REVIEW article

Front. Nucl. Eng.

Sec. Radioactive Waste Management

Volume 4 - 2025 | doi: 10.3389/fnuen.2025.1436087

This article is part of the Research TopicEURAD: State of the Art in Research and Development on Radioactive Waste Management and DisposalView all 7 articles

State of the art on thermo-hydro-mechanical behaviour of clay buffers at high temperature

Provisionally accepted
María Victoria  VillarMaría Victoria Villar1*Katerina  CernochovaKaterina Cernochova2Jaime  CuevasJaime Cuevas3Antonio  GensAntonio Gens4Natalia  GimenoNatalia Gimeno1Caroline  GrahamCaroline Graham5Jon  HarringtonJon Harrington5Vlastislav  KasparVlastislav Kaspar6Stephan  KaufholdStephan Kaufhold7Olivier  LeupinOlivier Leupin8David  MašínDavid Mašín9Jan  NajserJan Najser9Markus  OlinMarkus Olin10Heini  ReijonenHeini Reijonen11Šárka  ŠachlováŠárka Šachlová6Sergey  SayenkoSergey Sayenko12Daniel  SvenssonDaniel Svensson13Jiri  SvobodaJiri Svoboda2Gianni  VetteseGianni Vettese14Janne  YliharjuJanne Yliharju15Borys  ZlobenkoBorys Zlobenko16
  • 1Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas, Madrid, Spain
  • 2Czech Technical University in Prague, Prague 6, Prague, Czechia
  • 3Universidad Autónoma de Madrid, Madrid, Spain
  • 4Universitat Politecnica de Catalunya, Barcelona, Catalonia, Spain
  • 5British Geological Survey, Nottingham, United Kingdom
  • 6ÚJV Rež, a. s., Husinec, Czechia
  • 7Federal Institute For Geosciences and Natural Resources, Hanover, Lower Saxony, Germany
  • 8National Cooperative for the Disposal of Radioactive Waste (NAGRA), Wettingen, Aargau, Switzerland
  • 9Charles University, Prague, Prague, Czechia
  • 10VTT Technical Research Centre of Finland Ltd, Espoo, Uusimaa, Finland
  • 11Geological Survey of Finland, Espoo, Uusimaa, Finland
  • 12Kharkov Institute of Physics and Technology, Kharkiv, Kharkiv Oblast, Ukraine
  • 13Swedish Nuclear Fuel and Waste Management, Stockholm, Stockholm, Sweden
  • 14University of Helsinki, Helsinki, Uusimaa, Finland
  • 15University of Jyväskylä, Jyväskylä, Central Finland, Finland
  • 16Institute of Environmental Geochemistry of National Academy of Sciences of Ukraine, Kyiv, Ukraine

The final, formatted version of the article will be published soon.

Most safety cases for radioactive waste disposal concepts consider a temperature limit of 100°C for the clay buffer. Given that being able to tolerate higher temperature would have significant advantages, the work package HITEC of the EURAD project aimed at determining the influence of temperature above 100°C on buffer properties, trying to establish if the safety functions are unacceptably impaired. A synthesis of the state of knowledge on the thermo-hydro-mechanical and chemical behaviour of different buffer materials at different temperatures is presented, along with the progress made in this area during HITEC. The change of properties of preheated material and the hydro-mechanical properties of the bentonite at high temperatures were assessed.To cover the first instance, bentonite was heated at 150°C in dry and wet conditions for different periods of time up to 2 years. Clay mineralogy was remarkably preserved. The slight changes observed in other properties were opposite depending on the heating conditions: if evaporation was allowed, decreases in cation exchange capacity, specific surface area, sorption coefficients and sometimes swelling pressure were observed. The changes likely resulted from the strong drying induced by the elevated temperature. Bentonite was also subjected to hydration under thermal gradient in field and laboratory tests. No postmortem structural modifications of the smectite were observed, but dissolution and precipitation of species occurred, conditioned by the kind of bentonite and hydration water. These processes were accompanied by modification of the exchangeable cation complex.The determination of hydro-mechanical properties of expansive clay at elevated temperatures is challenging, with experimental and interpretation issues. In most cases a reduced swelling pressure was obtained when temperature increased, particularly for the higher dry densities. The results may be affected by the experimental protocols, the use of bentonite or purified smectite, and the exchangeable cations. Even at the highest temperatures the bentonite had the ability to fill voids and was able to develop large swelling pressures at high densities.Thermo-hydro-mechanical models were developed or upgraded during the project to include thermal phenomena and dependencies and were applied to the simulation of new laboratory thermo-hydraulic tests in cells.

Keywords: bentonite1, radioactive waste2, thermo-hydraulic behaviour3, swelling4, hydraulic conductivity5, buffer6, geochemistry7. (Min.5-Max. 8)

Received: 21 May 2024; Accepted: 22 May 2025.

Copyright: © 2025 Villar, Cernochova, Cuevas, Gens, Gimeno, Graham, Harrington, Kaspar, Kaufhold, Leupin, Mašín, Najser, Olin, Reijonen, Šachlová, Sayenko, Svensson, Svoboda, Vettese, Yliharju and Zlobenko. This is an open-access article distributed under the terms of the Creative Commons Attribution License (CC BY). The use, distribution or reproduction in other forums is permitted, provided the original author(s) or licensor are credited and that the original publication in this journal is cited, in accordance with accepted academic practice. No use, distribution or reproduction is permitted which does not comply with these terms.

* Correspondence: María Victoria Villar, Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas, Madrid, Spain

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