State of compacted mx-80 bentonite after simulation of thermo-hydraulic conditions in deep geological storage

Roberto Gómez-Espina, María Victoria Villar

Resultado de la investigación: Contribución a una revistaArtículorevisión exhaustiva

Resumen

These studies were developed in the framework of high-level nuclear waste (HLW) disposal in deep geological formations, in which the waste is protected by a group of geological and engineering barriers. In many disposal concepts, one of those engineering barriers is formed by compacted bentonite blocks. Bentonite was chosen as sealing material because of its expansive capacity, low permeability and high plasticity. The conditions of the bentonite in an engineered barrier for HLW disposal have been simulated in a laboratory test, using a 20-cm long cylindrical block of MX-80 clay that was heated and hydrated for 496 days. This bentonite is from Wyoming (USA), and has been selected in many disposal concepts as backfilling and sealing material (Sweden, Finland, Germany, France). This paper summarises some results obtained after the test was dismantled. The dry density and water content were measured in sections along the column. Also, soluble salts content, exchangeable cations and the cation exchange complex of the smectite were determined in the same sections.

Idioma originalInglés
Páginas (desde-hasta)289-294
Número de páginas6
PublicaciónMaterials Research Society Symposium Proceedings
Volumen1124
EstadoPublicada - 2009

Áreas temáticas de ASJC Scopus

  • Ingeniería mecánica
  • Mecánica de materiales
  • Ciencia de los materiales (todo)
  • Física de la materia condensada

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