
94% of researchers rate our articles as excellent or good
Learn more about the work of our research integrity team to safeguard the quality of each article we publish.
Find out more
REVIEW article
Front. Nucl. Eng.
Sec. Radioactive Waste Management
Volume 4 - 2025 | doi: 10.3389/fnuen.2025.1436490
This article is part of the Research Topic EURAD: State of the Art in Research and Development on Radioactive Waste Management and Disposal View all 6 articles
The final, formatted version of the article will be published soon.
You have multiple emails registered with Frontiers:
Please enter your email address:
If you already have an account, please login
You don't have a Frontiers account ? You can register here
Most safety cases for radioactive waste disposal concepts consider a temperature limit of 90°C in the clay host rock. Being able to tolerate higher temperature would have significant advantages. For this reason, part of the EURAD-HITEC project aimed at determining the influence of temperature above 90°C on clay host rock properties, trying to establish the possible extent of elevated temperature damage in the near and far field of clay host rock formations and the consequences of any such damage. Three clay formations considered to host radioactive waste repositories in Europe were the focus of the studies: the Boom Clay, the Callovo-Oxfordian claystone and the Opalinus Clay. A summary of the background knowledge about the thermo-hydro-mechanical behaviour of these clay host rocks is first presented. Then, the experimental and modelling activities carried out in the framework of the EURAD-HITEC project concerning these materials have been synthesised.The laboratory tests analysed the impact of temperature on the short-and long-term behaviour of the clay host rock and the self-sealing processes. Hydro-mechanical couplings between peak pore water pressure, temperature, permeability and confining stress were identified. The results confirmed that the claystone keeps its good mechanical and retention properties even when heated up to 100°C. Provided that the clay content of the samples is high enough, self-sealing was an efficient mechanism whatever the experimental conditions, although temperature may have a delaying effect.Poro-elastic models were used to model generic cases of a high-level waste repository, and consistent results were obtained by the different codes and teams, which shows the robustness of the modelling approach used to design the repositories. Two heating tests, performed in the HADES (Belgium) and MHM (France) underground research laboratories, were selected as benchmarks for the modelling activities. The evolutions of temperature and pore pressure were well modelled in the far field with a poro-elastic approach, but more advanced models are needed to take into account the processes occurring around the tunnels (e.g. modification of hydraulic properties within the EDZ, creep). The modelling of laboratory experiments showed the importance of a good understanding of the tests setup and of the boundary conditions.
Keywords: Claystone, Radioactive Waste, Thermo-hydraulic behaviour, creep, hydraulic conductivity, temperature, numerical modelling, anisotropy. (Min.5-Max. 8)
Received: 22 May 2024; Accepted: 20 Feb 2025.
Copyright: © 2025 Villar, Bésuelle, Collin, Cuss, de Lesquen, Dizier, El Tabbal, Gens, Graham, Grgic, Harrington, Imbert, Leupin, Levasseur, Narkūnienė, Simo and Tatomir. 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
Christophe de Lesquen, Agence Nationale Pour la Gestion des Déchets Radioactifs, Châtenay-Malabry, Île-de-France, France
Arnaud Dizier, European Underground Research Infrastructure for Disposal of nuclear waste in a Clay Environment, Mol, Belgium
Dragan Grgic, Université de Lorraine, Nancy, 54000, Lorraine, France
Disclaimer: All claims expressed in this article are solely those of the authors and do not necessarily represent those of their affiliated organizations, or those of the publisher, the editors and the reviewers. Any product that may be evaluated in this article or claim that may be made by its manufacturer is not guaranteed or endorsed by the publisher.
Research integrity at Frontiers
Learn more about the work of our research integrity team to safeguard the quality of each article we publish.