Structural integrity investigations of spent nuclear fuel with finite element modeling
Efstathios Vlassopoulos
CORRESPONDING AUTHOR
National Cooperative for the Disposal of Radioactive Waste, Wettingen, 5430, Switzerland
Susanne Pudollek
National Cooperative for the Disposal of Radioactive Waste, Wettingen, 5430, Switzerland
Olympios Alifieris
National Cooperative for the Disposal of Radioactive Waste, Wettingen, 5430, Switzerland
Dimitrios Papaioannou
III – Nuclear Decommissioning, Joint Research Centre, European Commission, Eggenstein-Leopoldshafen, 76344, Germany
Ramil Nasyrow
III – Nuclear Decommissioning, Joint Research Centre, European Commission, Eggenstein-Leopoldshafen, 76344, Germany
Ralf Gretter
III – Nuclear Decommissioning, Joint Research Centre, European Commission, Eggenstein-Leopoldshafen, 76344, Germany
Vincenzo V. Rondinella
III – Nuclear Decommissioning, Joint Research Centre, European Commission, Eggenstein-Leopoldshafen, 76344, Germany
Stefano Caruso
Kernkraftwerk Gösgen, Däniken, 4658, Switzerland
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Susanne Pudollek, Typhaine Guillemot, Xiaoshuo Li, and Valentyn Bykov
Saf. Nucl. Waste Disposal, 2, 97–97, https://doi.org/10.5194/sand-2-97-2023, https://doi.org/10.5194/sand-2-97-2023, 2023
Short summary
Short summary
Carbon-14 is an important, dose-determining contributing radionuclide in a deep geological repository for low- and intermediate-level radioactive waste. To derive a realistic and comprehensive assessment of the carbon-14 dose contribution a number of conservative assumptions within the modelling chain from model inventory description up to dose calculations have been reassessed and replaced by best-estimate approaches.
Madalina Wittel and Susanne Pudollek
Saf. Nucl. Waste Disposal, 1, 111–112, https://doi.org/10.5194/sand-1-111-2021, https://doi.org/10.5194/sand-1-111-2021, 2021