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| rdf:type
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| Description
| - The main aim of the repository disposal system is to prevent the migration of radionuclides into the biosphere. It is expected that the natural rock barrier as well as the engineered barrier elements of the system will guarantee the safe disposal of radioactive waste for the required time period. Bentonite clay has proven to be particularly suitable in this respect thanks to its sealing properties (very low permeability in the case of both water and gases). The buffer, which makes up a crucial part of the geotechnical barrier, surrounds the container in the disposal well. The main requirements in terms of the geotechnical properties of the buffer material consist of very low hydraulic conductivity (max 10-12m/s), high swelling ability (Ssw> 1MPa), rheological stability, high plasticity, and good thermal conductivity. The article presents the results of research into the most important geotechnical properties of Czech Ca-Mg bentonites and provides an outline of both the design of the technology and the experimental tests employed to simulate the filling of the gap between the buffer and the rock massif in the disposal well. The materials used in the gap-filling tests included pellets, granules, powder and mixtures thereof. The means of application studied consisted of the free fall pouring method, with and without vibration, and the spray method and the aim was to verify the way in which they worked with the various types and forms of material. The most important geotechnical parameter of the material, i.e. dry density, was determined following the application of the materials. It is hoped that the final design of gap-filling technology will be determined from the results of the mock-up testing of the disposal location. Mock-up tests reveal the impact of the dimensions of the gap on the most important geotechnical properties of the material. The article also presents geotechnical results gained from in-situ mock-up model testing (Mock-up Josef, Bentonite 95).
- The main aim of the repository disposal system is to prevent the migration of radionuclides into the biosphere. It is expected that the natural rock barrier as well as the engineered barrier elements of the system will guarantee the safe disposal of radioactive waste for the required time period. Bentonite clay has proven to be particularly suitable in this respect thanks to its sealing properties (very low permeability in the case of both water and gases). The buffer, which makes up a crucial part of the geotechnical barrier, surrounds the container in the disposal well. The main requirements in terms of the geotechnical properties of the buffer material consist of very low hydraulic conductivity (max 10-12m/s), high swelling ability (Ssw> 1MPa), rheological stability, high plasticity, and good thermal conductivity. The article presents the results of research into the most important geotechnical properties of Czech Ca-Mg bentonites and provides an outline of both the design of the technology and the experimental tests employed to simulate the filling of the gap between the buffer and the rock massif in the disposal well. The materials used in the gap-filling tests included pellets, granules, powder and mixtures thereof. The means of application studied consisted of the free fall pouring method, with and without vibration, and the spray method and the aim was to verify the way in which they worked with the various types and forms of material. The most important geotechnical parameter of the material, i.e. dry density, was determined following the application of the materials. It is hoped that the final design of gap-filling technology will be determined from the results of the mock-up testing of the disposal location. Mock-up tests reveal the impact of the dimensions of the gap on the most important geotechnical properties of the material. The article also presents geotechnical results gained from in-situ mock-up model testing (Mock-up Josef, Bentonite 95). (en)
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| Title
| - The Development of Bentonite Gap Filling for High-Level Waste Disposal
- The Development of Bentonite Gap Filling for High-Level Waste Disposal (en)
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| skos:prefLabel
| - The Development of Bentonite Gap Filling for High-Level Waste Disposal
- The Development of Bentonite Gap Filling for High-Level Waste Disposal (en)
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| skos:notation
| - RIV/68407700:21110/13:00210816!RIV14-MPO-21110___
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| http://linked.open...avai/riv/aktivita
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| http://linked.open...avai/riv/aktivity
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| http://linked.open...vai/riv/dodaniDat
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| http://linked.open...aciTvurceVysledku
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| http://linked.open.../riv/druhVysledku
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| http://linked.open...iv/duvernostUdaju
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| http://linked.open...titaPredkladatele
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| http://linked.open...dnocenehoVysledku
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| http://linked.open...ai/riv/idVysledku
| - RIV/68407700:21110/13:00210816
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| http://linked.open...riv/jazykVysledku
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| http://linked.open.../riv/klicovaSlova
| - deep radioactive waste repository; buffer; gap filling; bentonite (en)
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| http://linked.open.../riv/klicoveSlovo
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| http://linked.open...ontrolniKodProRIV
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| http://linked.open...v/mistoKonaniAkce
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| http://linked.open...i/riv/mistoVydani
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| http://linked.open...i/riv/nazevZdroje
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| http://linked.open...in/vavai/riv/obor
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| http://linked.open...ichTvurcuVysledku
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| http://linked.open...cetTvurcuVysledku
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| http://linked.open...vavai/riv/projekt
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| http://linked.open...UplatneniVysledku
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| http://linked.open...iv/tvurceVysledku
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| http://linked.open...vavai/riv/typAkce
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| http://linked.open.../riv/zahajeniAkce
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| number of pages
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| http://purl.org/ne...btex#hasPublisher
| - Nuclear Society of Slovenia
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| https://schema.org/isbn
| |
| http://localhost/t...ganizacniJednotka
| |
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