Compaction of crushed salt for safe containment – a summary of the KOMPASS projects
Larissa Friedenberg
CORRESPONDING AUTHOR
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH,
38122 Braunschweig, Germany
Jeroen Bartol
COVRA, 4455 TW Nieuwdorp, the Netherlands
James Bean
Sandia National Laboratories, Albuquerque, New Mexico 87123, USA
Steffen Beese
Federal Institute for Geosciences and Natural Resources, 30655 Hanover, Germany
Hendrik Bollmann
Chair for geomechanics and multiphysics Systems, Clausthal University of Technology, 38678 Clausthal-Zellerfeld,
Germany
Hans J. P. de Bresser
Department of Earth Sciences, Utrecht University, 3584 CS Utrecht, the Netherlands
Jibril Coulibaly
Sandia National Laboratories, Albuquerque, New Mexico 87123, USA
Oliver Czaikowski
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH,
38122 Braunschweig, Germany
Uwe Düsterloh
Chair for geomechanics and multiphysics Systems, Clausthal University of Technology, 38678 Clausthal-Zellerfeld,
Germany
Ralf Eickemeier
Federal Institute for Geosciences and Natural Resources, 30655 Hanover, Germany
Ann-Kathrin Gartzke
Federal Institute for Geosciences and Natural Resources, 30655 Hanover, Germany
Suzanne Hangx
Department of Earth Sciences, Utrecht University, 3584 CS Utrecht, the Netherlands
Ben Laurich
Federal Institute for Geosciences and Natural Resources, 30655 Hanover, Germany
Christian Lerch
BGE TECHNOLOGY GmbH, 31224 Peine, Germany
Svetlana Lerche
Chair for geomechanics and multiphysics Systems, Clausthal University of Technology, 38678 Clausthal-Zellerfeld,
Germany
Wenting Liu
Federal Institute for Geosciences and Natural Resources, 30655 Hanover, Germany
Christoph Lüdeling
Institut für Gebirgsmechanik GmbH, 04109 Leipzig, Germany
Melissa M. Mills
Sandia National Laboratories, Albuquerque, New Mexico 87123, USA
Nina Müller-Hoeppe
BGE TECHNOLOGY GmbH, 31224 Peine, Germany
Bart van Oosterhout
Department of Earth Sciences, Utrecht University, 3584 CS Utrecht, the Netherlands
Till Popp
Institut für Gebirgsmechanik GmbH, 04109 Leipzig, Germany
Ole Rabbel
Institut für Gebirgsmechanik GmbH, 04109 Leipzig, Germany
Michael Rahmig
BGE TECHNOLOGY GmbH, 31224 Peine, Germany
Benjamin Reedlunn
Sandia National Laboratories, Albuquerque, New Mexico 87123, USA
Christopher Rölke
Institut für Gebirgsmechanik GmbH, 04109 Leipzig, Germany
Christopher Spiers
Department of Earth Sciences, Utrecht University, 3584 CS Utrecht, the Netherlands
Kristoff Svensson
Federal Institute for Geosciences and Natural Resources, 30655 Hanover, Germany
Jan Thiedau
Federal Institute for Geosciences and Natural Resources, 30655 Hanover, Germany
Kornelia Zemke
Federal Institute for Geosciences and Natural Resources, 30655 Hanover, Germany
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Larissa Friedenberg, James Bean, Oliver Czaikowski, Uwe Düsterloh, Nina Müller-Hoeppe, Ben Laurich, Christian Lerch, Svetlana Lerche, Christoph Lüdeling, Melissa Mills, Till Popp, Benjamin Reedlunn, Dieter Stührenberg, Kristoff Svensson, Kornelia Zemke, and Juan Zhao
Saf. Nucl. Waste Disposal, 1, 121–123, https://doi.org/10.5194/sand-1-121-2021, https://doi.org/10.5194/sand-1-121-2021, 2021
Gesa Ziefle, Tuanny Cajuhi, Sebastian Condamin, Stephan Costabel, Oliver Czaikowski, Antoine Fourriére, Larissa Friedenberg, Markus Furche, Nico Graebling, Bastian Graupner, Jürgen Hesser, David Jaeggi, Kyra Jantschik, Tilo Kneuker, Olaf Kolditz, Franz Königer, Herbert Kunz, Ben Laurich, Jobst Maßmann, Christian Ostertag-Henning, Dorothee Rebscher, Karsten Rink, Wolfram Rühaak, Senecio Schefer, Rainer Schuhmann, Marc Wengler, and Klaus Wieczorek
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Svetlana Lerche and Uwe Düsterloh
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The planned use of crushed salt as the backfill and sealing material for the final disposal of radioactive waste in rock salt is justified by the favorable crushed salt material properties. A prognostic long-term safety assessment requires sufficiently proved physical modeling that can only be met on the basis of suitable laboratory and field investigations. To reduce the currently existing uncertainties, triaxial long-term compaction tests TUC-V2 and TUC-V4 (KOMPASS II) were carried out.
Thomas Nagel, Maximilian Bittens, Jörg Buchwald, Aqeel A. Chaudhry, Oliver G. Ernst, Werner Gräsle, Feliks Kiszkurno, Kata Kurgyis, Jobst Maßmann, Sibylle Mayr, Jan Thiedau, and Chao Zhang
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Computer simulations are used to understand processes in nuclear waste disposal. The results are used to judge the safety of waste repository. Not all the information needed for such analyses, e.g. rock properties, is precisely known, contributing to uncertainty in the analysis results. We are interested in understanding the effect of the uncertainty of input quantities and of certain simplifications made during model creation on the outcome of computer simulations.
Max Friedel, Fabian Weber, Heinz Konietzky, Paola Rocio León Vargas, Alireza Hassanzadegan, and Michael Rahmig
Saf. Nucl. Waste Disposal, 2, 63–63, https://doi.org/10.5194/sand-2-63-2023, https://doi.org/10.5194/sand-2-63-2023, 2023
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As part of BARIK, a laboratory programme is used to generate a dataset for anisotropic material to verify and validate the developed constitutive model. Based on
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Matthias Hinze, Klaus Wieczorek, Katja Emmerich, Jürgen Hesser, Markus Furche, Hua Shao, David Jaeggi, Senecio Schefer, Thomas Nagel, Juan Carlos Mayor, Simon Norris, Kim Chang-Seok, Philipp Schädle, José Luis García-Siñeriz, Rainer Schuhmann, Franz Königer, Uwe Glaubach, Christopher Rölke, and Ralf Diedel
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The SW-A experiment is a large-scale in situ test at the Mont Terri rock laboratory that implements a vertical hydraulic shaft-sealing system in argillaceous host rock. The response of the system and the surrounding rock to hydration is examined. The experiment objectives are to demonstrate the feasibility of installation, to investigate the saturation process, to qualify measurement and monitoring techniques, and to assess the sealing effectiveness. Recent data and experience are presented.
Carlos Guevara Morel, Jobst Maßmann, and Jan Thiedau
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This contribution focuses on the numerical assesment of the barrier integrity of a generic nuclear repository in crytalline rock.
Jan Thiedau, Maximilian Bittens, Jobst Maßmann, and Sibylle Mayr
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The assessment of the integrity of the geological barrier for repositories for nuclear waste can be significantly influenced by uncertainties in the model inputs. Hence, the results of these established integrity analyses should be enriched by statistical information. In this contribution, we present preliminary probabilistic results for rock integrity assessment for the generic repository system in clay rock and the developed tools for stochastic analyses.
Rocio Paola León Vargas, Max Friedel, Alireza Hassanzadegan, Michael Rahmig, Fabian Weber, and Heinz Konietzky
Saf. Nucl. Waste Disposal, 2, 119–120, https://doi.org/10.5194/sand-2-119-2023, https://doi.org/10.5194/sand-2-119-2023, 2023
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This contribution gives an overview of how the BARIK constitutive model was developed and tested. BARIK is an extended Hoek–Brown model for fractured crystalline rock that takes up to three fracture systems into account. It gives a numerical value to qualitative integrity criteria to show that the containment-providing rock zone in crystalline host rock is still intact. The BARIK model is a step forward in understanding and modeling the complex behavior of fractured crystalline hard rock.
Carlos Guevara Morel, Jobst Maßmann, and Jan Thiedau
Saf. Nucl. Waste Disposal, 1, 173–174, https://doi.org/10.5194/sand-1-173-2021, https://doi.org/10.5194/sand-1-173-2021, 2021
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Saf. Nucl. Waste Disposal, 1, 121–123, https://doi.org/10.5194/sand-1-121-2021, https://doi.org/10.5194/sand-1-121-2021, 2021
Kornelia Zemke, Kristoff Svensson, Ben Laurich, and Johanna Lippmann-Pipke
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Christoph Lüdeling, Dirk Naumann, and Wolfgang Minkley
Saf. Nucl. Waste Disposal, 1, 95–97, https://doi.org/10.5194/sand-1-95-2021, https://doi.org/10.5194/sand-1-95-2021, 2021
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Kristoff Svensson, Kornelia Zemke, and Ben Laurich
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Ben Laurich
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Elisenda Bakker and Johannes H. P. de Bresser
Solid Earth Discuss., https://doi.org/10.5194/se-2020-178, https://doi.org/10.5194/se-2020-178, 2020
Publication in SE not foreseen
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Ernst-Jan N. Kuiper, Johannes H. P. de Bresser, Martyn R. Drury, Jan Eichler, Gill M. Pennock, and Ilka Weikusat
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Ben Laurich, Janos L. Urai, Christian Vollmer, and Christophe Nussbaum
Solid Earth, 9, 1–24, https://doi.org/10.5194/se-9-1-2018, https://doi.org/10.5194/se-9-1-2018, 2018
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In Switzerland, the Opalinus Clay (OPA) formation is favored to host a repository for nuclear waste. Thus, we must know its deformation behavior. In this study, we focused on the microstructure of gouge, a thin (< 2 cm), drastically strained clay layer at the so-called Main Fault in the Mont Terri rock laboratory. We suggest that in situ gouge deforms in a more viscous manner than undeformed OPA in laboratory conditions. Moreover, we speculate about the origin and evolution of the gouge layer.
Ben Laurich, Janos L. Urai, and Christophe Nussbaum
Solid Earth, 8, 27–44, https://doi.org/10.5194/se-8-27-2017, https://doi.org/10.5194/se-8-27-2017, 2017
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Scaly clay is a well-known rock fabric that can develop in tectonic systems and that can alter the physical rock properties of a formation. However, the internal microstructure and evolution of this fabric remain poorly understood. We examined the scaly microstructure of progressively faulted Opalinus Clay using optical as well as scanning electron microscopy. We show that as little as 1 vol.% in scaly clay aggregates is strained and present an evolutionary model for this.
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For the deep geological disposal of high-level nuclear waste in rock salt formations, the safety concept includes the backfilling of open cavities with crushed salt. For the prognosis of the sealing function of the backfill for the safe containment of the nuclear waste, it is crucial to have a comprehensive process understanding of the crushed-salt compaction behavior. The KOMPASS projects were initiated to improve the scientific knowledge of using crushed salt as backfill material.
For the deep geological disposal of high-level nuclear waste in rock salt formations, the safety...