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This paper describes the analytical, numerical and experimental investigations on the phenomenon of
interactions between cask components and content of packages for the transport of radioactive material during drop
tests required according to the IAEA Regulations for the Safe Transport of Radioactive Material.
Radial and axial gaps between cask components and content are usually necessary for thermal reasons but larger
gaps can exist because of the geometrical dimensions of the specified content. Consequently interactions between
content and cask components (lid system, cask body, etc.) are possible and can not be excluded during drop tests.
Interactions in this context are relative movements between cask and content which are mainly due to elastic spring
effects after releasing the cask for the free drop. These relative movements can cause interior collisions between
content and cask during the main impact of the package onto the unyielding target.
Drop tests with various types of Type A and Type B packages fully instrumented with strain gauges and
accelerometers showed that these interactions respectively interior collisions can be considerable relating to high forces
acting on cask lids, lid bolts and the content. Of course the real quantitative consequences of the interactions depend
upon different conditions, among others the drop orientation, the design characteristics of the impact limiters, the
dimensions of the gaps, the material characteristics of the contents, etc. .
In order to investigate more precisely the phenomenon of interactions BAM carried out finite element
calculations for the named casks using the ABAQUS/ Standard and ABAQUS/ Explicit computer code comparing them
with results obtained from experiments. Additionally, tests with a simplified model instrumented with accelerometers
were carried out accompanied by finite element calculations and analytical calculations using MATHEMATICA.
The investigations on the mentioned phenomena of interaction show that they should be considered in approval design
tests and/ or calculations.
Tests with different Type B casks confirm the existence of effects with stress peaks in cask components due to
interactions between the cask and its contents. These effects can be caused by a delayed strike of the content onto surrounding cask components which cannot be excluded if the content is movable. Some results of the drop tests with two different Type B casks and with a model designed for the study of this problem are presented in the paper. Results of calculations performed with the ABAQUS computer code and by use of analytical methods to simulate the measured effects are discussed.
Federal Institute for Materials Research and Testing (BAM) is the responsible authority for the
assessment of mechanical and thermal safety as well as quality issues within the licensing procedure
for transport casks for radioactive materials. The assessment includes a brittle fracture analysis of all
relevant cask components.
For cask bodies where a steel bottom is welded to a steel shell, specimens for testing of sufficient
fracture resistance can normally not be extracted directly from the welding seam area of the cask.
Therefore, a methodology has to be developed to ensure compliance with the safety analysis
considerations and the approved design specification. This paper describes such a methodology
including brittle fracture analysis and de-termination of required material properties as well as aspects
of quality assurance during manufacturing.
Transport packages for spent fuel have to meet the International Atomic Energy Agency requirements for different transport conditions. Physical state of spent fuel and fuel rod cladding as well as geometric configuration of fuel assemblies are important inputs for the evaluation of package capabilities under these conditions. In this paper, the mechanical behaviour of high burn-up spent fuel assemblies under transport conditions is analysed with regard to assumptions to be used in the activity release and criticality safety analysis. In particular the different failure modes of the fuel rods (fine cracks or complete breakage), which can cause release of gas, volatiles, fuel particles or fragments have to be properly considered in these assumptions. In view of the complexity of interactions between the fuel rods as well as between fuel assemblies, basket, and cask containment, the exact mechanical analysis of such phenomena is nearly impossible. The gaps in information concerning the material properties of cladding and pellets, especially for the high burn-up fuel, make the analysis more complicated additionally. In this context some practical approaches based on experiences of BAM Federal Institute for Material Research and Testing within safety assessment of packages for transport of spent fuel are discussed.
Methodological aspects for finite element modeling of lid systems for type B(U) transport packages
(2012)
The regulatory compliance of the containment system is of essential importance for the assessment
process of Type B(U) transport packages. The requirements of the IAEA safety standards for
transport conditions implies high loading on the containment system. The integrity of the
containment system has to be ensured in mechanical and thermal tests.
The containment system of German SNF and HLW transport packages usually includes bolted lids
with metal gaskets. The finite element (FE) method is recommended for the analysis of lid systems
according to the guideline BAM-GGR 012 for assessment of bolted lid and trunnion systems. FE
analyses provide more accurate and detailed information about loading and deformation of such
kind of structures. The results allow the strength assessment of the lid and bolts as well as the
evaluation of relative displacements between the lid and the cask body in the area of the gasket
groove.
This paper discusses aspects concerning FE simulation of lid systems for Type B(U) packages for
the transport of SNF and HLW. The work is based on the experiences of BAM Federal Institute for
Materials Research and Testing as the German competent authority for the mechanical design
assessment of such kind of packages. The issues considered include modeling strategies, analysis
techniques and the interpretation of results. A particular focus of this paper is on the evaluation of
the results with regard to FE accuracy, influence of the FE contact formulation and FE modeling
techniques to take the metallic gasket into account.