TY - CONF A1 - Linnemann, Konrad A1 - Quercetti, Thomas A1 - Ballheimer, Viktor A1 - Rolle, Annette A1 - Wille, Frank T1 - Experimental and numerical analyses of spent nuclear fuel behavior under transport conditions N2 - Packages for the transport of spent nuclear fuel shall meet the International Atomic Energy Agency regulations to ensure safety under different transport conditions. The physical state of the spent fuel and the fuel rod cladding as well as the geometric configuration of fuel assemblies are important inputs for the evaluation of the package capabilities under these conditions. The mechanical behavior of spent fuel assemblies shall be analyzed with regard to the assumptions which are used in the containment and criticality safety analysis. The package as a mechanical system is characterized by a complex set of interactions, e. g. between the fuel rods within the assembly as well as between the fuel assemblies, the basket, and the cask containment. This complexity makes it difficult to assume appropriate mechanical loads for the spent fuel inside the package. Another challenge is the assumption of material properties which represent the variation of the fuel rods regarding cladding material, burn-up and the operation history sufficiently. The objective of this paper is to give an overview about the current approaches and research for the evaluation of spent fuel behavior within the package design approval procedure. In this context, analytical, numerical and experimental results are discussed. The presented work is achieved within a collaboration of BAM with national and international partners. T2 - Abteilungskolloquium 3.3 CY - Berlin, BAM Fabeckstraße DA - 02.10.2019 KW - Transportbehälter KW - Radioaktive Stoffe KW - Brennelementverhalten KW - FE-Berechnungen PY - 2019 AN - OPUS4-51173 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -