Cleall, Peter John ORCID: https://orcid.org/0000-0002-4005-5319, Melhuish, Troy Alexander and Thomas, Hywel Rhys ORCID: https://orcid.org/0000-0002-3951-0409 2006. Modelling the three-dimensional behaviour of a prototype nuclear waste repository. Engineering Geology 85 (1-2) , pp. 212-220. 10.1016/j.enggeo.2005.09.045 |
Abstract
This paper presents a study of the full three-dimensional thermo/hydro/mechanical behaviour of SKB's Prototype Repository experiment. In particular, the three-dimensional interaction of the multiple barrier system, which includes MX-80 bentonite buffer with the host rock is investigated. These materials are subjected to a steep thermal gradient representing the heat produced by highlevel nuclear waste. A hydraulic gradient is also present due to the host rock acting as a source of water. The simulation is achieved via the application of the numerical code, COMPASS, which implements a coupled thermo/hydro/mechanical approach to model the behaviour of saturated/unsaturated media. These patterns of behaviour require a large three-dimensional model in order to represent the non-symmetrical, complex geometry of the proposed repository. A range of simulation results is presented detailing the thermal–hydraulic–mechanical behaviour of the Prototypeinteraction occurring Repository. Attention has also been given to the micro–macro interaction occurring within the MX-80 bentonite buffer as the material begins to saturate and swell
Item Type: | Article |
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Date Type: | Publication |
Status: | Published |
Schools: | Engineering |
Subjects: | T Technology > TA Engineering (General). Civil engineering (General) |
Uncontrolled Keywords: | numerical modelling ; large scale test ; bentonite ; nuclear waste repository ; coupled flow |
Publisher: | Elsevier |
ISSN: | 00137952 |
Last Modified: | 17 Oct 2022 09:05 |
URI: | https://orca.cardiff.ac.uk/id/eprint/2020 |
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