is a layout optimization of a single and double layer repositories within a repository site with special joint set arrangements. Single and double layer repository models, subjected to the variation of repository depth, cavern spacing, pitch, and layer spacing, are analyzed for the thermal, hydraulic, and mechanical interaction behavior during the period of 2000 years from waste emplacement. Material properties used for the granitic rock mass, rock joints, PWR spent fuel, disposal canister, compacted bentonite, backfill material, and groundwater are the data collected domestically, and foreign data are used for some of the data not available domestically. The repository model includes a saturated granitic rock mass with joints, PWR spent fuel in a disposal canister surrounded by compacted bentonite inside a deposition hole, and backfill material in the rest of the space within a repository cavern

Full-scale demonstration of EBS construction technology I. Block, pellet and in-situ compaction method

International Nuclear Information System (INIS)

Toguri, Satohito; Asano, Hidekazu; Takao, Hajime; Matsuda, Takeshi; Amemiya, Kiyoshi

2008-01-01

(i) Bentonite Block: Applicability of manufacturing technology of buffer material was verified by manufacturing of full scale bentonite ring which consists of one-eight (1/8) dividing block (Outside Diameter (OD): 2.220 mm H: 300 mm). Density characteristic, dimension and scale effect, which were considered the tunnel environment under transportation, were evaluated. Vacuum suction technology was selected as handling technology for the ring. Hoisting characteristic of vacuum suction technology was presented through evaluation of the mechanical property of buffer material, the friction between blocks, etc. by using a full-scale bentonite ring (OD 2.200 mm, H 300 mm). And design of bentonite block and emplacement equipment were presented in consideration of manufacturability of the block, stability of handling and improvement of emplacement efficiency. (ii) Bentonite Pellet Filling: Basic characteristics such as water penetration, swelling and thermal conductivity of various kinds of bentonite pellet were collected by laboratory scale tests. Applicability of pellet filling technology was evaluated by horizontal filling test using a simulated full-scale drift tunnel (OD 2.200 mm, L 6 m) . Filling density, grain size distribution, etc. were also measured. (iii) In-Situ Compaction of Bentonite: Dynamic compaction method (heavy weight fall method) was selected as in-situ compaction technology. Compacting examination which used a full scale disposal pit (OD 2.360 mm) was carried out. Basic specification of compacting equipment and applicability of in-situ compaction technology were presented. Density, density distribution of buffer material and energy acted on the wall of the pit, were also measured. (author)

H, HM, and THM-C processes in engineered barriers

Energy Technology Data Exchange (ETDEWEB)

Cui, Y.J.; Tang, A.M.; Loiseau, C.; Delage, P.; Polak, M.; Souli, H.; Fleureau, J.M.; Wu, P.L.; Tien, Y.M.; Romero, E.; LI, Xiang Ling; Tanaka, Y.; Hasegawa, T.; Nakamura, K.; Sahara, F.; Murakami, T.; Kobayashi, I.; Mihara, M.; Ohi, T.; Lu, J.D.; Huang, W.H.; Lee, W.Y.; Sui, I.H.; Villar, M.V.; Sanchez, M.; Gens, A.; Samper, J.; Lu, C.; Montenegro, L.; Birgersson, M.; Karnland, O.; Nilsson, U.; Akesson, M.; Kristensson, O.; Gatabin, C.; Yang, C.R.; Huang, W.H.; Hsiao, T.H.; Dueck, A.; Lonnqvist, M.; Goudarzi, R.; Borgesson, L.; Fernandez, A.M.; Rivas, P.; Melon, A.M.; Villar, M.V.; Ferrow, E.; Bender Koch, Ch.; Suzuki, S.; Sazarashi, M.; Takegahara, T.; Takao, H.; Tanai, K.; Matsumoto, K.; Gatabin, C.; Touze, G.; Imbert, C.; Guillot, W.; Billaud, P

2007-07-01

This session gathers 24 articles (posters) dealing with: determining water permeability of a compacted bentonite sand mixture under confined and free-swell conditions; the model prediction of engineered barrier system effectiveness in the fracture at laboratory scale; the changes in the hydraulic properties of a smectite in presence of chromium; the wall friction and ejection behaviour of bentonite-base buffer material; the thermo-hydro-mechanical behaviour of a large scale mock-up test 'Ophelie' in Belgium: laboratory characterization and numerical modelling; modeling swelling characteristics and permeability of several compacted bentonite affected by saline water; modelling for the long-term Mechanical and Hydraulic behaviour of bentonite-based materials considering chemical transitions; the coupled thermal-hydro analysis on partially saturated bentonite; the behaviour of a bentonite barrier in the laboratory: experimental results up to 8 years and numerical simulation; a coupled hydrogeochemical calculations of the interactions of corrosion products and bentonite; the freezing in saturated bentonite: a thermodynamic approach; the mechanical modeling of MX-80: Development of constitutive laws; the mechanical modeling of MX-80 - Quick tools for BBM parameter analysis; TBT{sub 3} Mock-up test-experimental and model results; the suction characteristics of two compacted bentonite; the retention curves and volume change properties of unsaturated MX-80 bentonite: a laboratory study; humidity induced swelling and water absorption rate of highly compacted bentonite; unconfined compression tests on bentonite samples exposed to high temperature during long time in the field test lot; the thermophysical properties of bentonite; the geochemistry and mineralogy of a bentonite subjected to heating and hydration in an in-situ test after five years operation; the LOT project, long term test of buffer material at Aespoe: a Moessbauer spectroscopic study; the self

Integrated sorption and diffusion model for bentonite. Part 1. Clay-water interaction and sorption modeling in dispersed systems

International Nuclear Information System (INIS)

Tachi, Yukio; Suyama, Tadahiro; Ochs, Michael

2014-01-01

To predict the long-term migration of radionuclides (RNs) under variable conditions within the framework of safety analyses for geological disposal, thermodynamic sorption models are very powerful tools. The integrated sorption and diffusion (ISD) model for compacted bentonite was developed to achieve a consistent combination of clay–water interaction, sorption, and diffusion models. The basic premise considered in the ISD model was to consistently use the same simple surface model design and parameters for describing RNs sorption/diffusion as well as clay surface and porewater chemistry. A simple 1-site non-electrostatic surface complexation model in combination with a 1-site ion exchange model was selected to keep sorption model characteristics relatively robust for compacted systems. Fundamental parameters for the proposed model were evaluated from surface titration data for purified montmorillonite. The resulting basic model was then parameterized on the basis of selected published sorption data-sets for Np(V), Am(III), and U(VI) in dispersed systems, which cover a range of key geochemical conditions such as pH, ionic strength, and carbonate concentration. The sorption trends for these RNs can be quantitatively described by the model considering a full suite of surface species including hydrolytic and carbonate species. The application of these models to the description of diffusive-sorptive transport in compacted bentonites is presented in Part 2. (author)

STUDY OF THERMAL AND ACID STABILITY OF BENTONITE CLAY

Directory of Open Access Journals (Sweden)

Karna Wijaya

2010-06-01

Full Text Available The thermal and acid stability of the bentonite clays (Na- and Ca-bentonite have been tested. The thermal stability testing has been carried out by heating 5 gram of the clays  for five hours at 200, 300 and 500 °C respectively, meanwhile acid stability testing was performed by immersing 5 gram clays into 100 mL sulphuric acid 1M, 2M and 3M for 24 hours. The tested clays, then were characterized by means of X-Ray difractometry and IR-spectroscopy methods. The characterization results showed that upon heating, both Ca- and Na-bentonites indicated same thermal stability. However, upon acid treatment, Na-bentonite was found relatively stabiler and more resistance then Ca-bentonite.   Keywords: bentonite, clay, thermal stability, acid stability.

Granular MX-80 bentonite as buffer material: a focus on swelling characteristics

International Nuclear Information System (INIS)

Rizzi, M.; Laloui, L.; Salager, S.; Marschall, P.

2010-01-01

Document available in extended abstract form only. The Swiss High Level Waste (HLW) disposal concept envisages the emplacement of the waste canisters in horizontal tunnels excavated at a depth of several hundred meters in an over-consolidated clay-stone formation. After waste emplacement the disposal tunnels are backfilled with MX-80 granular bentonite. Research activities are presented in this paper, aimed at characterising the geomechanical behaviour of the MX-80 granular bentonite and at providing the theoretical framework for modelling its response to thermo-hydro- mechanical (THM) perturbations. From the experimental point of view, a series of tests has been designed in order to extract constitutive data and to assess the temperature and suction effects on the mechanical behaviour of the bentonite, paying particular attention in the investigation to the swelling behaviour of the material. As for the theoretical framework an elasto-plastic constitutive model has been developed to take into account those coupled processes of stress, capillary pressure, and temperature to which the bentonite will be submitted,. Bentonite is mainly composed of the smectite mineral montmorillonite with a high swelling capacity which may provide sufficient sealing properties to seal the tunnel without gaps and to restore the buffer continuity. In fact, as bentonite hydrates in the repositories it will expand in those areas where it is allowed and will exert a swelling pressure where the material is confined. The results of both confined and free swelling tests are presented. Confined tests are aiming at determining the pressure applied by the material during complete saturation under isochoric conditions, whereas in the free swelling tests the strain on hydration is measured. Some results from confined swelling tests at ambient temperature are presented. The specimen is compacted uniaxially directly in the cells, the initial dry density being chosen in the range between 1.6 and 1

Consolidation and compaction as a means to prevent settlement of bentonite/sandy silt mixes for use in waste disposal sites

International Nuclear Information System (INIS)

Abeele, W.V.

1985-01-01

The texture of the local Los Alamos tuff is that of a sandy silt with a high hydraulic conductivity. The permeability is dramatically decreased by addition of small amounts of bentonite. The coefficient of consolidation for bentonite/sandy silt ratios decreases inversely proportional with the square of that ratio, whereas the compression index, the swelling index, and the permeability change index increase with increasing bentonite ratio. A strong relationship also exists between the void ratio and the logarithm of the applied stress for any given bentonite ratio. The empirical linear relationship between the void ratio and the logarithm of the applied stress, developed by Taylor, is excellent and enables us to limit the evaluation of conductivity at any void ratio to the measurement of the initial and the desired void ratio, the initial conductivity, and the permeability change index. The decrease in void ratio caused by consolidation or natural compaction of the mixes are scrutinized. Examples of expected settlement and subsidence are calculated based on the known geotechnical characteristics of bentonite/sandy silt mixes. Remedial actions, i.e., means to limit the amount of settlement, are considered. We finally discuss our field experiment, which studies the influence of subsidence on layered systems in general and on biobarriers in particular. 15 refs., 5 tabs

Investigation of Wyoming Bentonite Hydration in Dry to Water-Saturated Supercritical CO2: Implications for Caprock Integrity

Science.gov (United States)

Loring, J. S.; Chen, J.; Thompson, C.; Schaef, T.; Miller, Q. R.; Martin, P. F.; Ilton, E. S.; Qafoku, O.; Felmy, A. R.; Rosso, K. M.

2012-12-01

The effectiveness of geologic sequestration as an enterprise for CO2 storage depends partly on the reactivity of supercritical CO2 (scCO2) with caprock minerals. Injection of scCO2 will displace formation water, and the pore space adjacent to overlying caprocks could eventually be dominated by dry to water-saturated scCO2. Caprock formations have high concentrations of clay minerals, including expandable montmorillonites. Water-bearing scCO2 is highly reactive and capable of hydrating or dehydrating clays, possibly leading to porosity and permeability changes that directly impact caprock performance. Dehydration will cause montmorillonite clay minerals in caprocks to contract, thereby decreasing solid volume and possibly increasing caprock permeability and porosity. On the other hand, water intercalation will cause these clays to expand, thereby increasing solid volume and possibly leading to self-sealing of caprock fractures. Pacific Northwest National Laboratory's Carbon Sequestration Initiative is developing capabilities for studying wet scCO2-mineral reactions in situ. Here, we introduce novel in situ infrared (IR) spectroscopic instrumentation that enables quantitative titrations of reactant minerals with water in scCO2. Results are presented for the infrared spectroscopic titrations of Na-, Ca-, and Mg-saturated Wyoming betonites with water over concentrations ranging from zero to scCO2 saturated. These experiments were carried out at 50°C and 90 bar. Transmission IR spectroscopy was used to measure concentrations of water dissolved in the scCO2 or intercalated into the clays. The titration curves evaluated from the transmission-IR data are compared between the three types of clays to assess the effects of the cation on water partitioning. Single-reflection attenuated total reflection (ATR) IR spectroscopy was used to collect the spectrum of the clays as they hydrate at every total water concentration during the titration. Clay hydration is evidenced by

New quantitative methods for mineral and porosity mapping in clayey materials: application to the compacted bentonites of engineered barriers

International Nuclear Information System (INIS)

Pret, D.

2003-12-01

Clayey materials are well known for their non permeable properties and their textural changes between the dry and hydrated states. Their porous network is classically investigated in the dry state using bulk measurements. However, the relationship between porosity and mineral spatial heterogeneities in the hydrated state is poorly understood. The textural analysis limits induce some difficulties to understand the migration of solute species into compacted bentonites (as for nuclear waste repository). The goal of this work is to improve the analysis techniques for hydrated clayey materials in order to provide a multi-scale quantitative petrography. The bentonite samples are impregnated using a resin whose properties are close to water ones. The classical petrographic study reveals strong heterogeneities of spatial and size distributions of porosity and minerals. SEM images analysis allows a quantification and a simple mapping of pores and minerals into unaltered bentonites. Nevertheless, as alterations are suspected to happen in the repository context, two methods for the analysis of all types of materials have been also developed. Two specific softwares permits the treatments of autoradiographs and chemical element maps obtained using electron microprobe. The results are quantitative maps highlighting the spatial porosity heterogeneities from the decimetric to the micrometric scales. All pore sizes are taken into account including clay interlayer spaces. Moreover, an accurate mineral mapping is also supplied on millimetric areas with a spatial resolution close to the micrometer. In a widely point of view, this work provides new complementary tools for the textural analysis of fine grained materials and the improvement of migration modelling of solute species. (author)

Studies on the chemical conditions and microstructure in the reference bentonites of alternative buffer materials project (ABM) in Aespoe

International Nuclear Information System (INIS)

Muurinen, A.

2009-06-01

The chemical and microstructural properties of some bentonites used in the ABM project in Aespoe HRL were studied in laboratory experiments. The aim was to obtain information about the materials before they were used in the field experiment and to test the research methods that will be used when the packages of the field experiment are retrieved. The bentonites of interest were MX-80, Deponit CAN, Asha 505 and Friedland Clay. The pH values in the compacted samples prepared from the clay powders and deionized water were about 8 for MX-80, 7 for Deponit and Asha, and 6.5 for Friedland clay. The Eh values in the compacted MX-80, Asha and Deponit samples varied between 100 mV and -100 mV, and in the Friedland clay from 0 mV to 200 mV. The total porosity, chloride porosity and the microstructure were studied in compacted samples prepared from MX-80, Deponit, Asha and Friedland Clay and equilibrated through filter plates with 0.1 M NaCl solution for 12.5 months in aerobic conditions. The dry densities of the samples were approximately 0.7, 1.0, 1.25 and 1.55 g/cm 3 . XRD and SAXS (Small Angle X-ray Scattering) were used to study the microstructure of the MX-80 and Deponit bentonites. It was obvious that the chloride porosity was lower than the water porosity in all the clays, which indicates the exclusion of anions caused by the negatively charged surfaces. In the XRD measurements on MX-80, Asha and Deponit, the measured basal spaces represented by the diffraction peaks were smaller than the theoretical one assuming a homogenous microstructure. This indicates that there was a substantial amount of water also in the pores, which were not seen by XRD. The SAXS data modelling which considered single discs and stacks of discs proposed that a large fraction of the clay should be considered as single platelets. The fraction of the single discs decreased with the increasing density of the sample. The number of layers in the stacks varied from 4 to 8. By combining the

Influence of selected factors on strontium sorption on bentonites

International Nuclear Information System (INIS)

Galambos, M.; Kufcakova, J.; Rajec, P.

2007-01-01

Sorption on bentonite will play an important role in retarding the migration of radionuclides from a waste repository. Bentonite is a natural clay and one of the most promising candidates for use as a buffer material in the geological disposal systems for high-level nuclear waste. It is intended to isolate metal canisters with highly radioactive waste products from the surrounding rocks because of its ability to retard the movement of radionuclides by sorption. Bentonite is characterized by low permeability, water swelling capability and excellent sorption potential for cationic radionuclides. To correctly assess the sorption potential of radionuclides on bentonite is essential for the development of predictive migration models. The sorption of strontium on bentonite from different Slovak deposits - Jelsovy potok, Kopernica and Lieskovec has been investigated under various experimental conditions, such as contact time, sorbate concentrations, presence of complementary cation. Sorption was studied using the batch technique. The uptake of Sr was rapid and equilibrium was reached almost instantaneously. The instantaneous uptake may be due to adsorption and/or exchange of the metal with some ions on the surface of the adsorbent. The best sorption characteristics distinguish bentonite Kopernica, sorption capacity for Sr of the fraction under 45 mm is 0,48 mmol·g -1 for Sr. The highest values of distribution coefficient were reached for the bentonite Jelsovy potok. Radiation stability has been investigated, the higher sorption parameters were observed for the irradiated bentonites, which can be explained by the increase of specific surface of the bentonite samples. The presence of complementary cations depresses the sorption of Sr on bentonite. Cations Ca 2+ exhibit higher effect on cesium sorption than the Na 2+ ions. Results indicate that the sorption of Sr 2+ on bentonite will be affected by the presence of high concentrations of various salts in the waste water

Corrosion of high-level radioactive waste iron-canisters in contact with bentonite

Energy Technology Data Exchange (ETDEWEB)

Kaufhold, Stephan, E-mail: s.kaufhold@bgr.de [BGR, Bundesanstalt für Geowissenschaften und Rohstoffe, Stilleweg 2, D-30655 Hannover (Germany); Hassel, Achim Walter [Max-Planck-Institut für Eisenforschung GmbH, Max-Planck-Straße 1, D-40237 Düsseldorf (Germany); Institute for Chemical Technology of Inorganic Materials, Johannes Kepler University Linz, Altenberger Straße 69, 4040 Linz (Austria); Sanders, Daniel [Max-Planck-Institut für Eisenforschung GmbH, Max-Planck-Straße 1, D-40237 Düsseldorf (Germany); Dohrmann, Reiner [BGR, Bundesanstalt für Geowissenschaften und Rohstoffe, Stilleweg 2, D-30655 Hannover (Germany); LBEG, Landesamt für Bergbau, Energie und Geologie, Stilleweg 2, D-30655 Hannover (Germany)

2015-03-21

Graphical abstract: Corrosion at the bentonite iron interface proceeds unaerobically with formation of an 1:1 Fe silicate mineral. A series of exposure tests with different types of bentonites showed that Na–bentonites are slightly less corrosive than Ca–bentonites and highly charges smectites are less corrosive compared to low charged ones. The formation of a patina was observed in some cases and has to be investigated further. - Highlights: • At the iron bentonite interface a 1:1 Fe layer silicate forms upon corrosion. • A series of iron–bentonite corrosion products showed slightly less corrosion for Na-rich and high-charged bentonites. • In some tests the formation of a patina was observed consisting of Fe–silicate, which has to be investigated further. - Abstract: Several countries favor the encapsulation of high-level radioactive waste (HLRW) in iron or steel canisters surrounded by highly compacted bentonite. In the present study the corrosion of iron in contact with different bentonites was investigated. The corrosion product was a 1:1 Fe layer silicate already described in literature (sometimes referred to as berthierine). Seven exposition test series (60 °C, 5 months) showed slightly less corrosion for the Na–bentonites compared to the Ca–bentonites. Two independent exposition tests with iron pellets and 38 different bentonites clearly proved the role of the layer charge density of the swelling clay minerals (smectites). Bentonites with high charged smectites are less corrosive than bentonites dominated by low charged ones. The type of counterion is additionally important because it determines the density of the gel and hence the solid/liquid ratio at the contact to the canister. The present study proves that the integrity of the multibarrier-system is seriously affected by the choice of the bentonite buffer encasing the metal canisters in most of the concepts. In some tests the formation of a patina was observed consisting of Fe�

Alteration of bentonite when contacted with supercritical CO2

Science.gov (United States)

Jinseok, K.; Jo, H. Y.; Yun, S. T.

2014-12-01

Deep saline formations overlaid by impermeable caprocks with a high sealing capacity are attractive CO2 storage reservoirs. Shales, which consist of mainly clay minerals, are potential caprocks for the CO2 storage reservoirs. The properties of clay minerals in shales may affect the sealing capacity of shales. In this study, changes in clay minerals' properties when contacted with supercritical (SC) CO2 at various conditions were investigated. Bentonite, whichis composed of primarily montmorillonite, was used as the clay material in this study. Batch reactor tests on wet bentonite samples in the presence of SC CO2 with or without aqueous phases were conducted at high pressure (12 MPa) and moderate temperature (50 oC) conditions for a week. Results show that the bentonite samples obtained from the tests with SC CO2 had less change in porosity than those obtained from the tests without SC CO2 (vacuum-drying) at a given reaction time, indicating that the bentonite samples dried in the presence of SC CO2 maintained their structure. These results suggest that CO2 molecules can diffuse into interlayer of montmorillonite, which is a primary mineral of bentonite, and form a single CO2 molecule layer or double CO2 molecule layers. The CO2 molecules can displace water molecules in the interlayer, resulting in maintaining the interlayer spacing when dehydration occurs. Noticeable changes in reacted bentonite samples obtained from the tests with an aqueous phase (NaCl, CaCl2, or sea water) are decreases in the fraction of plagioclase and pyrite and formation of carbonate minerals (i.e., calcite and dolomite) and halite. In addition, no significant exchanges of Na or Ca on the exchangeable complex of the montmorillonite in the presence of SC CO2 occurred, resulting in no significant changes in the swelling capacity of bentonite samples after reacting with SC CO2 in the presence of aqueous phases. These results might be attributed by the CO2 molecule layer, which prevents

Elastoplastic constitutive models parameters for unsaturated compacted bentonite sand buffer (BSB)

International Nuclear Information System (INIS)

Priyanto, D.; Man, A.; Dixon, D.; Blatz, J.

2010-01-01

Document available in extended abstract form only. Compacted Bentonite-Sand Buffer (BSB) material is one of the clay based sealing-system components proposed for use in a Canadian Deep Geological Repository (DGR) for used nuclear fuel. BSB is a 50:50 mixture (by dry mass) of bentonite and well-graded silica sand, compacted to a dry density of at least 1.67 Mg/m 3 . Numerical modelling of the evolution of a DGR requires defining of the Hydro-Mechanical (HM) parameters of the BSB. The objective of this paper is to determine the parameters that are needed to utilize an elastoplastic model to describe the BSB. The parameters of the Basic Barcelona Model (BBM) for BSB are determined based on the results of laboratory tests done under both water-saturated and unsaturated conditions. The BBM utilizes three key stress-state variables: net mean stress (p), deviatoric stress (q), and suction (s). Modification of the BBM to improve the prediction of the BSB behaviour is made based on these laboratory test results. Pre-consolidation stress (p o ), stiffness parameters due to changes in p in elastic (?) and plastic (λ(s)) ranges are determined from triaxial test results under isotropic loading, unloading and constant mass conditions with suctions in the range of 0-125 MPa. An increase of s results in an increase of p o and a decrease of λ(s) for s < 30 MPa, and constant po and λ(s) for s > 30 MPa. These data are used to determine the LC-Line. Blatz (2000) and Anderson (2003) concluded that the BSB has clay-dominated behaviour for s < 30 MPa and sand-dominated behaviour for s > 30 MPa. Based on this conclusion, the hardening parameter so of the suction increase yield curve is equal to 30 MPa. Using a measured s-v relationship from shrinkage tests, stiffness parameters for changes in s in the elastic range (?s) are approximately ∼ 0.065 and in the plastic range (λs) are approximately ∼ 0, which is different from the original BBM featuring λs > ?s. The tensile strength

Thermal effect on water retention curve of bentonite: experiment and thermodynamic modeling

International Nuclear Information System (INIS)

Qin Bing; Chen Zhenghai; Sun Faxin; Liu Yuemiao; Wang Ju

2012-01-01

The thermal effects on water retention curve of GMZ bentonite were investigated experimentally and theoretically. Water retention tests were conducted on GMZ bentonite at five temperatures ranging from 20℃ to 100℃. Test results showed that the water retention capacity and the hysteresis of the water retention curve decreased with increasing temperature, and that the water retention curves at different temperatures were almost parallel to each other. Based on the thermodynamics of sorption, a model was established to describe the temperature influence on the water retention curve. The model was validated by comparing the model predictions and the test results. (authors)

Optimization of bentonite pellet properties

International Nuclear Information System (INIS)

Sanden, Torbjoern; Andersson, Linus; Jonsson, Esther; Fritzell, Anni

2012-01-01

Document available in extended abstract form only. SKB in Sweden is developing and implementing concepts for the final disposal of spent nuclear fuel. A KBS-3V repository consists of a deposition tunnel with copper canisters containing spent fuel placed in vertical deposition holes. The canisters are embedded in highly compacted bentonite. After emplacement of canisters and bentonite blocks, the tunnels will be backfilled and sealed with an in-situ cast plug at the entrance. The main concept for backfilling the deposition tunnels imply pre compacted blocks of bentonite stacked on a bed of bentonite pellet. The remaining slot between blocks and rock will be filled with bentonite pellets. The work described in this abstract is a part of the ASKAR-project which main goal is to make a system design based on the selected concept for backfilling. Immediately after starting the backfill installation, inflowing water from the rock will come in contact with the pellet filling and thereby influence the characteristics of the pellet filling. The pellet filling helps to increase the average density of the backfill, but one of the most important properties beside this is the water storing capacity which will prevent water from reaching the backfill front where it would disturb and influence the quality of the installation. If water flows through the pellet filling out to the backfilling front, there will be erosion of material which also will affect the quality of the installed backfill. In order to optimize the properties regarding water storing capacity and sensitivity for erosion a number of tests have been made with different pellet types. The tests were made in different scales and with equipment specially designed for the purpose. The performed tests can be divided in four parts: 1. Standard tests (determining water content and density of pellet fillings and individual pellets, compressibility of the pellet fillings and strength of the individual pellets); 2. Erosion

Use of clays as buffers in radioactive repositories

International Nuclear Information System (INIS)

Pusch, R.

1983-05-01

For use as canister overpack, highly compacted bentonite is superior to illite and any reasonably montmorillonite-rich bentonite will do which is not too rich in sulphur. The organic content should be low and heat treatment may be required to bring this content down to an acceptable level. Heating to slightly more than 400degreeC does not affect the physical properties of neither montmorillonite, nor illite to a significant extent. Bentonite is also very suitable for use as sealing plugs in the form of highly compacted blocks. For use as backfill in tunnels and shafts, illitic clay is a candidate material which can be compacted on site to the rather high density that is required. Where a swelling capacity is needed, such as in the top part of tunnels, bentonite-based backfills are suitable and if Na saturated clay is used the bentoite fraction can be kept low. Thus, a 10 percent content of Na bentonite by weight should generally be sufficient for a well compacted mixture with respect to the required hydraulic conductivity, while a 20-30 percent content may be needed to arrive at a sufficient swelling power. The choice of a suitable clay material requires that the substance be properly characterized and tested. It is concluded that rather rigorous analyses are necessary as concerns overpacks, including mineralogical and granulometrical tests and the determination of the swelling characteristics as well as of certain chemical features. For backfills and for the current checking of all sorts of clay for use as buffer materials, the natural water content, the liquid limit and the swelling ability have to be determined, since they are the fingerprints of this type of soil. (author)

Laboratory tests to determine the effect of Olkiluoto bounding brine water on buffer performance

International Nuclear Information System (INIS)

Martikainen, J.; Schatz, T.

2011-10-01

This report presents a set of results from laboratory studies on the effect of bounding brine water exposure on buffer performance. In order to evaluate the effect of bounding brine water exposure on compacted bentonite buffer performance a series of experiments were conducted using swelling pressure and hydraulic conductivity measurements as follows: Direct exposure measurements were performed on MX-80 bentonite samples encompassing a range of dry density values from 1334 to 1585 kg/m 3 . These samples were saturated directly with a 70 g/L solution composed of calcium and sodium chloride at a Ca 2+ /Na + mass ratio of 3:2. Direct exposure measurements were performed on IBECO RWC samples encompassing a range of dry density values from 1314 to 1564 kg/m 3 . These samples were saturated directly with a 68.45 g/L solution composed of calcium and sodium chloride at a Ca 2+ /Na + mass ratio of 3.2:2. A set of MX-80 and IBECO RWC samples encompassing a range of dry density values from 1018 to 1607 kg/m 3 were initially saturated with tap water followed by (indirect) exposure to a 68.45 g/L solution composed of calcium and sodium chloride at a Ca 2+ /Na + mass ratio of 3.2:2. Sample swelling pressures were continuously monitored and hydraulic conductivity measurements were performed at each constant swelling pressure condition. In some cases, exchangeable cation analyses were performed. The specific test results are summarized as follows: All of the measured swelling pressure values upon exposure to bounding brine water were lower than the corresponding values after saturation with tap water. The relative swelling pressure decrease for the IBECO RWC samples was approximately half of the corresponding decrease for the MX-80 samples. On exposure to bounding brine water, hydraulic conductivity values were increased at the lowest densities, for both the MX-80 and IBECO samples, while at higher densities hydraulic conductivity values were essentially equivalent, for both the

Characterization of bentonite pore structure by combining chloride porosity and SAXS measurements

International Nuclear Information System (INIS)

Muurinen, A.

2010-01-01

Document available in extended abstract form only. The total water porosity, chloride porosity and the microstructure were studied in compacted samples prepared from MX-80 and Deponit bentonites equilibrated through filter plates with 0.1 M NaCl solution for 12.5 months. The dry densities of the samples varied approximately from 0.7 to 1.55 g/cm 3 . XRD and SAXS (Small Angle X-ray Scattering) were used to study the microstructure of the bentonites. It was obvious that the chloride porosity was lower than the water porosity in both clays, which indicates the exclusion caused by the negatively charged montmorillonite surfaces. In the XRD and SAXS measurements the measured basal spaces represented by the diffraction peaks were smaller than the theoretical ones assuming a homogenous microstructure. This indicates that there was a substantial amount of water also in the pores, which were not represented by the peaks. This could explain the difference between the measured chloride porosity and the modelling curve obtained with the Donnan model. By combining the information from the SAXS measurements and the chloride exclusion measurements, it was possible to evaluate the volumes of the soft and dense fractions and the pore sizes in each fraction for MX-80. The chloride porosity was mostly caused by the pores in the soft clay where the pore size is larger. The volume of the soft fraction decreased and its density increased with increasing density of the sample. (authors)

Investigation into the behaviour of bentonite in contact with magnetite and iron under the conditions of a final repository

International Nuclear Information System (INIS)

Mueller-Vonmoos, M.; Kahr, G.; Bucher, F.; Madsen, F.; Mayor, P.A.

1991-05-01

This report presents the results of investigations into how magnetite and iron affect the swelling behaviour of the Na-bentonite MX-80 and the Ca-bentonite Montigel. The experiments were conducted under conditions similar to those expected in a repository and covered cation exchange capacity, exchangeable cations and the swelling behaviour of the Na-bentonite MX-80 and the Ca-bentonite Montigel. Waste disposal is assumed to occur at a temperature of 80 o C under an anoxic atmosphere. In addition to this, the behaviour of trivalent iron in the interlayer space of montmorillonite was investigated. The investigations confirmed that contact between iron and bentonite under such conditions leads mainly to formation of magnetite and hydrogen. Montmorillonite does not take up iron by cation-exchange, either on contact with magnetite or with iron itself. The trivalent iron is unstable in the interlayer space of the montmorillonite and is exchanged mainly for aluminium; no change in the interlayer charge can be determined in such a case. It is therefore to be assumed that the aluminium is taken up from the edges of the clay particles into the interlayer space, but that no chlorite formation can be observed during this process. At 80 o C and 150 o C, the swelling pressures of the highly compacted bentonite-iron samples, related to the dry density of the bentonites, corresponded more or less to the swelling pressures of the untreated bentonites. The swelling pressure of the Fe(III)-bentonites was around 50% higher. It is assumed that this is mainly due to the high hydration energy of the iron and aluminium ions. 6 figs., 6 tabs., 13 refs

Pore water chemistry of domestic bentonite for the buffer of a repository: analysis of experimental data

International Nuclear Information System (INIS)

Lee, Jae Owan; Cho, Won Jin; Chun, Kwan Sik; Kang, Chul Hyung

1999-04-01

Experiments were conducted using synthetic ground water and domestic bentonite. Upon reaction of the bentonite and ground water, ionic concentration, ph and Eh nearly reached a steady-state within a few days. The pore water chemistry was dominated mainly by the mineralogical composition of bentonite. Analytic results showed that sodium, sulfate, and carbonate were major ions, and their concentrations increased to about 4-5 times those of original ground water. The ph increased from 8.1 to 8.9, and the Eh were between 365 mV and 375 mV. The concentration of most dissolved ions increased with increasing bentonite-to-ground water ratio. On the contrary, the ph and Eh were little affected by bentonite-to-ground water ratio. The dependence of ionic concentration upon temperature had different trends with different ions. Little change in the ph occurred up to 80 dg C, and decreased beyond the value of temperature. The Eh rather increased beyond 80 dg C on contrary to ph. (Author). 21 refs., 4 tabs., 18 figs

Rheological Behavior of Bentonite-Polyester Dispersions

Science.gov (United States)

Abu-Jdayil, Basim; Al-Omari, Salah Addin

2013-07-01

The rheological behavior of a bentonite clay dispersed in unsaturated polyester was investigated. The effects of the solid content and particle size on the steady and transient rheological properties of the dispersions were studied. In addition, two types of bentonite with different Na+/Ca+2 ratio were used in this study. The Herschel-Bulkley and the Weltman models were used to describe the apparent viscosity of the bentonite-polyester composite in relation to the shear rate and shearing time. The bentonite-polyester dispersions were found to exhibit both Newtonian and non-Newtonian behavior. The transition from a Newtonian to a Bingham plastic and then to a shear-thinning material with a yield stress was found to depend on the solid concentration, the particle size, and the type of bentonite. At a low solid content, the apparent viscosity of the bentonite dispersion increased linearly with solid concentration. But a dramatic increase in the apparent viscosity beyond a solid content of 20 wt.% was observed. On the other hand, a thixotropic behavior was detected in bentonite-polyester dispersions with a high solid content and a low particle size. However, this behavior was more pronounced in dispersions with a high Na+/Ca+2 ratio.

Thermal properties of bentonite under extreme conditions

Energy Technology Data Exchange (ETDEWEB)

Vasicek, R. [Czech Technical Univ., Centre of Experimental Geotechnics, Faculty of Civil Engineering, Prague (Czech Republic)

2005-07-01

Centre of Experimental Geotechnics (CEG) deals with the research of the behaviour of bentonite and clays. The measurement of thermal properties is not so frequent test in geotechnical laboratory but in relation to deep repository it is a part which should not be overlooked. The reason is the heat generated by canister with spent nuclear fuel and possible influence of the heat on the materials of the engineered barrier. In the initial stages following the burial of canister with the waste the barrier materials will be exposed to elevated temperature. According to existing information, these temperatures should not exceed 90 C. That heat can induce a creation of cracks and opening of joint between highly compacted blocks. It will predispose the bentonite barrier to penetration of water from surrounding towards to canister. Therefore easy removal of heat through the barrier is required. It is essential that the tests aimed at determining the real values of measured parameters are carried out in conditions identical with those anticipated in a future disposal system. These relatively complicated thermophysical tests are logical continuation of the simple ones, carried out under laboratory temperature and on not fully saturated samples without possibility to measure the swelling pressure. Thermophysical properties and swelling pressure are dominantly influenced by water content (which is influenced by temperature). Therefore is important to realize the tests under different moisture and thermal conditions. These tests are running at the APT-PO1 Analyser, designed to fulfill mentioned requirements - it allows measurement of thermal properties under temperature up to 200 C and swelling pressure up to 20 MPa. The device is capable to register the evolution of temperature, swelling and vapor pressure. The measurement of thermal conductivity and volume heat capacity is realized by the dynamic impulse method with point source of heat. Four types of tests are possible: at

Preparation of sol-gel TiO2/purified Na-bentonite composites and their photovoltaic application for natural dye-sensitized solar cells

International Nuclear Information System (INIS)

Saelim, Ni-on; Magaraphan, Rathanawan; Sreethawong, Thammanoon

2011-01-01

Highlights: → Natural dye from red cabbage was successfully employed in DSSC. → A fast sol-gel method to produce TiO 2 /clay thin film was proposed. → The sol-gel-prepared TiO 2 /clay was applied as the scattering layer on top of TiO 2 electrode. → Thicker sol-gel-prepared TiO 2 /clay electrode showed higher DSSC efficiency. - Abstract: The sol-gel TiO 2 /purified natural clay electrodes having Ti:Si molar ratios of 95:5 and 90:10 were initially prepared, sensitized with natural red cabbage dye, and compared to the sol-gel TiO 2 electrode in terms of physicochemical characteristics and solar cell efficiency. The results showed that the increase in purified Na-bentonite content greatly increased the specific surface area and total pore volume of the prepared sol-gel TiO 2 /purified Na-bentonite composites because the clay platelets prevented TiO 2 particle agglomeration. The sol-gel TiO 2 /5 mol% Si purified Na-bentonite and sol-gel TiO 2 /10 mol% Si purified Na-bentonite composites could increase the film thickness of solar cells without cracking when they were coated as a scattering layer on the TiO 2 semiconductor-based film, leading to increasing the efficiency of the natural dye-sensitized solar cells in this work.

Effect of dry density and temperature on the hydraulic conductivity of domestic compacted bentonite as a buffer material in the high level waste repository

International Nuclear Information System (INIS)

Cho, Won Jin; Chun, Kwan Sik; Lee, Jae Owan

1999-02-01

This study is intended to investigate the effect of dry density and temperature on the hydraulic conductivity of domestic calcium bentonite. The dry densities of bentonite are 1.4 Mg/m 3 , 1.6 Mg/m 3 and 1.6 Mg/m, and the temperatures are in the range of 20 dg C to 150 dg C. The hydraulic conductivities of compacted bentonite with dry densities higher than 1.4 Mg/m 3 are lower than 10 -1 1 m/s, and are low enough to inhibit the radionuclide release by advection through the buffer. The hydraulic conductivities at the temperature of 150 dg C increase up to about 1 order higher than those at 20 dg C. (author). 28 refs., 5 tabs., 20 figs

Corrosion of copper and authigenic sulfide mineral growth in hydrothermal bentonite experiments

Energy Technology Data Exchange (ETDEWEB)

Caporuscio, F.A., E-mail: floriec@lanl.gov [Los Alamos National Laboratory, Earth and Environmental Sciences, MS J966, Los Alamos, NM 87545 (United States); Palaich, S.E.M. [University of California, Los Angeles, CA 90095 (United States); Cheshire, M.C. [Los Alamos National Laboratory, Earth and Environmental Sciences, MS J966, Los Alamos, NM 87545 (United States); Jové Colón, C.F. [Sandia National Laboratory, Albuquerque, NM 87185 (United States)

2017-03-15

The focus of this experimental work is to characterize interaction of bentonite with possible used-fuel waste container materials. Experiments were performed up to 300 °C at 150–160 bars for five to six weeks. Bentonite was saturated with a 1900 ppm K-Ca-Na-Cl-bearing water with Cu-foils. Copper rapidly degrades into chalcocite (CuS{sub 2}) and minor covellite (CuS) in the presence of H{sub 2}S. Chalcocite growth and corrosion pit depths were measured for four different experimental runs yielding corrosion rates between 8.8 and 116 μm/yr depending on duration of experiment, brine composition, and clay type (bentonite vs. Opalinus Clay). Results of this research show that although pit-corrosion is demonstrated on Cu substrates, experiments show that the reactions that ensue, and the formation of minerals that develop, are extraordinarily slow. This supports the use of Cu in nuclide-containment systems as a possible engineered barrier system material. - Highlights: • Experiments run at 300 °C and 150 bars for up to six weeks. • Copper degrades to chalcocite (CuS2) and minor covellite (CuS) in presence of H2S. • Corrosion rates between 8.8 and 116 μm/yr. • Rate dependent on experiment duration, brine composition, and clay type. • Sulfide corrosion products may inhibit further corrosion of copper.

Salt content impact on the unsaturated property of bentonite-sand buffer backfilling materials

Energy Technology Data Exchange (ETDEWEB)

Zhang Ming [Key Laboratory of Mechanics on Disaster and Environment in Western China, Lanzhou University, Lanzhou 730000 (China); Zhang Huyuan, E-mail: p1314lvp@yahoo.com.cn [Key Laboratory of Mechanics on Disaster and Environment in Western China, Lanzhou University, Lanzhou 730000 (China); Jia Lingyan; Cui Suli [Key Laboratory of Mechanics on Disaster and Environment in Western China, Lanzhou University, Lanzhou 730000 (China)

2012-09-15

Highlights: Black-Right-Pointing-Pointer SWCC and infiltration process of bentonite-sand mixtures is researched. Black-Right-Pointing-Pointer The k{sub u} of bentonite-sand mixtures was evaluated as the buffer backfilling materials. Black-Right-Pointing-Pointer Salt content impacting on the unsaturated property of bentonite-sand materials is small. - Abstract: Bentonite mixed with sand is often considered as possible engineered barrier in deep high-level radioactive waste disposal in China. In the present work, the vapor transfer technique and water infiltration apparatus were used to measure the soil water characteristic curve (SWCC) and unsaturated hydraulic conductivity (k{sub u}) of bentonite-sand mixtures (B/S) effected by salt content. Results show, the water-holding capacity and k{sub u} increase slightly with the concentration of Na{sup +} in pore liquid increasing from 0 g/L to 12 g/L, similar with the solution concentration of Beishan groundwater in China. Salt content in the laboratory produced only one order of magnitude increase in k{sub u}, which is the 'safe' value. The different pore liquid concentrations used in this study led to small differences in thickness of diffuse double layer of bentonite in mixtures, this might explain why some differences have been found in final values of k{sub u}.

Study on chemical buffering property of GMZ sodium bentonite in air

International Nuclear Information System (INIS)

Wen Zhijian; Liu Yuemiao; Zong Zihua; Zhou Jia

2008-01-01

The high level radioactive wastes are characterized by very high initial radioactivity, the longer-lived actinides, many of actinides alpha-emitters. At present, the deep geological disposal is regarded as the most reasonable and effective way to safely disposal high-level radioactive wastes in the world. The conceptual model of HLW geological disposal in China is based on a multi-barrier system that combines an isolating geological environment with an engineered barrier system. The buffer is one of the engineered barrier materials and GMZ Na-bentonite is selected as the base material. The most important role related to buffer is chemical buffering, which means buffering of changes in water chemistry. This paper presents the experiments of GMZ-1 Na-bentonite reacted with distilled water in the air. The results and discussion of bench tests are reported. (authors)

Geochemical Processes and compacted bentonite FEBEX with a thermohydraulic gradient with a thermohydraulic gradient; Procesos geoquimicos y modificaciones texturales en bentonita FEBEX compactada sometida a un gradiente termohidraulico

Energy Technology Data Exchange (ETDEWEB)

Leguey Jimenez, S; Cuevas Rodriguez, J; Martin Barca, M; Vigil de la Villa Mencia, R.; Ramirez Martin, S; Garcia Gimenez, R [Universidad Autonoma de Madrid (Spain)

2002-07-01

At present, the main source of High Level radioactive Waste (HLW) is the electrical energy production during all sep of developing. In almost all the countries with nuclear programs, the option for the final management of HLW is the Deep Geological Repository (DGR), based on the concept of multi barrier. According to this concept, the wastes is isolated from biosphere by the interposition of confinement barrier. In the context of an investigation of the near field for a repository of HLW, the FEBEX Project, a set of laboratory test has been designed to give a better understanding of the thermo-hydro-mechanical and geochemical behaviour of the compacted bentonite as a confinement barrier. The object of these work is to analyse the properties of the bentonite and its behaviour under conditions that will be found in a repository. The precipitation of mineral phases, due to local changes in the chemical equilibrium and the hydration itself, can produce changes in the salinity of the interstitial water and in the microstructural organisation of the clay particles. the hydraulic and mechanical properties of the bentonite can be modified by the special conditions of the barrier. (Author)

BENTONITE-QUARTZ SAND AS THE BACKFILL MATERIALS ON THE RADIOACTIVE WASTE REPOSITORY

Directory of Open Access Journals (Sweden)

Raharjo Raharjo

2010-06-01

Full Text Available An investigation of the contribution of quartz sand in the bentonite mixture as the backfill materials on the shallow land burial of radioactive waste has been done. The experiment objective is to determine the effect of quartz sand in a bentonite mixture with bentonite particle sizes of -20+40, -40+60, and -60+80 mesh on the retardation factor and the uranium dispersion in the simulation of uranium migration in the backfill materials. The experiment was carried out by the fixed bed method in the column filled by the bentonite mixture with a bentonite-to-quartz sand weight percent ratio of 0/100, 25/75, 50/50, 75/25, and 100/0 on the water saturated condition flown by uranyl nitrate solution at concentration (Co of 500 ppm. The concentration of uranium in the effluents in interval 15 minutes represented as Ct was analyzed by spectrophotometer, then using Co and Ct, retardation factor (R and dispersivity ( were determined. The experiment data showed that the bentonite of -60+80 mesh and the quartz sand of -20+40 mesh on bentonite-to-quartz sand with weight percent ratio of 50/50 gave the highest retardation factor and dispersivity of 18.37 and 0.0363 cm, respectively.   Keywords: bentonite, quartz sand, backfill materials, radioactive waste

Temperature effect on the behaviour of engineered clay barriers

International Nuclear Information System (INIS)

Tang, A.M.

2005-11-01

The present work deals with the thermo-hydro-mechanical behaviour of compacted swelling clay used for engineered barriers in high-level radioactive repositories. The MX80 bentonite was chosen for this work. Firstly, an experimental work on the thermal conductivity of the compacted bentonite was performed. The results evidenced the effects of dry density, water content, volumetric fraction of soil components, microstructure, and mineralogy. This experimental work gave rise to the proposition of a theoretical model for estimate the thermal conductivity of compacted bentonites. Secondly, after a calibration of suction generated by saturated saline solution in function of temperature, water retention curves were determined at different temperatures. The experimental results showed a decrease of the water retention capacity of soil after heating. A simple model based on the interfacial tension air-water was formulated to simulate this effect. Thirdly, a new isotropic cell enabling a simultaneous control of suction, temperature and mechanical stress was developed. With this new cell, an experimental work on the thermo-mechanical behaviour of the unsaturated compacted bentonite was performed. Finally, a constitutive model was developed for simulate the thermo-hydro-mechanical behaviours obtained experimentally. (author)

Temperature effect on the behaviour of engineered clay barriers; Effet de la temperature sur le comportement des barrieres de confinement

Energy Technology Data Exchange (ETDEWEB)

Tang, A.M

2005-11-15

The present work deals with the thermo-hydro-mechanical behaviour of compacted swelling clay used for engineered barriers in high-level radioactive repositories. The MX80 bentonite was chosen for this work. Firstly, an experimental work on the thermal conductivity of the compacted bentonite was performed. The results evidenced the effects of dry density, water content, volumetric fraction of soil components, microstructure, and mineralogy. This experimental work gave rise to the proposition of a theoretical model for estimate the thermal conductivity of compacted bentonites. Secondly, after a calibration of suction generated by saturated saline solution in function of temperature, water retention curves were determined at different temperatures. The experimental results showed a decrease of the water retention capacity of soil after heating. A simple model based on the interfacial tension air-water was formulated to simulate this effect. Thirdly, a new isotropic cell enabling a simultaneous control of suction, temperature and mechanical stress was developed. With this new cell, an experimental work on the thermo-mechanical behaviour of the unsaturated compacted bentonite was performed. Finally, a constitutive model was developed for simulate the thermo-hydro-mechanical behaviours obtained experimentally. (author)

Diffusion of radionuclides in concrete/bentonite systems

International Nuclear Information System (INIS)

Albinsson, Y.; Boerjesson, S.; Andersson, K.; Allard, B.

1993-02-01

In a repository for nuclear waste, different construction materials will be used. Two important materials among these are concrete and bentonite clay. These will act as mechanical barriers, preventing convective water flow and also retard transport due to diffusion of dissolved radionuclides by a combination of mechanical constraints and chemical interactions with the solid. An important issue is the possible change of the initial sodium bentonite into the calcium form due to ion exchange with calcium from the cement. The initial leaching of the concrete has been studied using radioactive spiked concrete in contact with compacted bentonite. The diffusion of Cs, Am and Pu into 5 different types of concrete in contact with porewater have been measured. The measured diffusivity for Cs agrees reasonable well with data found in literature. For Am and Pu no movement could be measured (less than 0.2 mm) even though the contact times were extremely long (2.5 y and 5 y, respectively). This report gives also a summary of the previously published results about sorption and diffusion of radionuclides in cement performed in Prav/KBS/SKB projects 1980-1990. 25 refs

Study on the basic property of Gaomiaozi bentonite, inner mongolia

International Nuclear Information System (INIS)

Liu Yuemiao; Xu Guoqing; Liu Shufen; Chen Zhangru

2001-01-01

Buffer/backfill material layer is one of important engineered barriers in the HLW geological repository. The geologic setting of Gaomiaozi bentonite deposit is introduced, and the mineral composition, physical and chemical property, basic geotechnical property, swelling property and permeability of highly compacted bentonite of main ore bed has been studied. The study results show that montmorillonite content of Gaomiaozi bentonite is relatively high, physical and chemical property, geotechnical property and impermeability are good. So Gaomiaozi bentonite deposit could be regarded as supply base of buffer/backfill material for HLW geological repository

Hydro-mechanical paths within unsaturated compacted soil framed through water retention surfaces

Directory of Open Access Journals (Sweden)

Pelizzari Benjamin

2016-01-01

Full Text Available Compaction is a key issue of modern earthworks... From sustainable development, a need arise of using materials for compaction under given conditions that would normally be avoid due to unpredictable pathologies. The application of compaction on fine grained soils, without a change of gravimetric water content, lead to very important modifications of the void ratio and hence suction. Therefore the hydro-mechanical behaviour of fine grained soil need to be rendered around three variables: suction, void ratio, saturation degree or water content. The barring capacity of the soil is assessed through Penetrometers (In-situ manual penetrometer, CBR in order to assess gains through compaction. The three states variables are then assessed for in situ and frame through water retention surfaces, realized from Proctor tests, in which compaction effect and path could be described.

Unsaturated hydraulic property of buffer material

International Nuclear Information System (INIS)

Suzuki, Hideaki; Fujita, Tomoo

1999-09-01

After emplacement of the engineered barrier system (EBS), it is expected that the near-field environment will be impacted by phenomena such as heat dissipation by conduction and other heat transfer mechanism, infiltration of groundwater from the surrounding rock into the EBS, generation of swelling pressure in the buffer due to water infiltration and the stress imposed by the overburden pressure. These phenomena are not all independent, but can be strongly influenced by, and coupled with, each other. Evaluating these coupled thermo-hydro-mechanical phenomena is important in order to clarify the initial transient behavior of the engineered barrier system within the near-field. This report describes the results on measurement of chemical potential, water diffusivity, and thermal water diffusivity of bentonite that is considered as a candidate material of buffer and on comparison between measurements and theoretical studies for these properties. The following results are identified; (l) The hysteresis of chemical potential in wet and dry conditions for compacted bentonite is not shown clearly. The chemical potential depends on temperature and amount of montmorillonite. When chemical potential of compacted bentonite is zero, the specimen is saturated. The van Genuchten model is applicable to the measured chemical potential of compacted bentonite. (2) The Darcy's law and Philip and de Vries model are applicable to the measured water diffusivity and thermal water diffusivity of compacted bentonite. (author)

Geochemical modelling of hydrogen gas migration in an unsaturated bentonite buffer

NARCIS (Netherlands)

Sedighi, M.; Thomas, H.R.; Al Masum, S.; Vardon, P.J.; Nicholson, D.; Chen, Q.

2014-01-01

This paper presents an investigation of the transport and fate of hydrogen gas through compacted bentonite buffer. Various geochemical reactions that may occur in the multiphase and multicomponent system of the unsaturated bentonite buffer are considered. A reactive gas transport model, developed

On the hydro-mechanical behaviour of MX80 bentonite-based materials

Directory of Open Access Journals (Sweden)

Yu-Jun Cui

2017-06-01

Full Text Available Bentonite-based materials have been considered in many countries as engineered barrier/backfilling materials in deep geological disposal of high-level radioactive waste. During the long period of waste storage, these materials will play an essential role in ensuring the integrity of the storage system that consists of the waste canisters, the engineered barrier/backfill, the retaining structures as well as the geological barrier. Thus, it is essential to well understand the hydro-mechanical behaviours of these bentonite-based materials. This review paper presents the recent advances of knowledge on MX80 bentonite-based materials, in terms of water retention properties, hydraulic behaviour and mechanical behaviour. Emphasis is put on the effect of technological voids and the role of the dry density of bentonite. The swelling anisotropy is also discussed based on the results from swelling tests with measurements of both axial and radial swelling pressures on a sand-bentonite mixture compacted at different densities. Microstructure observation was used to help the interpretation of macroscopic hydro-mechanical behaviour. Also, the evolution of soil microstructure thus the soil density over time is discussed based on the results from mock-up tests. This evolution is essential for understanding the long-term hydro-mechanical behaviour of the engineered barrier/backfill.

Activation of a Ca-bentonite as buffer material

Science.gov (United States)

Huang, Wei-Hsing; Chen, Wen-Chuan

2016-04-01

Swelling behavior is an important criterion in achieving the low-permeability sealing function of buffer material. A potential buffer material may be used for radioactive waste repository in Taiwan is a locally available clayey material known as Zhisin clay, which has been identified as a Ca-bentonite. Due to its Ca-based origin, Zhisin was found to exhibit swelling capacity much lower than that of Na-bentonite. To enhance the swelling potential of Zhisin clay, a cation exchange process by addition of Na2CO3 powder was introduced in this paper. The addition of Na2CO3 reagent to Zhisin clay, in a liquid phase, caused the precipitation of CaCO3 and thereby induced a replacement of Ca2+ ions by Na+ ions on the surface of bentonite. Characterization test conducted on Zhisin clay includes chemical analysis, cation exchange capacity, X-ray diffraction, and thermogravimetry (TG). Free-swelling test apparatus was developed according to International Society of Rock Mechanics recommendations. A series of free-swelling tests were conducted on untreated and activated specimens to characterize the effect of activation on the swelling capacity of Zhisin clay. Efforts were made to determine an optimum dosage for the activation, and to evaluate the aging effect. Also, the activated material was evaluated for its stability in various hydrothermal conditions for potential applications as buffer material in a repository. Experimental results show that Na2CO3-activated Zhisin clay is superior in swelling potential to untreated Zhisin clay. Also, there exists an optimum amount of activator in terms of improvements in the swelling capacity. A distinct time-swell relationship was discovered for activated Zhisin clay. The corresponding mechanism refers to exchange of cations and breakdown of quasi-crystal, which results in ion exchange hysteresis of Ca-bentonite. Due to the ion exchange hysteresis, activated bentonite shows a post-rise time-swell relationship different than the sigmoid

Removal of uranium from water media by bentonite and zeolite

International Nuclear Information System (INIS)

Viglasova, E.; Krajnak, A.; Galambos, M.; Rosskopfova, O.

2014-01-01

The removal and recovery of uranium from contaminated surface, environment and ground water, as result of nuclear industries, has attracted more and more attentions. Several methods are available for removing of uranium, but adsorption among the others, is the most attractive. In case of management of radioactive waste, the adsorption of radionuclides plays significant role. Among the natural sorbents applied to the adsorption of uranium zeolites and bentonites offer a number of advantages. The main aims of this work are investigations of adsorption properties of Greek zeolite Metaxades and Greek bentonite Kimolos during adsorption of uranium from water solutions, comparison of their adsorption characteristics, fitting with isotherms (Freundlich, Langmuir and DR isotherm) and its behaviour during kinetics process influenced by temperature. (authors)

Immobilization of spent Bentonite by using cement matrix

International Nuclear Information System (INIS)

Isman MT; Endro-Kismolo

1996-01-01

Investigation of spent bentonite immobilization by using cement was done. The purpose of the investigation was to know the performance of cement in binding bentonite waste. The investigation was done by adding cement, water, and bentonite waste into a container and string until the mixture became homogenous. The mixture was put into a polyethylene tube (3.5 cm in diameter and 4 cm high) and it was cured up to 28 days. The specific weight of the monolith block was then calculated, and the compressive strength and the leaching rate in ground water and sea water was tested. The mass ratio of water to cement was 0.4. The variable investigated was the mass ratio of bentonite to cement. The immobilized bentonite waste was natural bentonite waste and activated bentonite waste. The result of the investigation showed that cement was good for binding bentonite waste. The maximum binding mass ratio of bentonite to cement was 0.4. In this condition the specific weight of the monolith block was 2.177 gram/cm 3 , its compressive strength was 22.6 N/mm 2 , and the leaching rate for 90 days in ground water and sea water was 5.7 x 10 -4 gram cm -2 day -1

Physical and hydraulic characteristics of bentonite-amended soil from Area 5, Nevada Test Site

International Nuclear Information System (INIS)

Albright, W.

1995-08-01

Radioactive waste requires significant isolation from the biosphere. Shallow land burial using low-permeability covers are often used to prevent the release of impounded material. This report details the characterization of a soil mixture intended for use as the low-permeability component of a radioactive waste disposal site. The addition of 6.5 percent bentonite to the sandy soils of the site reduced the value of saturated hydraulic conductivity (K s ) by more than two orders of magnitude to 7.6 x 10- 8 cm/sec. Characterization of the soil mixture included measurements of grain density, grain size distribution, compaction, porosity, dry bulk density, shear strength, desiccation shrinkage, K s , vapor conductivity, air permeability, the characteristic water retention function, and unsaturated hydraulic conductivity by both experimental and numerical estimation methods. The ability of the soil layer to limit infiltration in a simulated application was estimated in a one-dimensional model of a landfill cover

Review of a report on diffusion and sorption properties of radionuclides in compacted bentonite

Energy Technology Data Exchange (ETDEWEB)

Ochs, M. [BMG Engineering Ltd (United Kingdom)

1997-10-01

The present report encompasses the discussion of data uncertainties of the revised report prepared by Yu and Neretnieks (1977). Uncertainties of the reference system, in particular the porewater chemistry relevant for compacted bentonite, are illustrated with the help of a thermodynamic model. Uncertainties regarding the chemistry of the critical elements considered by Yu and Neretnieks (1977) are reviewed, and ranges of validity with regard to the extrapolation of sorption and diffusion data are indicated, where appropriate. The data selection made by Yu and Neretnieks (1977) is reviewed for each critical element, and uncertainties associated with these data are discussed. Possibilities on how to handle such uncertainties are discussed, and very briefly, the use of thermodynamic models for sensitivity analyses is illustrated using Cs. 33 refs.

Exchangeability of bentonite buffer and backfill materials

Energy Technology Data Exchange (ETDEWEB)

Savage, D. [Savage Earth Associates Ltd, Bournemouth (United Kingdom); Arthur, R. [Intera Inc, Ottawa, ON, (Canada); Luukkonen, A.

2012-08-15

Clay-based buffer and tunnel backfill materials are important barriers in the KBS-3 repository concept for final disposal of spent nuclear fuel in Finland. One issue that is relevant to material properties is the degree to which different bentonite compositions can be regarded as interchangeable. In Posiva's current repository design, the reference bentonite composition is MX-80, a sodium montmorillonite dominated clay. Posiva would like to be able to use bentonite with Ca-montmorillonite as the dominant clay mineral. However, at this stage, it is not clear what supporting data need to be acquired/defined to be able to place the state of knowledge of Ca-bentonite at the same level as that of Na-bentonite. In this report, the concept of bentonite exchangeability has been evaluated through consideration of how bentonite behaviour may be affected in six key performance-relevant properties, namely (1) mineralogical composition and availability of materials, (2) hydraulic conductivity, (3) mechanical and rheological properties, (4) long-term alteration, (5) colloidal properties, and (6) swelling pressure. The report evaluates implications for both buffer and backfill. Summary conclusions are drawn from these sections to suggest how bentonite exchangeability may be addressed in regulatory assessments of engineered barrier design for a future geological repository for spent fuel in Finland. Some important conclusions are: (a) There are some fundamental differences between Ca- and Na-bentonites such as colloidal behaviour, pore structure and long-term alteration that could affect the exchangeability of these materials as buffer or backfill materials and which should be further evaluated; (b) Additional experimental data are desirable for some issues such as long-term alteration, hydraulic properties and swelling behaviour, (c) The minor mineral content of bentonites is very variable, both between different bentonites and within the same bentonite type, it is not clear

Bentonite as a waste isolation pilot plant shaft sealing material

International Nuclear Information System (INIS)

Daemen, J.; Ran, Chongwei

1996-12-01

Current designs of the shaft sealing system for the Waste Isolation Pilot Plant (WIPP) propose using bentonite as a primary sealing component. The shaft sealing designs anticipate that compacted bentonite sealing components can perform through the 10,000-year regulatory period and beyond. To evaluate the acceptability of bentonite as a sealing material for the WIPP, this report identifies references that deal with the properties and characteristics of bentonite that may affect its behavior in the WIPP environment. This report reviews published studies that discuss using bentonite as sealing material for nuclear waste disposal, environmental restoration, toxic and chemical waste disposal, landfill liners, and applications in the petroleum industry. This report identifies the physical and chemical properties, stability and seal construction technologies of bentonite seals in shafts, especially in a saline brine environment. This report focuses on permeability, swelling pressure, strength, stiffness, longevity, and densification properties of bentonites

Bentonite as a waste isolation pilot plant shaft sealing material

Energy Technology Data Exchange (ETDEWEB)

Daemen, J.; Ran, Chongwei [Univ. of Nevada, Reno, NV (United States)

1996-12-01

Current designs of the shaft sealing system for the Waste Isolation Pilot Plant (WIPP) propose using bentonite as a primary sealing component. The shaft sealing designs anticipate that compacted bentonite sealing components can perform through the 10,000-year regulatory period and beyond. To evaluate the acceptability of bentonite as a sealing material for the WIPP, this report identifies references that deal with the properties and characteristics of bentonite that may affect its behavior in the WIPP environment. This report reviews published studies that discuss using bentonite as sealing material for nuclear waste disposal, environmental restoration, toxic and chemical waste disposal, landfill liners, and applications in the petroleum industry. This report identifies the physical and chemical properties, stability and seal construction technologies of bentonite seals in shafts, especially in a saline brine environment. This report focuses on permeability, swelling pressure, strength, stiffness, longevity, and densification properties of bentonites.

Eutrophication management in surface waters using lanthanum modified bentonite

DEFF Research Database (Denmark)

Copetti, Diego; Finsterle, Karin; Marziali, Laura

2016-01-01

This paper reviews the scientific knowledge on the use of a lanthanum modified bentonite (LMB) to manage eutrophication in surface water. The LMB has been applied in around 200 environments worldwide and it has undergone extensive testing at laboratory, mesocosm, and whole lake scales. The availa......This paper reviews the scientific knowledge on the use of a lanthanum modified bentonite (LMB) to manage eutrophication in surface water. The LMB has been applied in around 200 environments worldwide and it has undergone extensive testing at laboratory, mesocosm, and whole lake scales....... The available data underline a high efficiency for phosphorus binding. This efficiency can be limited by the presence of humic substances and competing oxyanions. Lanthanum concentrations detected during a LMB application are generally below acute toxicological threshold of different organisms, except in low...... alkalinity waters. To date there are no indications for long-term negative effects on LMB treated ecosystems, but issues related to La accumulation, increase of suspended solids and drastic resources depletion still need to be explored, in particular for sediment dwelling organisms. Application of LMB...

CRIEPI's research results (2006-2011) and clarified future issues on alteration behavior of bentonite barrier by alkaline solutions

International Nuclear Information System (INIS)

Yokoyama, Shingo; Nakamura, Kunihiko; Tanaka, Yukihisa; Hironaga, Michihiko

2013-01-01

In radioactive waste disposal facilities, bentonite barrier would be altered by alkaline solutions which arise by leaching of cementitious materials. Consequently suitable properties of the bentonite barrier would be degraded for a long time period. In CRIEPI, the investigation on the alteration of the bentonite under alkaline conditions was started in 2006, and several CRIEPI reports have been published. Specifically, we have investigated the kinetics of montmorillonite dissolution, the mineralogical alteration of compacted bentonite (with high- and low-dry density) and the change of permeability of the compacted bentonite (with high- and low-dry density) during alteration under the alkaline conditions. Furthermore, stability of saponite, which has similar physical properties to the bentonite, under the alkaline conditions was also examined. In this report, we show the outline of those research results, and lay out the clarified future issues extracted from our results. Ten clarified future issues were divided three categories as follows: 1) the estimation of the alteration behavior of the bentonite by alkaline solutions, 2) the elucidation of the mechanism of physical properties (e.g., permeability, swelling properties and mechanistic properties) change of the compacted bentonites during alteration, and 3) the development of the model building and simulation technology concerning the change in physical properties during alteration under alkaline conditions. (author)

Study on chemical buffering property of GMZ sodium bentonite under atmospheric condition

International Nuclear Information System (INIS)

Wen Zhijian

2012-01-01

At present, the deep geological disposal is regarded as the most reasonable and effective way to safely disposal the high-level radioactive wastes in the world. The conceptual model of HLW geological disposal in China is based on a multi-barrier system that combines an isolating geological environment with an engineered barrier system. The buffer is one of the engineered barrier materials and GMZ Na-bentonite is selected as the basic material. One of the most important functions related to buffer is the chemical buffering, which means buffering the changes in pore water chemistry. This paper presents the experiments of GMZ-1 Na-bentonite reacted with distilled water under atmospheric condition. The batch tests and results discussion are reported. Na and Mg in batch test solution are co-provided by interlayer cations of montmorillonite and solids dissolution, K and Ca are provided by dissolution of solids. The result is a pre-requisite for predicting near-field nuclide migration and assesses the long-term stability of the engineered barrier materials. (author)

Cation Exchange Efficiency Of Modified Bentonite Using In-Situ GAMMA Radiation Polymerization Of Acrylic Acid Or Acrylamide

International Nuclear Information System (INIS)

ISMAIL, S.A.; FALAZI, B.

2009-01-01

Modified bentonites as cation exchangers were prepared by treating raw bentonite with 3N NaOH at 95 0 C followed by in-situ polymerization using gamma irradiation as well as hydrogen peroxide initiation of acrylic acid or acrylamide in the matrix.Water swelling and acid capacity were determined and cation exchange capacity for Cu 2+ , Ni 2+ and Co 2+ was evaluated. It has been found that catiexchange capacity of treated bentonite was increased as result of formed polyacrylic acid and polyacrylamide in the matrix. In case of acrylic acid, the maximum cation exchange capacities of 3.5, 3.1 and 2.5 mg equivalent/g were determined for Cu 2+ , Ni 2+ and Co 2+ , respectively, and for acrylamide, the corresponding capacities were 2.9, 2.8 and 2.6 mg equivalent/g, respectively. Water swelling was found to be associated with holding large amounts of water, for instance, 49 g of water was sorbed per one gram of the sodium salt form of polyacrylic acid in bentonite matrix, in other words the degree of swelling in water achieved 4500%.

Mobility of U, Np, Pu, Am and Cm from spent nuclear fuel into bentonite clay

International Nuclear Information System (INIS)

Ramebaeck, H.; Skaalberg, M.; Eklund, U.B.; Kjellberg, L.; Werme, L.

1998-01-01

The mobility of uranium, neptunium, plutonium, americium and curium from spent nuclear fuel (UO 2 ) into compacted bentonite was studied. Pieces of spent BWR UO 2 fuel was embedded in a compacted bentonite clay/low saline synthetic groundwater system. After a contact time of six years the bentonite was sliced into 0.1 mm thick slices and analysed for its content of actinides. Radiometric as well as inductively coupled plasma mass spectrometry (ICP-MS) were used for the analysis. The influence on the mobility by the addition of metallic iron, metallic copper and vivianite (Fe(II)-mineral) to the bentonite clay was investigated. The results show a low mobility of actinides in bentonite clay. Except for uranium the mobility of the other actinides could, after six years of diffusion time, only be detected less than 1 mm from the spent fuel. (orig.)

Evaluation of bentonite alteration due to interactions with iron. Sensitivity analyses to identify the important factors for the bentonite alteration

International Nuclear Information System (INIS)

Sasamoto, Hiroshi; Wilson, James; Sato, Tsutomu

2013-01-01

Performance assessment of geological disposal systems for high-level radioactive waste requires a consideration of long-term systems behaviour. It is possible that the alteration of swelling clay present in bentonite buffers might have an impact on buffer functions. In the present study, iron (as a candidate overpack material)-bentonite (I-B) interactions were evaluated as the main buffer alteration scenario. Existing knowledge on alteration of bentonite during I-B interactions was first reviewed, then the evaluation methodology was developed considering modeling techniques previously used overseas. A conceptual model for smectite alteration during I-B interactions was produced. The following reactions and processes were selected: 1) release of Fe 2+ due to overpack corrosion; 2) diffusion of Fe 2+ in compacted bentonite; 3) sorption of Fe 2+ on smectite edge and ion exchange in interlayers; 4) dissolution of primary phases and formation of alteration products. Sensitivity analyses were performed to identify the most important factors for the alteration of bentonite by I-B interactions. (author)

A study on the swelling characteristics of a potential buffer material : Effect of ionic strength and temperature on the swelling pressure

Energy Technology Data Exchange (ETDEWEB)

Lee, Jae Owan; Cho, Won Jin; Chun, Kwan Sik [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-04-01

This study is intended to investigate the effect of ionic strength and temperature on the swelling pressure of bentonite. The dry density for compacted bentonite was adjusted between 1.4 Mg/m{sup 3} - 1.8 Mg/m{sup 3}. The effect of temperature was tested at 20 deg C, 40 deg C, 60 deg C, 80 deg C, and the effect of ionic strength with distilled water, synthetic ground water, and 0.01 M - 0.1 M NaCl solution. The swelling pressure decreased with increasing ionic strength, and its dependency got lower at high dry density. Temperature had negligible effect on the swelling pressure of compacted bentonite, which could be explained by the change in hydration pressure, osmotic pressure, and pore water pressure in accordance with temperature. The swelling pressure of compacted bentonite with low dry density was dominated mainly by osmosis. However, hydration was thought to become important at higher dry density, compared with the osmosis. 32 refs., 11 figs., 4 tabs. (Author)

Numerical simulation of alteration of sodium bentonite by diffusion of ionic groundwater components

International Nuclear Information System (INIS)

Jacobsen, J.S.; Carnahan, C.L.

1987-12-01

Experiments measuring the movement of trace amounts of radionuclides through compacted bentonite have typically used unaltered bentonite. Models based on experiments such as these may not lead to accurate predictions of the migration through altered or partially altered bentonite of radionuclides that undergo ion exchange. To address this problem, we have modified an existing transport code to include ion exchange and aqueous complexation reactions. The code is thus able to simulate the diffusion of major ionic groundwater components through bentonite and reactions between the bentonite and groundwater. Numerical simulations have been made to investigate the conversion of sodium bentonite to calcium bentonite for a reference groundwater characteristic of deep granitic formations. 20 refs., 2 figs., 2 tabs

Investigation of the selected properties of dusts from the reclamation of spent sands with bentonite

Directory of Open Access Journals (Sweden)

J. Kamińska

2011-10-01

Full Text Available The investigation results of the selected properties of dusts generated during the mechanical reclamation of spent sands with bentonite as well as dusts from the dedusting system of sand processing plant are presented in the hereby paper. Investigations were performed with regard to determination conditions allowing to pelletise dusts in the bowl granulator. The verified methods of testing physical and chemical dust properties such as: specific density, bulk density of loosely put materials and apparent density of compacted materials together with their corresponding porosity, ignition losses and pH values, were applied. Granular composition of dusts generated during abrasion of spent binding materials in mechanical dry reclamation processes of spent sands with bentonite and coal dusts were performed by the laser diffraction analysis, allowing to broaden the measuring range of particle diameters. The optimal wetting agent content (in this case water at which the dust-water mixture obtains the best strength properties – after compacting by means of the standard moulder’s rammer – was determined.

Mass Transfer and Porous Media (MTPM)

Energy Technology Data Exchange (ETDEWEB)

Rotenberg, B.; Marry, V.; Malikova, N.; Vuilleumier, R.; Giffaut, E.; Turq, P.; Robinet, J.C.; Diaz, N.; Sardini, P.; Goutelard, F.; Menut, D.; Parneix, J.C.; Sammartino, S.; Pret, D.; Coelho, D.; Jougnot, D.; Revil, A.; Boulin, P.F.; Angulo-Jaramillo, R.; Daian, J.F.; Talandier, J.; Berne, P.; Cochepin, B.; Trotignon, L.; Bildstein, O.; Steefel, C.; Lagneau, V.; Van der Lee, J.; Birchall, D.J.; Harrington, J.F.; Noy, D.J.; Sellin, P.; Bildstein, O.; Piault, E.; Trotignon, L.; Montarnal, P.; Deville, E.; Genty, A.; Le Potier, C.; Imbert, C.; Semete, P.; Desgree, P.; Fevrier, B.; Courtois, A.; Touze, G.; Sboui, A.; Roberts, J.E.; Jaffre, J.; Glaus, M.A.; Rosse, R.; Van Loon, L.R.; Matray, J.M.; Parneix, J.C.; Tinseau, E.; Pret, D.; Mayor, J.C.; Ohkubo, T.; Kikuchi, H.; Yamaguchi, M.; Alonso, U.; Missana, T.; Garcia-Gutierrez, M.; Patelli, A.; Siitari-Kauppi, M.; Leskinen, A.; Rigato, V.; Samper, J.; Dewonck, S.; Zheng, L.; Yang, Q.; Naves, A.; Dai, Z.; Samper, J.; Wolfsberg, A.; Levitt, D.; Cormenzana, J.L.; Missana, T.; Mingarro, M.; Schampera, B.; Dultz, S.; Riebe, B.; Samper, J.; Yang, Q.; Genty, A.; Perraud, D.; Poller, A.; Mayer, G.; Croise, J.; Marschall, P.; Krooss, B.; Matray, J.M.; Tanaka, T.; Vogel, P.; Lavanchy, J.M.; Enssle, C.P.; Cruchaudet, M.; Dewonck, S.; Descostes, M.; Blin, V.; Radwan, J.; Poinssot, C.; Mibus, J.; Sachs, S.; Devol-Brown, I.; Motellier, S.; Tinseau, E.; Thoby, D.; Marsal, F.; DeWindt, L.; Tinseau, E.; Pellegrini, D.; Bauer, A.; Fiehn, B.; Marquardt, Ch.; Romer, J.; Gortzen, A.; Kienzler, B

2007-07-01

-montmorillonites: in-situ diffusion experiments using ATR-FTIR spectroscopy; the unsaturated flow around high-level long-lived radioactive waste repository drift seal with Alliances platform; the numerical Interpretation of gas transport experiments on water-saturated samples of Opalinus clay; the Callovo-Oxfordian Formation at the Meuse/Haute-Marne URL: consistency between measured hydraulic conductivity and the drainage effect of the experimental drifts; In-situ diffusion tests performed In the Callovo-Oxfordian mud-stone in the Meuse/Haute-Marne URL: Experimental data and numerical interpretations; the influence of humic colloids on the migration of U(VI) in compacted clay; the diffusion of tritiated water and ions through the Tournemire argillite (France) in presence of alkaline fluids; the reactive transport modelling of in-situ cement/clay interactions on Tournemire argillite; the results on Pu diffusion experiments in the Opalinus Clay; the diffusion of H{sub 2}O and electro-osmosis in water-saturated compacted Na-montmorillonite using H{sub 2}{sup 18}O as a tracer; a deterministic and probabilistic compartmental modelling of nitrate reduction and transfer in a bituminous waste cell and the adjacent host rock; an experimental study on gas permeability of the Callovo-Oxfordian argillite of Meuse/Haute-Marne URL; gas intrusion in saturated bentonite a thermodynamic approach; evaluating the application of Archie law for argillaceous rocks; the comparison between radial diffusion and leaching for determining chloride and sulphate in Tournemire argillite pore water; a cross method of a nano-scale model and macroscopic data to estimate anion effective diffusion coefficient in argillite; the numerical modelling of coupled mechanics and gas transfer; the vertical distribution of HCO{sub 3}{sup -} transport parameters in Boom clay in the Mol-1 borehole (Mol, Belgium); diffusion experiments in Callovo- Oxfordian clay from the Meuse/Haute-Marne URL France: 2 model results; an experimental

One-dimensional self-sealing ability of bentonites in artificial seawater

International Nuclear Information System (INIS)

Komine, Hideo; Yasuhara, Kazuya; Murakami, Satoshi

2009-01-01

A high-level radioactive waste disposal facility might be built in a coastal area in Japan from the viewpoint of feasible transportation of waste. Therefore, it is important to investigate the effects of seawater on a bentonite-based buffer. This study investigated the influence of seawater on self-sealing ability of three common sodium-types of bentonite by the laboratory experiment and chemical analysis. From the results of laboratory experiment, suitable specifications were defined for a bentonite-based buffer that can withstand the effects of seawater. Furthermore, mechanism on filtration of seawater components in highly compacted bentonite was discussed by the results of chemical analysis. (author)

Long term mineralogical properties of bentonite/quartz buffer substance

International Nuclear Information System (INIS)

Jacobsson, A.; Pusch, R.

1978-06-01

This report shows results from investigations concerning properties in bentonitebased buffersubstances which are suggested to be used when high level radioactive wastes from nuclear powerplants are to be stored finally. Recommended material characteristica of the bentonite to be used are summerized. In an attempt to find geological evidence for bentonite to loose its desireable properties there were no such findings at the temperatures, groundwater situations and pressures which are to be expected at the actual depositing depth (500 m) for a considerable period of time. Concerning biological activity and then specially the mobility and activity of bacteria the conclusion is that there will be little or no influence from them either there is bentonite-sand or compacted pure bentonite in the buffer mass

Hydrothermal alkaline stability of bentonite barrier by concrete interstitial wastes

International Nuclear Information System (INIS)

Leguey Jimenez, S.; Cuevas Rodriguez, J.; Ramirez Martin, S.; Vigil de la villa Mencia, R.; Martin Barca, M.

2002-01-01

At present, the main source of High Level radioactive Waste (HLW) is the electrical energy production during all the steps of developing. In almost all the countries with nuclear programs, the option for the final management of HLW is the Deep Geological Repository (DGR) based on the concept of multi barrier. According to this concept, the waste is isolated from biosphere by the interposition of confinement barriers. Two of the engineering barriers in the Spanish design of DGR in granitic rock are compacted bentonite and concrete. The bentonite barrier is the backfilling and sealing material for the repository gallery, because of its mechanical and physico-chemical properties. The main qualities of concrete as a component of a multi barrier system are its low permeability, mechanical resistance and chemical properties. With regard to chemical composition of concrete, the alkaline nature of cement pore water lowers the solubility of many radioactive elements. However, structural transformation in smectite, dissolution or precipitation of minerals and, consequently, changes in the bentonite properties could occurs in the alkaline conditions generated by the cement degradation. The main objective of the present work is to evaluate the effect of concrete in the stability of Spanish reference bentonite (La Serrata of Nijar, Almeria, Spain) in conditions similar to those estimated in a DGR in granitic rock. Because of the main role of bentonite barrier in the global performance of the repository, the present study is essential to guarantee its security. (Author)

Use of Bentonite in residual waters of tanneries for the removal of Cr(III)

International Nuclear Information System (INIS)

Echavarria Isaza, Adriana; Moreno Casaf, Monica; Ramirez Ochoa, Claudia; Tamayo Martinez, Claudia; Saldarriaga Molina, Carlos

1998-01-01

An efficient procedure is reported for Cr(III) removal from tannery waste waters by means of natural and chemically treated bentonites. The best result was obtained using 20 mL of effluent with 7.5 grams of Bentonite. With this quantity it was removed the total amount of chromium III present in the sample

Concrete/Febex Bentonite Interaction: Results On Short-Term Column Experiments

International Nuclear Information System (INIS)

Escribano, A.; Turrero, M.J.; Torres, E.; Martin, P.L.

2008-01-01

Interaction between the alkaline pore fluids from the concrete engineered barriers and the bentonite at the repository conditions may generate products that can diffuse through the porous structure of the bentonite affecting their properties. A comprehensive study based on series of short term experiments is being performed to provide experimental evidences on the physical, chemical and mineralogical changes during the concrete-compacted bentonite interaction. Samples were analyzed by XRD, SEM-EDS and FTIR. Measurements of swelling capacity, specific surface area and chemical analysis for cation exchange capacity and soluble salts analyses were also performed. (authors)

Concrete/Febex Bentonite Interaction: Results On Short-Term Column Experiments

Energy Technology Data Exchange (ETDEWEB)

Escribano, A.; Turrero, M.J.; Torres, E.; Martin, P.L. [CIEMAT, Environmental Department, Avda. Complutense, 22, 28040 Madrid (Spain)

2008-07-01

Interaction between the alkaline pore fluids from the concrete engineered barriers and the bentonite at the repository conditions may generate products that can diffuse through the porous structure of the bentonite affecting their properties. A comprehensive study based on series of short term experiments is being performed to provide experimental evidences on the physical, chemical and mineralogical changes during the concrete-compacted bentonite interaction. Samples were analyzed by XRD, SEM-EDS and FTIR. Measurements of swelling capacity, specific surface area and chemical analysis for cation exchange capacity and soluble salts analyses were also performed. (authors)

Placement of pre-compacted and in situ compacted dense backfill materials in shaft seals

International Nuclear Information System (INIS)

Martino, J.; Dixon, D.; Kim, C.S.

2010-01-01

greatly reduced. The concrete provides confinement for the swelling clay. Two approaches were taken for the central clay unit in each seal. The main shaft uses compacted in situ clay-based material with 40% dry mass Wyoming sodium bentonite (200 mesh gradation), and 60% uniform gradation, water washed sand (< 2% of - 200 mesh size), with a target dry density of 1.80 ± 0.05 Mg/m 3 . The ventilation shaft uses pre-compacted clay blocks composed of 70% Kunigel V1 bentonite and 30% uniform gradation, water washed sand. These blocks were originally prepared in 1998 for the Tunnel Sealing Experiment (TSX) and unused materials were stored underground under plastic sheets. The blocks were designed to be hand placed and are approximately 35 cm x 10 cm x 18 cm in size which is convenient for use in construction of the ventilation shaft seal. In situ compaction required pre-blending of the clay-based material in order to achieve a clay component that is homogeneous with respect to density and initial degree of saturation. Because of the volume involved and in order to test a technique that is both time and cost efficient regarding material preparation, a conventional concrete dry batching truck was utilized. An auger on the truck blended the raw materials, with a water tank supplying the required water. The resulting material was bagged and stored for use once it was quality checked. Clay was delivered to the seal location in the main shaft once the lowermost concrete portion of the seal was cured for 28 days. The bagged clay was transferred to a shaft clam-shell bucket and transported to the seal location and then dumped. The clay material was manually spread to an initial ∼20 cm thickness for compaction and once compaction was completed each lift was approximately 10 cm in thickness. The clay volume in the shaft is approximately 117 m 3 (6-m-thick). Compaction was accomplished by use of two relatively small, hand-operated impact compactors. Along the perimeter of the shaft (and

Engineering Properties of Bentonite Stabilized with Lime and Phosphogypsum

Directory of Open Access Journals (Sweden)

Kumar Sujeet

2014-12-01

Full Text Available Engineering properties such as compaction, unconfined compressive strength, consistency limits, percentage swell, free swell index, the California bearing ratio and the consolidation of bentonite stabilized with lime and phosphogypsum are presented in this paper. The content of the lime and phosphogypsum varied from 0 to 10 %. The results reveal that the dry unit weight and optimum moisture content of bentonite + 8 % lime increased with the addition of 8 % phosphogypsum. The percentage of swell increased and the free swell index decreased with the addition of 8 % phosphogypsum to the bentonite + 8 % lime mix. The unconfined compressive strength of the bentonite + 8 % lime increased with the addition of 8 % phosphogypsum as well as an increase in the curing period up to 14 days. The liquid limit and plastic limit of the bentonite + 8 % lime increased, whereas the plasticity index remained constant with the addition of 8 % phosphogypsum. The California bearing ratio, modulus of subgrade reaction, and secant modulus increased for the bentonite stabilized with lime and phosphogypsum. The coefficient of the consolidation of the bentonite increased with the addition of 8 % lime and no change with the addition of 8 % phosphogypsum.

Investigations on uranium sorption on bentonite and montmorillonite, respectively, and uranium in environmental samples; Untersuchungen zur Uransorption an Bentonit bzw. Montmorillonit sowie von Uran in Umweltproben

Energy Technology Data Exchange (ETDEWEB)

Azeroual, Mohamed

2010-09-22

The geotechnical barrier is an important component of a geological repository and consists of compacted bentonite surrounding radioactive waste containers. Its most important functions are, to retard the radionuclide migration into the biosphere and to prevent groundwater contact with containers. lt is therefore of central importance to investigate the bentonite material on its capacity to sorb radionuclides under near-natural chemical and physical conditions. The purpose of this work was to study the adsorption of uranium(VI) on bentonit and on montmorillonite-standards at high uranium concentrations. Thereby, a special account was given to the calcium-uranyl-carbonate complexation, which leads to the formation of very stable and mobile uncharged Ca{sub 2}UO{sub 2}(CO{sub 3}){sub 3} complex. Results of batch experiments showed that the dicalcium-uranyl-tricarbonate complexation lowers the uranium(VI) sorption on natural clay (bentonite) by a factor of up to 3. After 21 days of contact time, about 40 % and 20 % of the initial uranium(VI)concentration were sorbed on Na-bentonite and ea-bentonite, respectively, from a solution with Ca{sub 2}UO{sub 2}(CO{sub 3}){sub 3} dominating the uranium(VI) speciation. On the contrary, about 55 % of the initial uranium(VI)-concentration were sorbed on thes clays from the solution, in which (UO{sub 2}){sub 2}CO{sub 3}(OH){sub 3}{sup -} complex dominated the uranium(VI) speciation. Thus uranium(VI) sorption is more strongly influenced by the solution composition than by bentonite type. Na-bentonite should be used instead of ea-bentonite as a geotechnical barrier, since calcium-uranyl-carbonate complexation may be a realistic scenario. Further SEM-EDX and HREM-EDX studies showed that uranium(VI) sorption occurred predominantly on montmorillonite, which is the main component of bentonite. Uranium(VI) sorption on bentonite's accessory Minerals (pyrite, calcite, mica, and feldspar) was not observed. Investigation of uranium

Erosion of bentonite by flow and colloid diffusion

International Nuclear Information System (INIS)

Moreno, Luis; Liu, Longcheng; Neretnieks, Ivars

2010-01-01

water velocity for the rectangular geometry. For the cylindrical geometry, the dependence is somewhat lower (exponent about 0.4) since the length of the gel/water interface decreases with increasing water flow rate. The penetration depth of the gel/water interface decreases with increasing water flow rate. For water velocity of the order of a metre per year the gel may penetrate several metres into the fracture at steady state. The simulations were made with only sodium as counter-ion. Most simulations had sodium concentrations below the critical coagulation concentration, CCC. In the compacted bentonite at the fracture mouth it was 10 mM and 0.1 mM in the approaching water. At these concentrations the gel is expansive and can turn into a sol releasing colloidal particles. The low ion concentration has a strong impact on the fluid viscosity, which increases with decreasing ionic strength. At the same time, however the repulsion forces between the smectite particles increase causing a quicker expansion and sol formation. Simulations with higher sodium concentrations in the seeping water had a marginal influence on the erosion rate. For the highest water flow rates the smectite loss could be up to 0.3 kg per year for one canister. This is more than one order of magnitude more than what would result by smectite particle diffusion alone if gel flow was neglected and account was only taken of particle diffusion out into the seeping water. (authors)

In-situ interferometric measurements of compacted smectite under hyper-alkaline condition - 59124

International Nuclear Information System (INIS)

Satoh, Hisao; Kurosawa, Susumu; Ishii, Tomoko; Owada, Hitoshi

2012-01-01

Document available in abstract form only. Full text of publication follows: Alteration of bentonite buffer at the repository for radioactive waste is an unavoidable phenomenon. However, precise kinetic data is useful for evaluation of the endurance for long-term safety. Alkaline attack to bentonite by cement-leachates may enhance alteration of smectite into the other phase such as zeolite. Until recently, there are a number of detailed dissolution studies (e.g., Cama et al., 2000; Yokoyama et al., 2005; Rozalen et al., 2008) for suspended smectite, using high precision measurements by ICPMS and AFM analyses. In contrast, dissolution study of compacted smectite is very limited (e.g., Nakayama et al., 2003). In order to verify the previous data, the dissolution rate of compacted smectite with realistic density needs to be confirmed experimentally. We have, for the first time, applied in-situ vertical scanning interferometry (VSI) along with the auto-compaction cell for measuring dissolution rates of smectite compacted at 0.04-20.0 MPa and 70 deg. C in 0.3 M NaOH (pH 12.1). At less-compaction (0.04 MPa), Kunipia-P smectite initially showed a relatively fast dissolution of ∼2E-11 mol/m 2 /s which is comparable to the rate for suspended smectite under same pH-T condition. At high-compaction ( 2 /s, but at higher compaction (>5 MPa), smectite dissolution was enhanced again to ∼5E-13 mol/ m 2 /s

Adsorption of La(III) onto GMZ bentonite. Effect of contact time, bentonite content, pH value and ionic strength

International Nuclear Information System (INIS)

Yonggui Chen; Changsha University of Science and Technology, Changsha; Chunming Zhu; Weimin Ye; Yanhong Sun; Huiying Duan; Dongbei Wu

2012-01-01

Bentonite has been studied extensively because of its strong adsorption capacity. A local Na-bentonite named GMZ bentonite, collected from Gaomiaozi County (Inner Mongolia, China), was selected as the first choice of buffer/backfill material for the high-level radioactive waste repository in China. In this research, the adsorption of La (III) onto GMZ bentonite was performed as a function of contact time, pH, solid content and metal ion concentrations by using the batch experiments. The results indicate that the adsorption of La (III) on GMZ bentonite achieves equilibration quickly and the kinetic adsorption follows the pseudo-second-order model; the adsorption of La (III) on the adsorbent is strongly dependent on pH and solid content, the adsorption process follows Langmuir isotherm. The equilibrium batch experiment data demonstrate that GMZ bentonite is effective adsorbent for the removal of La (III) from aqueous solution with the maximum adsorption capacity of 26.8 mg g -1 under the given experimental conditions. (author)

LOT A2 Test, THC-modelling of bentonite buffer in a final repository of spent nuclear fuel

International Nuclear Information System (INIS)

Itaelae, A.; Olin, M.; Rasilainen, K.; Pulkkanen, V.M.

2010-01-01

Document available in extended abstract form only. The Finnish spent nuclear fuel disposal is planned to be based on the KBS-3V repository concept. Within this concept, the role of the bentonite buffer is considered to be central. The aim of this study was to model the evolution of the buffer during the thermal phase (heat-generating period of spent fuel), when the bentonite is only partially saturated initially, and the surrounding rock matrix is assumed to be fully saturated. It is essential to study how temperature will affect saturation and also how both of these affect the chemistry of bentonite. In order to make the modeling more concrete, an example experimental case was considered: Long Term Test of Buffer Materials (LOT) A2-parcel test at the Aespoe Hard Rock Laboratory (HRL) in Sweden. In the A2-parcel the MX-80 bentonite was exposed to adverse (120-150 deg. C) temperature conditions and high temperature gradients. The test parcel diameter was smaller than in the actual KBS-3V deposition hole to speed up the saturation. The chemical behaviour of minerals causes their redistribution inside the bentonite. For example, according to the laboratory tests, gypsum dissolves and anhydrite precipitates near the heater-bentonite interface. Also, incoming groundwater affects the bentonite pore water and its properties. These changes may, in turn, influence the mechanical properties of the bentonite. A coupled Thermo-Hydro-Chemical (THC) model was applied, which means that all mechanical effects were ignored. The purpose of the model was first to achieve a satisfactory match between the model and experimental results, and, therefore, the time frame was limited to ten years (LOT A-2 parcel test lasted approximately 6 years). The system was simplified to 1-D in order to reduce the computational work, which can be very significant due to complex chemical calculations. The 1-D model results are reported in Itaelae (2009). The aim is to extend the calculations to 2-D

Coupled transport/reaction modelling with ion-exchange: Study of the long-term properties of bentonite buffer in a final repository

International Nuclear Information System (INIS)

Liu Jinsong; Neretnieks, I.

1997-05-01

Possible transformation of Na-montmorillonite to Ca-montmorillonite, by ion exchange, in the bentonite buffer in a final repository for spent nuclear fuel can lead to a drastic decrease in the swelling capacity and a significant increase in the permeability of the bentonite. The ion exchange mechanism has been studied, by using the coupled transport/reaction model. In most typical sites of the granite bedrock where there are no large fractures, groundwater flow is limited. The results of this study show that the ion-exchange process will be very slow in this case. Only a few percent of the total Na-montmorillonite is exchanged within 1 to 10 thousand years. When the groundwater flow in the bedrock is assumed to be unlimited, an upper bound of the conditions of the water flow, a sharp ion-exchange front can be formed and propagate within the bentonite buffer. When the groundwater is assumed to be the Aespoe water, with a high Ca concentration, the break-through time of the ion-exchange front can be a few thousand years. When the water is assumed to be Allard water with low Ca concentration, the break-through time can be as long as 10 5 to 10 6 years. When a canister has manufacturing defects, both the pyrite oxidation and the ion-exchange processes can occur simultaneously. A redox front and an ion-exchange front develop from both sides of the bentonite buffer. before the two fronts meet, they travel relatively independently in the bentonite. After they have met, they interact only marginally. Even if a large scale ion-exchange happens, the release of the dissolved uranium species from the bentonite to the rock can still be extremely small. The release is mainly controlled by the redox potential of pyrite oxidation

Colloid chemical aspects of the ''confined bentonite concept''

International Nuclear Information System (INIS)

Bell, J.C. Le

1978-03-01

Measurements of the amount of particles released from a bentonite gel by light scattering and visual inspection show that while particles are released in distilled water, the gel will be coagulated if in contact with ground water and consequently the release of particles is negligibly small. Studies of sedimentation volumes by ultracentrifugation also clearly indicate that the bentonite in contact with ground water under the repository pressure will form a completely stable coagulated gel. The swelling of confined bentonite was studied in an ''artificial crack'' of width 0.5 mm. The bentonite flowed readily into this crack and into the much narrower crack formed when the cell was broken. The swelling properties of the bentonite at the repository depth are discussed. It is argued that the gel, if sufficient volume is available, will swell spontaneously to a volume that is approximately 30 % larger than the initial one and then form a stable, coagulated gel containing 30-35 % water in equilibrium with the ground water. Investigations of the diffusion of colloidal matter (sodium lignosulphonate molecules of mean diameter 6 nm) and calcium ions into a dilute bentonite gel show that colloidal matter very probably will have a negligible rate of diffusion while the calcium ions diffuse rapidly. This implies that the initial bentonite gel which is partially in its sodium form will be completely exchanged to its calcium form when brought into contact with ground water which ensures that it will remain coagulated even in its swollen state

Physical and chemical properties for sandstone and bentonites

International Nuclear Information System (INIS)

Sato, Haruo

2004-01-01

Physical and chemical properties such as porosity, pore-size distribution, dry density, solid density, mineralogy and chemical composition, which are important parameters for the understanding and analysis of the diffusion phenomena of radionuclides and ions in bentonite and in the geosphere, were measured. The measurements were performed for sandstone, of which fundamental data and information are limited. For bentonite, 3 kinds of bentonites with different smectite contents (Kunigel-V1, Kunipia-F, MX80) were used. In the measurements of the physical and chemical properties of rock, the measurements of solid density by pychnometer, the measurements of porosity, dry density and solid density by water saturation method, the measurements of porosity, dry density, solid density, pore-size distribution and specific surface area of pores by Hg porosimetry, the identifications of constituent minerals by X-ray Diffractometry (XRD), the measurement of chemical composition by whole rock analysis, the observations of micropore structure by Laser Confocal Microscope (LCM), the measurements of water vaporization curves and the measurements of the homogeneity of the rock by penetration of KMnO 4 were performed. While, in the measurements of the physical and chemical properties for bentonite, water basis water content, water content, porosity, dry density, solid density and their distributions in samples were measured, and the degree of inhomogeneity was quantitatively evaluated by comparing with data and information reported up to date. The porosities of sandstone are 15.6±0.21% for water saturation method and 15.5±0.2% for Hg porosimetry, and similar values were obtained in both methods. The solid densities ranged 2.65-2.69 Mg/m 3 for 3 methods, and the average value was 2.668±0.012 Mg/m 3 . The average pore size was 88.8±0.5nm, and pore sizes ≤10μm shared 80% of total pore volume and pore sizes ≤1μm shared 40%. The specific surface area of the pores is 4.09±0.017 m

Activation of wine bentonite with gamma rays

International Nuclear Information System (INIS)

Goranov, N.; Antonov, M.

1997-01-01

The action of gamma rays on wine bentonite as well as influence of its adsorption and technologic qualities on the composition and stability of wines against protein darkening and precipitation has been studied. The experiments were carried out with wine bentonite produced in the firm Bentonite and irradiated with doses of 0.4, 0.6, 0.8 and 1.0 MR. White and red wines have been treated with irradiated bentonite under laboratory conditions at 1.0 g/dm 3 . All samples are treated at the same conditions. The flocculation rate of the sediment was determined visually. Samples have been taken 24 h later from the cleared wine layers. The following parameters have been determined: clarification, filtration rate, phenolic compounds, calcium, colour intensity, total extracted substances, etc. The volume of the sediment has been determined also. The control samples have been taken from the same unirradiated wines. The results showed better and faster clarification in on the third, the 20th and the 24th hours with using of gamma-irradiated at doses 0.8 and 1.0 MR. The sediment was the most compact and its volume - the smallest compared to the samples treated with bentonite irradiated with doses of 0.6 and 0.4 MR. This ensures a faster clarification and better filtration of treated wines. The bentonite activated with doses of 0.8 and 1.0 MR adsorbs the phenolic compounds and the complex protein-phenolic molecules better. In the same time it adsorbs less extracted substances compared to untreated bentonite and so preserves all organoleptic properties of wine. The irradiated bentonite adsorbs less the monomers of anthocyan compounds which ensures brighter natural colour of wine. The gamma-rays activation consolidates calcium in the crystal lattice of bentonite particles and in this way eliminates the formation of crystal precipitates

Survival of bacteria in nuclear waste buffer materials. The influence of nutrients, temperature and water activity

International Nuclear Information System (INIS)

Pedersen, K.; Motamedi, M.

1995-12-01

The concept of deep geological disposal of spent fuel is common to many national nuclear waste programs. Long-lived radioactive waste will be encapsulated in canisters made of corrosion resistant materials e.g. copper and buried several hundred meters below ground in a geological formation. Different types of compacted bentonite clay, or mixtures with sand, will be placed as a buffer around the waste canisters. A major concern for the performance of the canisters is that sulphate-reducing bacteria (SRB) may be present in the clay and induce corrosion by production of hydrogen sulphide. This report presents data on viable counts of SRB in the bedrock of Aespoe hard rock laboratory. A theoretical background on the concept water activity is given, together with basic information about SRB. Some results on microbial populations from a full scale buffer test in Canada is presented. These results suggested water activity to be a strong limiting factor for survival of bacteria in compacted bentonite. As a consequence, experiments were set up to investigate the effect from water activity on survival of SRB in bentonite. Here we show that survival of SRB in bentonite depends on the availability of water and that compacting a high quality bentonite to a density of 2.0 g/cm 3 , corresponding to a water activity (a w ) of 0.96, prevented SRB from surviving in the clay. 24 refs

Review of the properties and uses of bentonite as a buffer and backfill material

International Nuclear Information System (INIS)

Savage, D.; Lind, A.; Arthur, R.C.

1999-05-01

similar studies elsewhere and is therefore contentious and open to debate. There seems to be a general lack of integration of analogue studies with modelling and experimental work in terms of a model of the evolution of the chemistry of bentonite pore fluids with time (i.e. analogue evidence demonstrates the importance of mineral dissolution and precipitation, but this is not incorporated into the chemical modelling approach). Some rationalisation of approaches is required for a credible model of bentonite pore water evolution to be created. There is little apparent use of modelled bentonite pore water chemistry for the calculation of radionuclide solubility, sorption and speciation in PA (c.f. approaches used by Nagra, JNC, TVO). Although recent work in part redresses this imbalance, SKB is alone amongst disposal agencies in this approach. There is little published work by SKB on the interaction of bentonite with cement. There is now a growing literature elsewhere on this subject which does not seem to be reflected in studies carried out by SKB. Collaboration with other waste disposal authorities interested in this topic is recommended. It may be necessary to incorporate chemical processes into the current SKB conceptual model of gas transport in buffer and backfill materials. Dissolved or gaseous H 2 is generated by Fe corrosion under anaerobic conditions, and this gas may be reactive with several minerals in bentonite, including smectite. Although field tests carried out by SKB suggest that the emplacement of compacted bentonite will not be a problem from the perspective of buffer performance, borehole, shaft and vault sealing, there are apparent problems for block manufacture. The introduction of oil as a lubricant in block manufacture, for example may pose problems for long-term behaviour of the near-field due to the presence of these organic materials. Better manufacturing methods are therefore required

Review of the properties and uses of bentonite as a buffer and backfill material

Energy Technology Data Exchange (ETDEWEB)

Savage, D.; Lind, A. [QuantiSci Ltd., Melton Mowbray (United Kingdom); Arthur, R.C. [QuantiSci lnc., Denver, CO (United States)

1999-05-01

similar studies elsewhere and is therefore contentious and open to debate. There seems to be a general lack of integration of analogue studies with modelling and experimental work in terms of a model of the evolution of the chemistry of bentonite pore fluids with time (i.e. analogue evidence demonstrates the importance of mineral dissolution and precipitation, but this is not incorporated into the chemical modelling approach). Some rationalisation of approaches is required for a credible model of bentonite pore water evolution to be created. There is little apparent use of modelled bentonite pore water chemistry for the calculation of radionuclide solubility, sorption and speciation in PA (c.f. approaches used by Nagra, JNC, TVO). Although recent work in part redresses this imbalance, SKB is alone amongst disposal agencies in this approach. There is little published work by SKB on the interaction of bentonite with cement. There is now a growing literature elsewhere on this subject which does not seem to be reflected in studies carried out by SKB. Collaboration with other waste disposal authorities interested in this topic is recommended. It may be necessary to incorporate chemical processes into the current SKB conceptual model of gas transport in buffer and backfill materials. Dissolved or gaseous H{sub 2} is generated by Fe corrosion under anaerobic conditions, and this gas may be reactive with several minerals in bentonite, including smectite. Although field tests carried out by SKB suggest that the emplacement of compacted bentonite will not be a problem from the perspective of buffer performance, borehole, shaft and vault sealing, there are apparent problems for block manufacture. The introduction of oil as a lubricant in block manufacture, for example may pose problems for long-term behaviour of the near-field due to the presence of these organic materials. Better manufacturing methods are therefore required 112 refs, 4 figs, 4 tabs

Backfilling of deposition tunnels: Use of bentonite pellets

International Nuclear Information System (INIS)

Dixon, David; Sanden, Torbjoern; Jonsson, Esther; Hansen, Johanna

2011-02-01

determine what properties must be exhibited by adjacent swelling materials (Highly Compacted Bentonite or other densely compacted clay-based backfill blocks) in order that the backfill component meets its performance requirements once system equilibration has occurred. Although there is some information available from literature related to pellets, there is still a need to evaluate what optimization can be achieved with respect to density, shape, composition, gradation and as-placed properties. Studies completed to date show a typical as-placed dry density range of ∼1,000 kg/m3 for narrow gaps associated with the block and air-entrained pellet backfill to ∼1,400 kg/m3 for pellet-granule mixtures installed in a horizontal tunnel where equipment access is less problematic. The KBS-3V concept presently utilises pellets placed to ∼1,000 kg/m3 which makes qualification of adjacent sealing materials (HCB or other clay-based blocks) of high importance (ensuring system performance goals are met). These pellet materials also require that means of minimizing erosion caused by water flow along the pellet-rock interface be identified and technological means to protect the backfill from erosion be kept ready for use

Backfilling of deposition tunnels: Use of bentonite pellets

Energy Technology Data Exchange (ETDEWEB)

Dixon, David (Atomic Energy of Canada Limited (Canada)); Sanden, Torbjoern (Clay Technology AB (Sweden)); Jonsson, Esther (Swedish Nuclear Fuel and Waste Mangaement Co. (Sweden)); Hansen, Johanna (Posiva Oy (Finland))

2011-02-15

determine what properties must be exhibited by adjacent swelling materials (Highly Compacted Bentonite or other densely compacted clay-based backfill blocks) in order that the backfill component meets its performance requirements once system equilibration has occurred. Although there is some information available from literature related to pellets, there is still a need to evaluate what optimization can be achieved with respect to density, shape, composition, gradation and as-placed properties. Studies completed to date show a typical as-placed dry density range of approx1,000 kg/m3 for narrow gaps associated with the block and air-entrained pellet backfill to approx1,400 kg/m3 for pellet-granule mixtures installed in a horizontal tunnel where equipment access is less problematic. The KBS-3V concept presently utilises pellets placed to approx1,000 kg/m3 which makes qualification of adjacent sealing materials (HCB or other clay-based blocks) of high importance (ensuring system performance goals are met). These pellet materials also require that means of minimizing erosion caused by water flow along the pellet-rock interface be identified and technological means to protect the backfill from erosion be kept ready for use

Are distribution coefficients measured from batch experiments meaningful for quantifying retention in compacted material?

Energy Technology Data Exchange (ETDEWEB)

Goutelard, F.; Charles, Y.; Page, J. [CEA/DEN/DPC/SECR/L3MR batiment 450, 91191 Gif sur Yvette (France)

2005-07-01

Full text of publication follows: To quantify the ability of a clayey material to act as a barrier for radionuclides migration, reliable data on retention properties must be available. The most common method for determining the distribution coefficient, quantifying the radionuclide adsorption, is the batch technique applied to powdered solid. Are these data meaningful for highly compacted minerals? This question is still under debate in literature [1,2]. The aim of the present study is to compare distribution coefficient (KD) value for Cs and Ni onto compacted and dispersed for both Bentonite MX80 and Callovo-Oxfordian clayey material in a simulated site water. Firstly, classical batch sorption experiments are carried on dispersed materials pre-conditioned with the simulated site water at pH 7.3. Radiotracer {sup 137}Cs and {sup 58}Ni are used to investigate the constant-pH isotherm sorption. The bottleneck for measuring distribution coefficient onto highly compacted material lies in a careful monitoring of chemical conditions because they are driven by diffusion processes. For this study, we have chosen to use in-diffusion experiments [3]. Sample size is optimized to reach for high retention level (300 mL/g) the steady state in a reasonable time (3 to 6 month). In order to describe the response surface of compacted distribution coefficient on bentonite MX80, a 2 variables Doehlert matrix has been chosen. In this experimental design, the two variables are density and dispersed distribution coefficient. Bentonite is pre-conditioning before compaction to a density ranging from 1.2 to 1.85 kg/l. The pellet is confined in a cylindrical stainless steel filter (150 {mu}L) closed to both ends. The cell is placed in a tightly closed bottle containing the working solution. After a re-equilibration period (at least 3 weeks), {sup 133}Cs and {sup 59}Ni stable isotope are introduced for monitoring the KD level (between 150 mL/g to 330 mL/g). Radiotracer {sup 137}Cs and {sup 58

Are distribution coefficients measured from batch experiments meaningful for quantifying retention in compacted material?

International Nuclear Information System (INIS)

Goutelard, F.; Charles, Y.; Page, J.

2005-01-01

Full text of publication follows: To quantify the ability of a clayey material to act as a barrier for radionuclides migration, reliable data on retention properties must be available. The most common method for determining the distribution coefficient, quantifying the radionuclide adsorption, is the batch technique applied to powdered solid. Are these data meaningful for highly compacted minerals? This question is still under debate in literature [1,2]. The aim of the present study is to compare distribution coefficient (KD) value for Cs and Ni onto compacted and dispersed for both Bentonite MX80 and Callovo-Oxfordian clayey material in a simulated site water. Firstly, classical batch sorption experiments are carried on dispersed materials pre-conditioned with the simulated site water at pH 7.3. Radiotracer 137 Cs and 58 Ni are used to investigate the constant-pH isotherm sorption. The bottleneck for measuring distribution coefficient onto highly compacted material lies in a careful monitoring of chemical conditions because they are driven by diffusion processes. For this study, we have chosen to use in-diffusion experiments [3]. Sample size is optimized to reach for high retention level (300 mL/g) the steady state in a reasonable time (3 to 6 month). In order to describe the response surface of compacted distribution coefficient on bentonite MX80, a 2 variables Doehlert matrix has been chosen. In this experimental design, the two variables are density and dispersed distribution coefficient. Bentonite is pre-conditioning before compaction to a density ranging from 1.2 to 1.85 kg/l. The pellet is confined in a cylindrical stainless steel filter (150 μL) closed to both ends. The cell is placed in a tightly closed bottle containing the working solution. After a re-equilibration period (at least 3 weeks), 133 Cs and 59 Ni stable isotope are introduced for monitoring the KD level (between 150 mL/g to 330 mL/g). Radiotracer 137 Cs and 58 Ni are used to quantify the

Effects of water inflow into a deposition hole - Influence of pellets type and of buffer block manufacturing technique

Energy Technology Data Exchange (ETDEWEB)

Johannesson, Lars-Erik; Jense, Viktor [Clay Technology AB, Lund (Sweden)

2012-10-15

During the installation of buffer and canister in a deposition hole a number of different problems can arise. The problems are mainly connected to water flow from fractures in the rock into the deposition hole. According to the reference design for the KBS-3V concept, the buffer is protected with a special sheet made of rubber during the installation phase. This protection sheet will at some stage be removed and the outer gap between the buffer blocks and the rock surface will be filled with bentonite pellets. The interaction of buffer blocks and pellets have previously been investigated. The focuses of those studies were the following processes: 1. Erosion. Erosion of bentonite from the deposition hole up into the tunnel backfill material. This process will continue until a tunnel plug has been installed and the backfill is saturated. 2. Heave. Early wetting of the pellets filling may cause a heave of the buffer blocks into the backfill that will decrease the density of the buffer. The laboratory tests presented in this study are complementing previous investigations by focusing on how the choice of manufacturing process for the bentonite blocks (isostatic or uniaxial compaction) and pellets (roller compaction or extrusion) are affecting erosion and the heaving effect.

Effects of water inflow into a deposition hole - Influence of pellets type and of buffer block manufacturing technique

International Nuclear Information System (INIS)

Johannesson, Lars-Erik; Jense, Viktor

2012-10-01

During the installation of buffer and canister in a deposition hole a number of different problems can arise. The problems are mainly connected to water flow from fractures in the rock into the deposition hole. According to the reference design for the KBS-3V concept, the buffer is protected with a special sheet made of rubber during the installation phase. This protection sheet will at some stage be removed and the outer gap between the buffer blocks and the rock surface will be filled with bentonite pellets. The interaction of buffer blocks and pellets have previously been investigated. The focuses of those studies were the following processes: 1. Erosion. Erosion of bentonite from the deposition hole up into the tunnel backfill material. This process will continue until a tunnel plug has been installed and the backfill is saturated. 2. Heave. Early wetting of the pellets filling may cause a heave of the buffer blocks into the backfill that will decrease the density of the buffer. The laboratory tests presented in this study are complementing previous investigations by focusing on how the choice of manufacturing process for the bentonite blocks (isostatic or uniaxial compaction) and pellets (roller compaction or extrusion) are affecting erosion and the heaving effect

Design and construction of a large-scale sand-bentonite seal for controlled gas release from a L/ILW repository - The GAST project at GTS

International Nuclear Information System (INIS)

Rueedi, J.; Marschall, P.; Vaissiere, R. de la; Jung, H.; Reinhold, M.; Steiner, P.; Garcia-Sineriz, J.L.

2012-01-01

experiments on the real scale are needed for benchmarking the performance of the two-phase flow models. The Gas-Permeable Seal Test (GAST) was initiated in 2010 as a GTS partner project with Andra and KRMC as project partners. The experiment was emplaced at Grimsel Test Site (GTS) in 2011/2012. The S/B seal with a length of 8 m and a diameter of 3m was emplaced to demonstrate the effective functioning of gas permeable seals at realistic scales and under realistic hydraulic boundary conditions ('proof of concept'). The latter condition required the experiment to be emplaced in an existing TBM (tunnel boring machine) drilled tunnel at GTS where the surrounding granite has shown to provide a negligible excavation damaged zone (EDZ) and the stiff rock enables water injection at pressures similar to those expected for a L/ILW repository seal, i.e. 3-5 MPa corresponding to the hydrostatic pressure at 300-500 m depth. The S/B body was compacted manually in horizontal sheets of about 10 cm thickness with a target dry density of 1.7 g/cm 3 . The remaining head space as well as all S/B interfaces (i.e. towards granite and concrete plug) were sealed with granular bentonite and/or with bentonite blocks. The experiment is planned to be saturated until 2014 followed by gas injection from the far end of the tunnel in 2015. The experiment aims at validating and, if necessary, improving current conceptual models for the re-saturation and gas invasion processes into S/B seals and the determination of up-scaled gas / water permeabilities of S/B seals (i.e. two-phase flow parameters for large-scale models). For this reason material saturation, water pressures and earth pressures are monitored continuously by more than 150 sensors distributed among 15 instrumentation cross sections, comprising of piezometers for pore pressure, relative humidity sensors, psychrometers and TDRs for water saturation, total pressure cells for stress state and piezo-crystals for seismic tomography. All instruments and

Evolution of the bentonite barrier under glacial meltwater intrusion conditions

Energy Technology Data Exchange (ETDEWEB)

Schaefer, T.; Bouby, M. [Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen (Germany). Inst. for Nuclear Waste Disposal (INE); Blechschmidt, I. [NAGRA National Cooperation Disposal Radioactive Waste, Wettingen (Switzerland); and others

2015-07-01

Recent safety assessments for repository concepts that combine a clay engineered barrier system (EBS) with a fractured rock have shown that melt water intrusion may have a direct impact on the EBS barrier function in two aspects: - Generation of colloids may degrade the engineered barrier - Colloid transport of radionuclides may reduce the efficiency of the natural barrier The studies presented here are performed in the framework of the Federal Ministry of Economic Affairs and Energy (BMWi) KIT/GRS project KOLLORADO-e, the EU collaborative project CP BELBaR (www.skb.se/belbar) and especially within the Colloid Formation and Migration (CFM) project at the Grimsel Test Site, GTS (www.grimsel.com). Key research areas are (a) the erosion of the bentonite buffer, (b) clay colloid stability and (c) colloid-radionuclide- host rock surface interactions. Concerning bentonite buffer integrity parameters like the bentonite type, Na-/Ca-exchangeable cation ratio, compaction density, role of accessory minerals, the fracture aperture size and groundwater chemistry and flow velocity are investigated in order to identify controlling factors, understand the main mechanisms of erosion from the bentonite surface and to quantify the extent of the possible erosion under these different conditions. Clay colloid stability studies are performed under different geochemical conditions. The main objective is to answer the question if colloids formed at the near/far field interface would be stable only if favourable conditions exist and therefore their relevance for radionuclide transport will be strongly dependent on the local geochemical conditions (inorganic cations Na{sup +}, Ca{sup 2+}, Mg{sup 2+}, Al{sup 3+} and organic complexing agents). Finally, the interaction between colloids and radionuclides and the host rock is intensively investigated in order to answer the question, how colloid mobility may be affected by the composition of the host rock, surface roughness and the mechanism of

Development of a bentonite free swelling model in an elastoplastic framework

International Nuclear Information System (INIS)

Navarro, V.; Asensio, L.; Yustres, A.; Alonso, J.; Pintado, X.

2012-01-01

Document available in extended abstract form only. The aim of this work is to develop a Hydro-Chemo-Mechanical (HcM) model able to consistently reproduce the whole swelling process of both unsaturated and saturated bentonites. The Barcelona Expansive Model (BExM) was taken as a starting point, as it has been satisfactorily applied to model the behaviour of compacted bentonites. However, its suitability for the analysis of free swelling has not been proved, namely for the case when porosities reach values close to and over 0.9 and the soil becomes disarranged. These conditions mean pulling BExM further away from the domain for which it was initially conceived. For this reason, a modified formulation of BExM has been developed. It has been named m/BExM. In order to explain the high swelling ability of bentonites, it is assumed that the distortion of the water structure induced by the clay sheets begins to have a significant effect also in macro water structure when the micro void ratio goes beyond a certain threshold value and the confining forces do not exceed the repulsive forces. Accordingly, macro water will experience a decrease in its chemical potential, and the voids in which this phenomenon takes part will act as sinks, increasing their volume and causing an important raise of macro-porosity (disarrangement of the soil macro skeleton). When this phenomenon starts, the micro strain rate is greater than that of the macro disarrangement. Nonetheless, when the micro void ratio reaches high values, the disarrangement becomes more significant. The variation of the micro void ratio with the swelling pressure is described with an exponential law. The developed formulation takes into account the geochemical effects by using a modified swelling pressure, in keeping with the proposal of Karnland et al. (2005) when working with a saline solution of relevant concentration. The presence of sodium and calcium cations, as well as that of a generic polyvalent anion (by

{sup 137}Cs sorption into bentonite from Cidadap-Tasikmalaya as buffer material for disposal demonstration plant facility at Serpong

Energy Technology Data Exchange (ETDEWEB)

Setiawan, B., E-mail: bravo@batan.go.id; Sriwahyuni, H., E-mail: bravo@batan.go.id; Ekaningrum, NE., E-mail: bravo@batan.go.id; Sumantry, T., E-mail: bravo@batan.go.id [Radwaste Technology Center-National Nuclear Energy Agency, PUSPIPTEK, Serpong-Tangerang 15310 (Indonesia)

2014-03-24

According to co-location principle, near surface disposal type the disposal demonstration plant facility will be build at Serpong nuclear area. The facility also for anticipation of future needs to provide national facility for the servicing of radwaste management of non-nuclear power plant activity in Serpong Nuclear Area. It is needs to study the material of buffer and backfill for the safety of demonstration plant facility. A local bentonite rock from Cidadap-Tasikmalaya was used as the buffer materials. Objective of experiment is to find out the specific data of sorption characteristic of Cidadap bentonite as buffer material in a radwaste disposal system. Experiments were performed in batch method, where bentonite samples were contacted with CsCl solution labeled with Cs-137 in 100 ml/g liquid:solid ratio. Initial Cs concentration was 10{sup −8} M and to study the effects of ionic strength and Cs concentration in solution, 0.1 and 1.0 M NaCl also CsCl concentration ranging 10{sup −8} - 10{sup −4} M were added in solution. As the indicator of Cs saturated in bentonite samples, Kd value was applied. Affected parameters in the experiment were contact time, effects of ionic strength and concentration of CsCl. Results showed that sorption of Cs by bentonite reached constantly after 16 days contacted, and Kd value was 10.600 ml/g. Effect of CsCl concentration on Kd value may decreased in increased in CsCl concentration. Effect of ionic strength increased according to increased in concentration of background and would effect to Kd value due to competition of Na ions and Cs in solution interacts with bentonite. By obtaining the bentonite character data as buffer material, the results could be used as the basis for making of design and the basic of performance assessment the near surface disposal facility in terms of isolation capacity of radwaste later.

Investigations of excavated clay-stone as backfill/seal material

International Nuclear Information System (INIS)

Zhang, Chun-Liang

2012-01-01

Document available in extended abstract form only. Crushed clay-stone produced by excavation activities of repository drifts has been investigated as backfill/seal material at the GRS laboratory. The raw aggregate with coarse grains is considered to be used for backfilling the repository openings and, in mixture with bentonite, for sealing the boreholes, drifts and shafts. The GRS research programme focused on characterizing the thermo-hydro-mechanical properties of the excavated Callovo-Oxfordian clay-stone (COX) and the clay-stone-bentonite mixtures, including mechanical compaction, gas and water permeability as function of porosity, water retention and saturation, swelling capacity, and thermal properties of the materials. The most important results are presented in this paper. Figure 1 shows the compaction and permeability behaviour of the excavated clay-stone with grains up to a size of 32 mm. The results were obtained on large samples of 280 mm diameter and 680 mm height under quasi-hydrostatic compression. The porosity and permeability decrease with increasing load. The porosity-mean stress relation is non-linear and may be expressed by an exponential function. The backfill becomes stiffer at low porosities and can sustain certain deviatoric loads. At porosity of ∼21 %, the strength is characterized by an inherent cohesion of 3.7 MPa and an internal friction angle of 12 deg.. Additionally, the compaction is also dependent on time or loading rate, water content, and temperature. The compaction of the porous backfill material leads to a reduction in permeability. The measured gas permeability decreases much faster at low porosities below ∼25 %. The gas permeability at porosity of ∼20 % becomes as low as that of 10 -20 - 10 -21 m 2 for the intact clay rock. This is probably due to disconnection of the pore network during the compaction. As sealing material, powdered COX clay-stone was mixed with MX80 bentonite powder in different ratios and compacted to

Immobilizing Bacillus subtilis on the carrier of poly (acrylic acid)/sodium bentonite for treating sludge from Pangasius fish ponds

International Nuclear Information System (INIS)

Nguyen Thanh Duoc; Doan Binh; Pham Thi Thu Hong

2016-01-01

Sodium bentonite (NaBent) was modified by poly(acrylic acid) (PAAc) to prepare the carriers for immobilization of Bacillus subtilis. Different mixtures of NaBent/AAc were regularly dispersed in distilled water and irradiated under gamma rays at an absorbed dose of 6.5 kGy with dose rate of 0.85 kGy/hr in air for polymerization of acrylic acid and formation of poly(acrylic acid)/sodium bentonite (PAAc-NaBent). The reaction yield was determined with the initial concentration of acrylic acid (AAc). The functional group properties of the resulting PAAc-NaBent were analyzed by Fourier Transform Infrared spectra (FTIR). Bacillus subtilis cells were immobilized on both NaBent and PAAc-NaBent as carriers by adsorption method for treating the sludge contaminated by fish feces and residual feed from the Pangasius farming ponds. The results showed that immobilization capacity of Bacillus subtilis on the PAAc-NaBent was better than that on non-modified NaBent. Analysis of BOD for the farming pond water containing Bacillus subtilis and the bacteria immobilized carriers with time revealed the lower BOD values obtained with the samples containing PAAc-NaBent, suggested that degradation of organic pollutants by Bacillus subtilis immobilized on the PAAc-Na Bent was faster than that by free bacteria. (author)

The influence of colloids on the migration of radionuclides

International Nuclear Information System (INIS)

Seher, Holger

2011-01-01

For a concept of deep geological disposal of high level nuclear waste, the repository will be designed as a multiple-barrier system including bentonite as the buffer/backfill material and the host rock formation as the geological barrier. The engineered barrier (compacted bentonite) will be in contact with the host rock formation (e.g. granite). Consequently the bentonite will be saturated over time with formation groundwater, which will induce swelling and gel formation of the bentonite. At the gel-groundwater boundary, colloid detachment might be a possible colloid source and therefore might enhance the mobility of strong sorbing actinides. This work will focus on three aspects of colloidal transport: (a) Colloid stability in the mixing zone between granite groundwater and bentonite pore water, including its description with an extended DLVO model. (b) Colloid generation and erosion of the bentonite at the interface between compacted bentonite and granitic groundwater, as well as formation of new colloids in the mixing zone between the bentonite porewater and the granitic groundwater. (c) Colloid transport and the interaction of U, Th, Hf, Tb, Eu and Cm with bentonite colloids and fracture filling material, as well as their mobility in a natural fracture.

Stability of bentonite gels in crystalline rock

International Nuclear Information System (INIS)

Pusch, R.

1983-02-01

The present, extended study comprises a derivation of a simple rock model as a basis for calculation of the penetration rate of bentonite and of the groundwater flow rate, which is a determinant of the erodibility of the protruding clay film. This model, which is representative of a gross permeability of about 10 -8 - 10 -9 m/s, implies a spectrum of slot-shaped joints with apertures ranging between 0.1 and 0.5 mm. It is concluded that less than 2percent of the highly compacted bentonite will be lost into traversing joints in 10 6 years. A closer analysis, in which also Poiseuille retardation and short-term experiments were taken into account, even suggests that the penetration into the considered joints will be less than that. The penetration rate is expected to be 1 decimeter in a few hundred years. The risk of erosion by flowing groundwater was estimated by comparing clay particle bond strength, evaluated from viscometer tests, and theoretically derived drag forces, the conclusion being that the maximum expected water flow rate in the widest joints of the rock model (4 times 10 -4 m/s) is not sufficient to disrupt the gel front or the large individual clay flocs that may exist at this front. The experiments support the conclusion that erosion will not be a source of bentonite loss. A worst case scenario with a shear zone being developed across deposition holes is finally considered and in addition to this, the conditions in the fracture-rich tunnel floor at the upper end of the deposition holes are also analysed. This study shows that even if the rock is much more fractured than normal conditions would imply, the bentonite loss is expected to be very moderate and without substantial effect on the barrier functions of the remaining clay cores in the deposition holes. (author)

Heat conductivity of buffer materials

International Nuclear Information System (INIS)

Boergesson, L.; Fredrikson, Anders; Johannesson, L.E.

1994-11-01

The report deals with the thermal conductivity of bentonite based buffer materials. An improved technique for measuring the thermal conductivity of buffer materials is described. Measurements of FLAC calculations applying this technique have led to a proposal of how standardized tests should be conducted and evaluated. The thermal conductivity of bentonite with different void ratio and degree of water saturation has been determined in the following different ways: * Theoretically according to three different investigations by other researchers. * Laboratory measurements with the proposed method. * Results from back-calculated field tests. Comparison and evaluation showed that these results agreed very well, when the buffer material was almost water saturated. However, the influence of the degree of saturation was not very well predicted with the theoretical methods. Furthermore, the field tests showed that the average thermal conductivity in situ of buffer material (compacted to blocks) with low degree of water saturation was lower than expected from laboratory tests. 12 refs, 29 figs, 11 tabs

Controlled release of diuron from an alginate-bentonite formulation: water release kinetics and soil mobility study.

Science.gov (United States)

Fernández-Pérez, M; Villafranca-Sánchez, M; González-Pradas, E; Flores-Céspedes, F

1999-02-01

The herbicide diuron was incorporated in alginate-based granules to obtain controlled release (CR) properties. The standard formulation (alginate-herbicide-water) was modified by the addition of different sorbents. The effect on diuron release rate caused by incorporation of natural and acid-treated bentonites in alginate formulation was studied by immersion of the granules in water under static conditions. The release of diuron was diffusion-controlled. The time taken for 50% release of active ingredient to be released into water, T(50), was calculated for the comparison of formulations. The addition of bentonite to the alginate-based formulation produced the higher T(50) values, indicating slower release of the diuron. The mobility of technical and formulated diuron was compared by using soil columns. The use of alginate-based CR formulations containing bentonite produced a less vertical distribution of the active ingredient as compared to the technical product and commercial formulation. Sorption capacities of the various soil constituents for diuron were also determined using batch experiments.

Modelling of erosion of bentonite gel by gel/sol flow

Energy Technology Data Exchange (ETDEWEB)

Moreno, Luis; Neretnieks, Ivars; Longcheng Liu (Chemical Engineering and Technology, School of Chemical Science and Engineering, Royal Institute of Technology, Stockholm (Sweden))

2010-11-15

order of a metre per year the gel may penetrate several metres into the fracture when steady state is reached. The simulations were made with only sodium as counterion. Most simulations had sodium concentrations below the critical coagulation concentration, CCC. In the compacted bentonite at the fracture mouth it was 10 mM and 0.1 mM in the approaching water. At these concentrations the gel is expansive and can turn into a sol releasing colloidal particles. The low ion concentration has a strong impact on the fluid viscosity, which increases with decreasing ionic strength. At the same time, however the repulsion forces between the smectite particles increase causing a quicker expansion. Simulations with higher sodium concentrations had a marginal influence on the erosion rate. For the highest water flow rates the smectite loss could be up to 0.3 kg per year for one canister. This is more than one order of magnitude larger than what could be reached by smectite particle diffusion alone if fluid flow was neglected. In experiments in downward facing slits (fractures) it has been found that bentonite releases gel agglomerates much faster than expected. These are released and sediment also under conditions where it is expected that the smectite particles should have separated into individual smectite sheets, which would not noticeably be influenced by gravity. The reasons for this behaviour are not understood. In the modelling it is assumed that there are no other larger non-smectite particles that would be left behind to gradually build up a bed of particles that could act as filter, slowing down or even straining further smectite penetration into the fracture. The modelling results could therefore be highly pessimistic because bentonites contain tens of percent of accessory minerals that do not form colloids and the presence of which may cause the expansion to be slowed down by friction against the fracture walls

Modelling of erosion of bentonite gel by gel/sol flow

International Nuclear Information System (INIS)

Moreno, Luis; Neretnieks, Ivars; Longcheng Liu

2010-11-01

order of a metre per year the gel may penetrate several metres into the fracture when steady state is reached. The simulations were made with only sodium as counterion. Most simulations had sodium concentrations below the critical coagulation concentration, CCC. In the compacted bentonite at the fracture mouth it was 10 mM and 0.1 mM in the approaching water. At these concentrations the gel is expansive and can turn into a sol releasing colloidal particles. The low ion concentration has a strong impact on the fluid viscosity, which increases with decreasing ionic strength. At the same time, however the repulsion forces between the smectite particles increase causing a quicker expansion. Simulations with higher sodium concentrations had a marginal influence on the erosion rate. For the highest water flow rates the smectite loss could be up to 0.3 kg per year for one canister. This is more than one order of magnitude larger than what could be reached by smectite particle diffusion alone if fluid flow was neglected. In experiments in downward facing slits (fractures) it has been found that bentonite releases gel agglomerates much faster than expected. These are released and sediment also under conditions where it is expected that the smectite particles should have separated into individual smectite sheets, which would not noticeably be influenced by gravity. The reasons for this behaviour are not understood. In the modelling it is assumed that there are no other larger non-smectite particles that would be left behind to gradually build up a bed of particles that could act as filter, slowing down or even straining further smectite penetration into the fracture. The modelling results could therefore be highly pessimistic because bentonites contain tens of percent of accessory minerals that do not form colloids and the presence of which may cause the expansion to be slowed down by friction against the fracture walls

Quality assurance of the bentonite material

International Nuclear Information System (INIS)

Ahonen, L.; Korkeakoski, P.; Tiljander, M.; Kivikoski, H.; Laaksonen, R.

2008-05-01

This report describes a quality assurance chain for the bentonite material acquisition for a nuclear waste disposal repository. Chemical, mineralogical and geotechnical methods, which may be applied in quality control of bentonite are shortly reviewed. As a case study, many of the presented control studies were performed for six different bentonite samples. Chemical analysis is a very reliable research method to control material homogeneity, because the accuracy and repeatability of the study method is extremely good. Accurate mineralogical study of bentonite is a complicated task. X-ray diffractometry is the best method to identify smectite minerals, but quantitative analysis of smectite content remains uncertain. To obtain a better quantitative analysis, development of techniques based on automatic image analysis of SEM images is proposed. General characteristics of bentonite can be obtained by rapid indicator tests, which can be done on the place of reception. These tests are methylene blue test giving information on the cation exchange capacity, swelling index and determination of water absorption. Different methods were used in the determination of cation exchange capacity (CEC) of bentonite. The results indicated differences both between methodologies and between replicate determinations for the same material and method. Additional work should be done to improve the reliability and reproducibility of the methodology. Bentonite contains water in different modes. Thus, different determination methods are used in bentonite studies and they give somewhat dissimilar results. Clay research use frequently the so-called consistency tests (liquid limit, plastic limit and plasticity index). This study method does, however, not seem to be very practical in quality control of bentonite. Therefore, only the determination of liquid limit with fall-cone method is recommended for quality control. (orig.)

Survival of bacteria in nuclear waste buffer materials. The influence of nutrients, temperature and water activity

Energy Technology Data Exchange (ETDEWEB)

Pedersen, K.; Motamedi, M. [Goeteborg Univ. (Sweden). Dept. of General and Marine Microbiology; Karnland, O. [Clay Technology AB, Lund (Sweden)

1995-12-01

The concept of deep geological disposal of spent fuel is common to many national nuclear waste programs. Long-lived radioactive waste will be encapsulated in canisters made of corrosion resistant materials e.g. copper and buried several hundred meters below ground in a geological formation. Different types of compacted bentonite clay, or mixtures with sand, will be placed as a buffer around the waste canisters. A major concern for the performance of the canisters is that sulphate-reducing bacteria (SRB) may be present in the clay and induce corrosion by production of hydrogen sulphide. This report presents data on viable counts of SRB in the bedrock of Aespoe hard rock laboratory. A theoretical background on the concept water activity is given, together with basic information about SRB. Some results on microbial populations from a full scale buffer test in Canada is presented. These results suggested water activity to be a strong limiting factor for survival of bacteria in compacted bentonite. As a consequence, experiments were set up to investigate the effect from water activity on survival of SRB in bentonite. Here we show that survival of SRB in bentonite depends on the availability of water and that compacting a high quality bentonite to a density of 2.0 g/cm{sup 3}, corresponding to a water activity (a{sub w}) of 0.96, prevented SRB from surviving in the clay. 24 refs.

Study on the properties of Gaomiaozi bentonite as the buffer/backfilling materials for HLW disposal

International Nuclear Information System (INIS)

Liu Xiaodong; Luo Taian; Zhu Guoping; Chen Qingchun

2007-12-01

Systematic studies including mineral composition and structure, physico- chemical properties and thermal properties have been conducted on Gaomiaozi bentonite, Xinghe County, Inner Mongolia Autonomous Region. The compaction characteristics of bentonite and the influence of additive to bentonite have been discussed. The analysis of mineral composition and structure show that the bentonite ores are dominated by montmorillonite. Preliminary studies of the characteristics of ores indicated that No-type bentonite from the deposit has good absorption, excellent swelling and high cation exchangeability. The compressibility of bentonite will be improved by adding the additives such as quartz sand. The studies indicated that the characteristics of Gaomiaozi bentonite can satisfy the requirement of buffer/backfilling materials for HLW repository and the ores can be selected as the preferential candidate to provide buffer/backfill- ing materials for HLW repository in China. (authors)

Study on the properties of Gaomiaozi bentonite as the buffer/backfilling materials for HLW disposal

Energy Technology Data Exchange (ETDEWEB)

Xiaodong, Liu [East China Inst. of Technology, Fuzhou (China); [Key Laboratory of Nuclear Resources and Environment of Ministry of Education, Fuzhou (China); Taian, Luo; Guoping, Zhu; Qingchun, Chen [East China Inst. of Technology, Fuzhou (China)

2007-12-15

Systematic studies including mineral composition and structure, physico- chemical properties and thermal properties have been conducted on Gaomiaozi bentonite, Xinghe County, Inner Mongolia Autonomous Region. The compaction characteristics of bentonite and the influence of additive to bentonite have been discussed. The analysis of mineral composition and structure show that the bentonite ores are dominated by montmorillonite. Preliminary studies of the characteristics of ores indicated that No-type bentonite from the deposit has good absorption, excellent swelling and high cation exchangeability. The compressibility of bentonite will be improved by adding the additives such as quartz sand. The studies indicated that the characteristics of Gaomiaozi bentonite can satisfy the requirement of buffer/backfilling materials for HLW repository and the ores can be selected as the preferential candidate to provide buffer/backfill- ing materials for HLW repository in China. (authors)

Uniaxial backfill block compaction

International Nuclear Information System (INIS)

Koskinen, V.

2012-05-01

The main parts of the project were: to make a literature survey of the previous uniaxial compaction experiments; do uniaxial compaction tests in laboratory scale; and do industrial scale production tests. Object of the project was to sort out the different factors affecting the quality assurance chain of the backfill block uniaxial production and solve a material sticking to mould problem which appeared during manufacturing the blocks of bentonite and cruched rock mixture. The effect of mineralogical and chemical composition on the long term functionality of the backfill was excluded from the project. However, the used smectite-rich clays have been tested for mineralogical consistency. These tests were done in B and Tech OY according their SOPs. The objective of the Laboratory scale tests was to find right material- and compaction parameters for the industrial scale tests. Direct comparison between the laboratory scale tests and industrial scale tests is not possible because the mould geometry and compaction speed has a big influence for the compaction process. For this reason the selected material parameters were also affected by the previous compaction experiments. The industrial scale tests were done in summer of 2010 in southern Sweden. Blocks were done with uniaxial compaction. A 40 tons of the mixture of bentonite and crushed rock blocks and almost 50 tons of Friedland-clay blocks were compacted. (orig.)

Flow of gasoline-in-water microemulsion through water-saturated soil columns

International Nuclear Information System (INIS)

Ouyang, Y.; Mansell, R.S.; Rhue, R.D.

1995-01-01

Much consideration has been given to the use of surfactants to clean up nonaqueous phase liquids (NAPLs) from contaminated soil and ground water. Although this emulsification technique has shown significant potential for application in environmental remediation practices, a major obstacle leading to low washing efficiency is the potential formation of macroemulsion with unfavorable flow characteristics in porous media. This study investigated influences of the flow of leaded-gasoline-in-water (LG/W) microemulsion upon the transport of gasoline and lead (Pb) species in water-saturated soil columns. Two experiments were performed: (1) the immiscible displacement of leaded gasoline and (2) the miscible displacement of LG/W microemulsion through soil columns, followed by sequentially flushing with NaCl solution and a water/surfactant/cosurfactant (W/S/CoS) mixture. Comparison of breakthrough curves (BTC) for gasoline between the two experiments shows that about 90% of gasoline and total Pb were removed from the soil columns by NaCl solution in the LG/W microemulsion experiment as compared to 40% removal of gasoline and 10% removal of total Pb at the same process in the leaded gasoline experiment. Results indicate that gasoline and Pb species moved much more effectively through soil during miscible flow of LG/W microemulsion than during immiscible flow of leaded gasoline. In contrast to the adverse effects of macroemulsion on the transport of NAPLs, microemulsion was found to enhance the transport of gasoline through water-saturated soil. Mass balance analysis shows that the W/S/CoS mixture had a high capacity for removing residual gasoline and Pb species from contaminated soil. Comparison of water-pressure differences across the soil columns for the two experiments indicates that pore clogging by gasoline droplets was greatly minimized in the LG/W microemulsion experiment

MODIFIED REVERSE OSMOSIS SYSTEM FOR TREATMENT OF PRODUCED WATERS

Energy Technology Data Exchange (ETDEWEB)

Robert L. Lee; Junghan Dong

2004-06-03

This final report of ''Modified Reverse Osmosis System for Treatment of Produced Water,'' DOE project No. DE-FC26-00BC15326 describes work performed in the third year of the project. Several good results were obtained, which are documented in this report. The compacted bentonite membranes were replaced by supported bentonite membranes, which exhibited the same salt rejection capability. Unfortunately, it also inherited the clay expansion problem due to water invasion into the interlayer spaces of the compacted bentonite membranes. We noted that the supported bentonite membrane developed in the project was the first of its kind reported in the literature. An {alpha}-alumina-supported MFI-type zeolite membrane synthesized by in-situ crystallization was fabricated and tested. Unlike the bentonite clay membranes, the zeolite membranes maintained stability and high salt rejection rate even for a highly saline solution. Actual produced brines from gas and oil fields were then tested. For gas fields producing brine, the 18,300 ppm TDS (total dissolved solids) in the produced brine was reduced to 3060 ppm, an 83.3% rejection rate of 15,240 ppm salt rejection. For oilfield brine, while the TDS was reduced from 181,600 ppm to 148,900 ppm, an 18% rejection rate of 32,700 ppm reduction, the zeolite membrane was stable. Preliminary results show the dissolved organics, mainly hydrocarbons, did not affect the salt rejection. However, the rejection of organics was inconclusive at this point. Finally, the by-product of this project, the {alpha}-alumina-supported Pt-Co/Na Y catalytic zeolite membrane was developed and demonstrated for overcoming the two-step limitation of nonoxidation methane (CH{sub 4}) conversion to higher hydrocarbons (C{sub 2+}) and hydrogen (H{sub 2}). Detailed experiments to obtain quantitative results of H{sub 2} generation for various conditions are now being conducted. Technology transfer efforts included five manuscripts submitted to

Long-term gas migration modelling in compacted bentonite using swelling/shrinkage-dependent two phase flow parameters

International Nuclear Information System (INIS)

Tawara, Y.; Mori, K.; Tada, K.; Shimura, T.; Sato, S.; Yamamoto, S.; Asano, H.; Namiki, K.

2012-01-01

Document available in extended abstract form only. After the completion of field-scaled Gas Migration Test (GMT) at the Grimsel Test Site (GTS Phase V Project, 1996-2004), an advanced gas migration modelling study has been implemented to increase the accuracy and reliability as a part of the R and D programs by the Radioactive Waste Management funding and research Center (RWMC) in Japan. The multiple gas migration modes which consist of diffusive transport of dissolved gas, conventional two phase flow, pore failure induced microscopic fissuring and macroscopic fracturing flow, were identified in GMT bentonite. However the required parameters and constitutive models governing those modes are still uncertain. To tackle this issue, an extended validation and scoping study aiming to generalize such gas migration behavior has been performed in the advanced gas migration modelling study. One of the main objectives of the validation study is to identify gas migration modes using laboratory test data and to qualify the alternative models and parameters. In the scoping study, we have extracted the specific THMC (Thermal, Hydrological, Mechanical and Chemical) coupled processes which have impacts on the performance measures such as the pressure built-up in EBS (Engineered Barrier System) and expelled water to the geosphere by gas generation and transport. The measured data of hydration tests and gas injection tests using bentonite specimens with different water contents were reproduced. Two phase flow parameters were estimated using the observed data of both types of tests, independently. The simulated results of the conventional two phase flow model were well-matched with the hydration test data. In the gas injection test, the extended two phase flow model which simulates the pressure-induced pore failure (pathway dilation), was able to reproduce observed data reasonably. However, we found that the identified parameters obtained from the hydration test data were

Sorption behavior of neptunium on bentonite -- Effect of calcium ion on the sorption

International Nuclear Information System (INIS)

Kozai, Naofumi; Ohnuki, Toshihiko; Muraoka, Susumu

1995-01-01

The sorption behavior of neptunium on bentonite was studied with batch type sorption and desorption experiments over a pH range of 2 to 8. A series of parallel studies using Na-smectite, Ca-smectite and admixtures of Na-smectite and calcite quantified the capacity of Ca 2+ (which occurs in bentonite as an exchangeable cation of smectite and as a component of calcite) to inhibit the sorption of neptunium. The distribution coefficient (K d ) of neptunium for bentonite was constant from pH 2 to 7, while for pure Na-smectite K d increased below pH 5 due to specific sorption of neptunium on Na-smectite. Specific sorption was defined as occurring when neptunium could be desorbed by a strong acid (1 M HCl) but was stable in the presence of 1 M KCl. It was found that the quantity of neptunium sorbed on Na-smectite was inversely proportional to the concentration of Ca 2+ in solution, an effect most pronounced at pH 2+ limits the specific sorption capacity of Na-smectite for neptunium. Similarly, in the mixture of Na-smectite and calcite, sufficient Ca 2+ was solubilized to depress neptunium sorption. This investigation demonstrates that Ca 2+ contained in bentonite as exchangeable cation and released from calcite reduces the specific sorption of neptunium

Effects of Pulp and Na-Bentonite Amendments on the Mobility of Trace Elements, Soil Enzymes Activity and Microbial Parameters under Ex Situ Aided Phytostabilization

Science.gov (United States)

Wasilkowski, Daniel; Mrozik, Agnieszka

2017-01-01

The objective of this study was to explore the potential use of pulp (by-product) from coffee processing and Na-bentonite (commercial product) for minimizing the environmental risk of Zn, Pb and Cd in soil collected from a former mine and zinc-lead smelter. The effects of soil amendments on the physicochemical properties of soil, the structural and functional diversity of the soil microbiome as well as soil enzymes were investigated. Moreover, biomass of Festuca arundinacea Schreb. (cultivar Asterix) and the uptake of trace elements in plant tissues were studied. The outdoor pot set contained the following soils: control soil (initial), untreated soil (without additives) with grass cultivation and soils treated (with additives) with and without plant development. All of the selected parameters were measured at the beginning of the experiment (t0), after 2 months of chemical stabilization (t2) and at the end of the aided phytostabilization process (t14). The obtained results indicated that both amendments efficiently immobilized the bioavailable fractions of Zn (87–91%) and Cd (70–83%) at t14; however, they were characterized by a lower ability to bind Pb (33–50%). Pulp and Na-bentonite drastically increased the activity of dehydrogenase (70- and 12-fold, respectively) at t14, while the activities of urease, acid and alkaline phosphatases differed significantly depending on the type of material that was added into the soil. Generally, the activities of these enzymes increased; however, the increase was greater for pulp (3.5-6-fold) than for the Na-bentonite treatment (1.3–2.2-fold) as compared to the control. Soil additives significantly influenced the composition and dynamics of the soil microbial biomass over the experiment. At the end, the contribution of microbial groups could be ordered as follows: gram negative bacteria, fungi, gram positive bacteria, actinomycetes regardless of the type of soil enrichment. Conversely, the shift in the functional

Effects of Pulp and Na-Bentonite Amendments on the Mobility of Trace Elements, Soil Enzymes Activity and Microbial Parameters under Ex Situ Aided Phytostabilization.

Directory of Open Access Journals (Sweden)

Daniel Wasilkowski

Full Text Available The objective of this study was to explore the potential use of pulp (by-product from coffee processing and Na-bentonite (commercial product for minimizing the environmental risk of Zn, Pb and Cd in soil collected from a former mine and zinc-lead smelter. The effects of soil amendments on the physicochemical properties of soil, the structural and functional diversity of the soil microbiome as well as soil enzymes were investigated. Moreover, biomass of Festuca arundinacea Schreb. (cultivar Asterix and the uptake of trace elements in plant tissues were studied. The outdoor pot set contained the following soils: control soil (initial, untreated soil (without additives with grass cultivation and soils treated (with additives with and without plant development. All of the selected parameters were measured at the beginning of the experiment (t0, after 2 months of chemical stabilization (t2 and at the end of the aided phytostabilization process (t14. The obtained results indicated that both amendments efficiently immobilized the bioavailable fractions of Zn (87-91% and Cd (70-83% at t14; however, they were characterized by a lower ability to bind Pb (33-50%. Pulp and Na-bentonite drastically increased the activity of dehydrogenase (70- and 12-fold, respectively at t14, while the activities of urease, acid and alkaline phosphatases differed significantly depending on the type of material that was added into the soil. Generally, the activities of these enzymes increased; however, the increase was greater for pulp (3.5-6-fold than for the Na-bentonite treatment (1.3-2.2-fold as compared to the control. Soil additives significantly influenced the composition and dynamics of the soil microbial biomass over the experiment. At the end, the contribution of microbial groups could be ordered as follows: gram negative bacteria, fungi, gram positive bacteria, actinomycetes regardless of the type of soil enrichment. Conversely, the shift in the functional

Field test of ethanol/bentonite slurry grouting into rock fracture

International Nuclear Information System (INIS)

Motoyuki Asada; Hitoshi Nakashima; Takashi Ishii; Sumio Horiuchi

2006-01-01