Abstract
Radioactive waste disposal, as the final step of the open nuclear fuel cycle, is an important process to protect humans and the environment from harmful effects of ionising radiation. Approaching the construction of the geological repository, the understanding and predictability of the behavior of engineered barrier material becomes more important than ever. Therefore, a number of research studies are being focused on the experimental and numerical analysis of the engineered barrier material state and behavior under repository conditions. Engineered barrier material will be in contact with the host rock and waste packages, and its properties and behavior will be governed by complex and coupled thermo-hydro-mechanical processes. This paper presents the modeling activities of the Lithuanian Energy Institute, performed in the framework of the H2020 project BEACON (Bentonite Mechanical Evolution). The numerical model, developed in COMSOL Multiphysics (Burlington, MA 01803, USA), was applied for the modeling of experiments, performed by Ecole Polytechnique Federale de Lausanne (EPFL, Switzerland), on granular MX-80 bentonite in the odeometer cell. The hydromechanical behavior of a compacted bentonite sample was analyzed under different conditions: hydration with groundwater under confined volume conditions and hydration under free swelling conditions and subsequent mechanical loading. Model outcomes (swelling pressure, saturation, dry density, and void ratio) were compared to the available experimental data. The modeling results were in line with the analyzed experimental data.
Subject
Geology,Geotechnical Engineering and Engineering Geology
Reference44 articles.
1. Licence Granted for Finnish Used Fuel Repositoryhttps://www.world-nuclear-news.org/WR-Licence-granted-for-Finnish-used-fuel-repository-1211155.html
2. Posiva Submits Application for Operating Licence for Encapsulation and Final Disposal Facility of Spent Nuclear Fuelhttps://www.posivasolutions.com/news/pressreleasesstockexchangereleases/2021/posivasubmitsapplicationforoperatinglicenceforencapsulationandfinaldisposalfacilityofspentnuclearfuel.html
3. Disposal of Radioactive Waste,2011
4. Safety Functions, Performance Targets and Technical Design Requirements for a KBS-3V Repository,2017
5. Definition of System Requirements for KBS-3H Deposition of Spent Nuclear Fuel,2003
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