Conference Abstract
| 
10 Nov 2021
Conference Abstract |
| 10 Nov 2021
| 10 Nov 2021
Twenty years of research on spent nuclear fuel in the context of final disposal at KIT-INE in multinational collaborative projects
Institute for Nuclear Waste Disposal (INE), Karlsruhe Institute of Technology (KIT), P.O. Box 3640, 76021 Karlsruhe, Germany
Elke Bohnert
Institute for Nuclear Waste Disposal (INE), Karlsruhe Institute of Technology (KIT), P.O. Box 3640, 76021 Karlsruhe, Germany
Luis Iglesias Pérez
Institute for Nuclear Waste Disposal (INE), Karlsruhe Institute of Technology (KIT), P.O. Box 3640, 76021 Karlsruhe, Germany
Tobias König
Institute for Nuclear Waste Disposal (INE), Karlsruhe Institute of Technology (KIT), P.O. Box 3640, 76021 Karlsruhe, Germany
Volker Metz
Institute for Nuclear Waste Disposal (INE), Karlsruhe Institute of Technology (KIT), P.O. Box 3640, 76021 Karlsruhe, Germany
Arndt Walschburger
Institute for Nuclear Waste Disposal (INE), Karlsruhe Institute of Technology (KIT), P.O. Box 3640, 76021 Karlsruhe, Germany
Horst Geckeis
Institute for Nuclear Waste Disposal (INE), Karlsruhe Institute of Technology (KIT), P.O. Box 3640, 76021 Karlsruhe, Germany
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Our contribution focuses on the release of fission gases during the dissolution process of two different types of spent nuclear fuel, i.e. UOX and (U, Pu)OX mixed-oxide fuels, in order to identify and quantify the role of fission gas release rates as an indicator of radionuclide source terms. Within our work, it is shown that, independent of the type of spent nuclear fuel, a comparable, fast initial release of fission gases is evident in all experiments.
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Stainless steel was exposed to highly saline brines under anoxic and elevated temperature conditions. Samples were analyzed by various techniques in order to identify the nature of the secondary phases present in the corrosion layer forming at the steel–brine interface. Outcomes suggest that the corrosion layer has duplex structure, with an inner layer mostly of chromium (hydr)oxides and an outer layer made of iron- and nickel-based spinel compounds with admixed nickel (hydr)oxides.
Tobias König, Elke Bohnert, Ernesto González-Robles, Michel Herm, Luis Iglesias-Pérez, Volker Metz, Arndt Walschburger, and Horst Geckeis
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Our contribution focuses on the release of fission gases during the dissolution process of two different types of spent nuclear fuel, i.e. UOX and (U, Pu)OX mixed-oxide fuels, in order to identify and quantify the role of fission gas release rates as an indicator of radionuclide source terms. Within our work, it is shown that, independent of the type of spent nuclear fuel, a comparable, fast initial release of fission gases is evident in all experiments.
Michel Herm, Arndt Walschburger, Tobias König, Volker Metz, and Horst Geckeis
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This paper presents an experimental investigation of uranium release from spent nuclear fuels under conditions expected in a deep geological repository.
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The Repository Site Selection Act explicitly emphasises that targeting the disposal of high-level radioactive waste is a so-called learning process. We are of the opinion that the procedure and the available data should be combined with geoscientific knowledge to support the identification of siting regions. We propose this workshop and invite all experts who have dealt with the search for a repository site from a geoscientific perspective.
Tobias König, Ron Dagan, Kathy Dardenne, Michel Herm, Volker Metz, Tim Pruessmann, Jörg Rothe, Dieter Schild, Arndt Walschburger, and Horst Geckeis
Saf. Nucl. Waste Disposal, 1, 5–6, https://doi.org/10.5194/sand-1-5-2021, https://doi.org/10.5194/sand-1-5-2021, 2021
Mara Marchetti, Michel Herm, Tobias König, Simone Manenti, and Volker Metz
Saf. Nucl. Waste Disposal, 1, 7–8, https://doi.org/10.5194/sand-1-7-2021, https://doi.org/10.5194/sand-1-7-2021, 2021
M. Carme Chaparro, Nicolas Finck, Volker Metz, and Horst Geckeis
Saf. Nucl. Waste Disposal, 1, 169–170, https://doi.org/10.5194/sand-1-169-2021, https://doi.org/10.5194/sand-1-169-2021, 2021
Nikoleta Morelová, Kathy Dardenne, Nicolas Finck, Frank Heberling, Volker Metz, Dieter Schild, Horst Geckeis, and Nikitas Diomidis
Saf. Nucl. Waste Disposal, 1, 103–104, https://doi.org/10.5194/sand-1-103-2021, https://doi.org/10.5194/sand-1-103-2021, 2021
Xavier Gaona, Marcus Altmaier, Iuliia Androniuk, Nese Çevirim-Papaioannou, Michel Herm, Luis Iglesias-Perez, Yongheum Jo, Volker Metz, Andrej Skerencak-Frech, Agost Tasi, and Horst Geckeis
Saf. Nucl. Waste Disposal, 1, 151–152, https://doi.org/10.5194/sand-1-151-2021, https://doi.org/10.5194/sand-1-151-2021, 2021
Daniel Glückman, Karin Hain, Claudia Joseph, Volker Metz, Francesca Quinto, Peter Steier, and Horst Geckeis
Saf. Nucl. Waste Disposal, 1, 153–154, https://doi.org/10.5194/sand-1-153-2021, https://doi.org/10.5194/sand-1-153-2021, 2021
Dirk Bosbach, Horst Geckeis, Frank Heberling, Olaf Kolditz, Michael Kühn, Katharina Müller, Thorsten Stumpf, and the iCROSS team
Saf. Nucl. Waste Disposal, 1, 85–87, https://doi.org/10.5194/sand-1-85-2021, https://doi.org/10.5194/sand-1-85-2021, 2021
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The present contribution provides an overview on the collaborative project iCROSS and reports selected results. The impact of considering complex coupled processes in repository subsystems for the assessment of the integrity of a given (generic) repository arrangement will be discussed. The interdisciplinary team combines experimental work in the lab, in the underground rock laboratory and environmental simulations in order to achieve process understanding across variable scales.
David Fellhauer, Xavier Gaona, Marcus Altmaier, and Horst Geckeis
Saf. Nucl. Waste Disposal, 1, 149–150, https://doi.org/10.5194/sand-1-149-2021, https://doi.org/10.5194/sand-1-149-2021, 2021
Andrej Skerencak-Frech, Petra Panak, Kathy Dardenne, Jörg Rothe, Xavier Gaona, Marcus Altmaier, and Horst Geckeis
Saf. Nucl. Waste Disposal, 1, 159–160, https://doi.org/10.5194/sand-1-159-2021, https://doi.org/10.5194/sand-1-159-2021, 2021
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An overview on the recent advances in the field of high temperature studies of radionuclides in aqueous solutions will be given. Besides summarizing information on key technical aspects relevant for high temperature studies, the effect of increased temperatures on the complexation of trivalent actinides with chloride will be discussed in more detail, to illustrate newly derived in-depth understanding of the impact of increased temperatures on the (geo)chemical behaviour of trivalent actinides.
Cited articles
Ewing, R. C.: Long-term storage of spent nuclear fuel, Nature Materials, 14, 252–257, https://doi.org/10.1038/nmat4226, 2015.
