Radiological characterization of a German pressurized water reactor based on a highly resolved method for activity analysis and dose rate calculation
Markus Nolden
CORRESPONDING AUTHOR
Chair of Repository Safety (ELS), RWTH Aachen University, Aachen, 52062, Germany
Agnes Scaramus
CORRESPONDING AUTHOR
Chair of Repository Safety (ELS), RWTH Aachen University, Aachen, 52062, Germany
Rahim Nabbi
Chair of Repository Safety (ELS), RWTH Aachen University, Aachen, 52062, Germany
Frank Charlier
Chair of Repository Safety (ELS), RWTH Aachen University, Aachen, 52062, Germany
Klaus Fischer-Appelt
Chair of Repository Safety (ELS), RWTH Aachen University, Aachen, 52062, Germany
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Marc Johnen, Judith Flügge, Jens Wolf, Klaus Fischer-Appelt, and Frank Charlier
Saf. Nucl. Waste Disposal, 2, 87–87, https://doi.org/10.5194/sand-2-87-2023, https://doi.org/10.5194/sand-2-87-2023, 2023
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Due to the long half-lives of the radionuclides contained in waste, a repository for high-level radioactive waste must safely contain them for long timescales, which include geological and climatic changes. For this reason, numerical groundwater models are developed in this work considering various climate processes and influences in relation to repository safety. Glaciers, permafrost, erosion, and sea level fluctuations will be considered and related to the geological situation in Germany.
Kurt Diedrich, Klaus Fischer-Appelt, and Frank Charlier
Saf. Nucl. Waste Disposal, 2, 169–170, https://doi.org/10.5194/sand-2-169-2023, https://doi.org/10.5194/sand-2-169-2023, 2023
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In the research project presented here, the use of multiple-criterion decision analysis (MCDA) in the German site-selection procedure is discussed. The aim is to explore the applicability for the decision problem to the emplacement concept of high-level radioactive waste (HLW) packages regarding German safety investigations. The expected outcome is a basic decision model that can provide decision support and increase transparency, understanding, and acceptance in the site-selection procedure.
Christoph G. Gärtner, Klaus Fischer-Appelt, and Frank Charlier
Saf. Nucl. Waste Disposal, 2, 85–86, https://doi.org/10.5194/sand-2-85-2023, https://doi.org/10.5194/sand-2-85-2023, 2023
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Crystalline rock is a potential candidate for storing nuclear waste in the deep geological underground in Germany. However, fractures within these rocks pose a challenge, as they can create pathways for fluids that might corrode barriers and release radioactive materials into the environment. The exact configuration of these fracture networks is often unknown. Our study aims to better understand and predict these networks by combining existing data with advanced modelling techniques.
Hajar El Fatihi, Klaus Fischer-Appelt, and Frank Charlier
Saf. Nucl. Waste Disposal, 2, 133–134, https://doi.org/10.5194/sand-2-133-2023, https://doi.org/10.5194/sand-2-133-2023, 2023
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Based on the German site selection process for a deep geological repository for high-level radioactive waste, we propose a site-prioritization method based on a multi-criteria decision-making approach and risk estimates for each sub-region. The method takes into account the geological factors as well as the uncertainty associated with the heterogeneous nature of subsurface data quality and quantity, in order to enable stakeholders to make informed decisions during the site selection process.
Gerd Frieling, Klaus Fischer-Appelt, Ute Maurer-Rurack, Thomas Beuth, and Guido Bracke
Saf. Nucl. Waste Disposal, 1, 35–36, https://doi.org/10.5194/sand-1-35-2021, https://doi.org/10.5194/sand-1-35-2021, 2021
Neslihan Yanikömer, Rahim Nabbi, and Klaus Fischer-Appelt
Saf. Nucl. Waste Disposal, 1, 17–18, https://doi.org/10.5194/sand-1-17-2021, https://doi.org/10.5194/sand-1-17-2021, 2021
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Since the requirement of the proof of safety to up to 100 years arises, integrity of the spent fuel elements in prolonged interim storage and long-term repository is getting more critical issue. In response to this safety matter, we developed and applied a multiscale simulation methodology to assess the impact of the radiation induced microstructures on mechanical properties of the spent fuel elements to provide reliable structural performance limits and safety margin respectively.