TY - CONF A1 - Müller, Karsten A1 - Ballheimer, Viktor A1 - Droste, Bernhard A1 - Rödel, Roland A1 - Völzke, Holger A1 - Zencker, Uwe T1 - Die Anwendung der Bruchmechanik im Sicherheitsnachweis von Transportbehältern für die Beförderung radioaktiver Stoffe T2 - 36. Tagung des DVM-Arbeitskreises Bruchvorgänge CY - Köln, Deutschland DA - 2004-02-17 KW - Gusseisen mit Kugelgraphit KW - Bruchmechanischer Sicherheitsnachweis KW - Stoßbeanspruchung KW - Transportbehälter KW - Radioaktive Stoffe KW - Ductile iron KW - Fracture mechanics safety assessment KW - Mechanical impact KW - Transport casks KW - Radioactive material PY - 2004 SN - 0943-3473 IS - 236 SP - 225 EP - 238 PB - DVM CY - Berlin AN - OPUS4-5336 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Wolff, Dietmar A1 - Droste, Bernhard A1 - Völzke, Holger A1 - Baden, M. T1 - German approach and experience feedback of transport ability of SNF packages after interim storage N2 - In Germany the concept of dry interim storage of spent fuel in dual purpose metal casks is implemented, currently for periods of up to 40 years. The casks being used have an approved package design in accordance with the international transport regulations. The license for dry storage is granted on the German Atomic Energy Act with respect to the recently revised “Guidelines for dry interim storage of irradiated fuel assemblies and heat-generating radioactive waste in casks” by the German Waste management Commission (ESK). For transport on public routes between or after long term interim storage periods, it has to be ensured that the transport and storage casks fulfil the specifications of the transport approval or other sufficient properties which satisfy the proofs for the compliance of the safety objectives at that time. In recent years the validation period of transport approval certificates for manufactured, loaded and stored packages were discussed among authorities and applicants. A case dependant system of 3, 5 and 10 years was established. There are consequences for the safety cases in the Package Design Safety Report including evaluation of long term behavior of components and specific operating procedures of the package. Present research and knowledge concerning the long term behavior of transport and storage cask components have to be consulted as well as experiences from interim cask storage operations. Challenges in the safety assessment are e.g. the behavior of aged metal and elastomeric gaskets under IAEA test conditions to ensure that the results of drop tests can be transferred to the compliance of the safety objectives at the time of transport after the interim storage period. T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 18.08.2013 KW - Storage KW - Transport KW - Lagerung KW - Verpackung KW - Radioactive material PY - 2013 SP - 1 EP - 9 PB - Omnipress AN - OPUS4-30159 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -