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BAM is the responsible authority in Germany for the assessment of the mechanical and thermal design safety of packages for the transport of radioactive materials. The assessment has to cover the proof of brittle fracture safety for package components made of potentially brittle materials. This paper gives a survey of the regulatory and technical requirements for such an assessment according to BAM's new 'Guidelines for the application of ductile cast iron for transport and storage casks for radioactive materials'. Based on these guidelines, higher stresses than before will be permissible, but it is necessary to put more effort into the safety assessment procedure. The fundamentals of such a proof using the methods of fracture mechanics are presented. The recommended procedure takes into account the guidelines of the IAEA's advisory material which are based on the prevention of crack initiation. Examples of BAM's research and safety assessment practices are given. Recommendations for further developments towards package designs with higher acceptable stress levels will conclude the paper.
In the present study, ductile cast iron from an original DCI container with a wide variety of microstructure was
investigated in order to determine the materials fracture toughness under impact loading conditions. Three-point bending
specimens with thickness of 140 mm from a cubic DCI container were investigated at elevated loading rates to
provide reliable fracture toughness parameters for the assessment procedures. In contrast to static fracture behaviour,
the fracture toughness values of thick-walled DCI at higher loading rates show a remarkable reduction with decreasing
temperature up to 50 °C and a significant shift of the transition range. The lower bound fracture toughness value used
in the BAM DCI safety concept was confirmed for impact loading conditions by these fracture mechanics tests using
large specimens. These measurements are relevant to the licensing tests for storage containers without shock absorbers,
especially to the assessment of the dynamic behaviour of crack-like defects inside a cask structure under drop test conditions.
Using extensive dynamic numerical analyses it could be shown, that for special crack configurations the dynamic
crack tip parameter (KI, or J) may be estimated by static formulae even under mechanical impact. These results
of the safety assessment were verified according to the German Konrad repository acceptance criteria by a drop test
with a cubic waste container with artificial crack-like defects from 5 m height onto a representative storage facility
foundation.
Mechanical design assessment approaches of actual spent fuel and HLW transport package designs
(2010)
Mechanical design assessment approaches of actual spent fuel and HLW transport package designs
(2010)
Auswirkungen von Ermüdungsbeanspruchungen auf Struktur und Eigenschaften von Fahrbahndeckenbeton
(2015)
Ausgehend von der Zielsetzung der DFG-Forschergruppe 1498, die Einflüsse auf den AKR-Schädigungsprozess in Fahrbahndecken aus Beton grundlegend zu klären, sind zwei aufeinander aufbauende Untersuchungsschwerpunkte Gegenstand dieses Beitrags. Im ersten Schwerpunkt wurden die prüftechnischen Voraussetzungen für die Charakterisierung der Degradation und damit der Rissbildung im Fahrbahndeckenbeton durch die Vorschädigung infolge von Ermüdungsbeanspruchungen geschaffen. Realisiert wurde dies durch die Implementierung und Optimierung eines Monitoringsystems im zyklischen 4-Punkt-Biegeversuch zur simultanen Erfassung der Rissbildung im großformatigen Schwingbalken. Zusätzlich wurde die Röntgen-3D-Computertomografie für die hochauflösende räumliche quantitative Rissanalyse in den Bohrkernen aus den Schwingbalken ohne und mit Vorschädigung weiterentwickelt. Im zweiten Untersuchungsschwerpunkt wurde mittels vielfältiger Experimente an kleinformatigen Probekörpern aus dem Schwingbalken gezeigt, dass durch die Ermüdungsbeanspruchung die bruchmechanischen Materialkennwerte des Betons zum Teil eine signifikante Veränderung erfahren. Based on the objective of the DFG (German research foundation) funded research group 1498 to clarify the influences on the ASR damage process, this paper deals with two focuses of investigation. In the first focus the technical requirements for the characterisation concerning the degradation and the formation of cracks in concrete pavements by the pre-damage as a result of fatigue loading were created. This was realized by the implementation and the optimisation of a monitoring system in the cyclic four point bending test to capture simultaneously the formation of cracks in the beam under sinusoidal bending load. In addition, the X-ray 3D-computed tomography was enhanced for the high-resolution quantitative spatial crack analysis in the drilling cores extracted of the beam under sinusoidal bending load without and with a pre-damage. Building on the first focus, in the second focus of investigation a significant change of the fracture-mechanical properties of the concrete as a result of fatigue loading has been demonstrated in numerous experiments using small specimens extracted from the beam under sinusoidal bending load.
The safety and integrity of casks for radioactive waste in accidental scenarios is analysed by BAM Federal institute tor Materials Research and Testing. An accidental scenario in German interim storage facilities is the drop from a crane during the handling operation. To reduce the mechanical loads to the cask a shock absorbing footing with high energy absorption capability is used in these areas. In order to analyse and evaluate such impact scenarios of casks, numerical simulations are performed. For a comprehensive simulation of an accidental scenario the behaviour of the damping concrete footing has to be taken into account as well and therefor a material model is needed. Material parameters under different loading conditions are the basis for a numerical model. For that reason a government funded research project (Kasparek, 2012) was conducted to characterise damping concrete under quasi-static as well as highly dynamic impact loading conditions. The performed tests include compression tests with and without lateral constraint small-scale and midscale penetration tests with different indenters, and finally a full-scale drop test onto a damping concrete footing.
Ermittlung dynamischer Kennwerte von Dämpferbeton für die Simulation des Beanspruchungsverhaltens
(2016)
Die Sicherheit und Integrität von Verpackungen radioaktiver Stoffe wird anhand von numerischen Berechnungen bewertet. Bei einem Anprall oder Absturz sind die mechanischen Beanspruchungen auf die Behälter auch von den Eigenschaften des Untergrunds abhängig. Um potentielle Gefahren während der Verladung zu minimieren, wird energieabsorbierender Dämpferbeton in den Handhabungsbereichen nuklearer Lager eingesetzt.
Zu einer umfassenden sicherheitstechnischen Analyse und Bewertung gehört die Berücksichtigung des Beanspruchungsverhaltens von Dämpferbeton. Hierfür ist ein numerisches Materialmodell notwendig, das in der Literatur bisher nicht vorlag. Die dafür notwendigen dynamischen Kennwerte sind in verschiedenen Druck- und Eindringversuchen ermittelt worden. Dazu wurden dynamische Druckversuche an würfelförmigen Prüfkörpern durchgeführt, sowie Eindringversuche mit unterschiedlichen Eindringkörpern und Dämpferbetonproben. Die experimentell ermittelten Kennwerte wurden verwendet, um ein Materialmodell für Dämpferbeton zu entwickeln und kritische Beanspruchungsszenarien numerisch zu berechnen. Um die Qualität des Materialmodells zu überprüfen, wurde ein realitätsnaher Fallversuch eines Behälters in Originalgröße auf ein lagertypisches Dämpferbetonfundament durchgeführt.
In dem Beitrag sollen die unterschiedlichen Untersuchungen zur Ermittlung dynamischer Kennwerte sowie deren Ergebnisse dargestellt werden. Gezeigt werden ebenso numerische Nachberechnungen einzelner Versuche sowie die ausführliche Berechnung des Fallversuchs im Originalmaßstab. Experimentelle und numerische Ergebnisse aus der Simulation werden hier gegenübergestellt.
The shock absorbing material damping concrete is for the foundation in dry interim storage facilities for radioactive waste in Germany. In case of a potential cask drop damping concrete minimizes the mechanical loads to the cask. In course of safety analyzes this accident scenario is considered by numerical simulations using the finite element method. To get reliable results of numerical simulations a suitable material model is needed to take the characteristics of damping concrete into account. Due to the lack of sufficient material knowledge a research project was started to characterize the material’s behavior under different load conditions. This paper presents the test program to analyze the material behavior of damping concrete which is characterized by large volume change and
strain rate hardening dependence. The determined Parameters were used to adapt an existing material model of the FE-code ABAQUS®. This model has to handle the mechanical damage behavior of damping concrete which occurs under compression and shear loads during a potential cask drop. To verify the material model numerical simulations are compared with dynamic penetration tests, which were conducted with specimens assembled similar to the real application of the damping concrete footings. The transferability of the material
model to a real accident scenario was verified by a drop test with a full-scale cask on a damping concrete footing.
Mechanical loading conditions of transport and storage casks for radioactive materials in accidental scenarios are highly affected by the behavior of both: the impact limiters and the footing materials. To minimize potential damages during the handling of casks, a so called damping concrete is frequently used for the footings in interim nuclear facilities. It obtains its shock absorbing properties through admixing of polymer cells. For a comprehensive mechanical evaluation of casks, advanced material models are also needed for damping concrete. In order to characterize the mechanical properties and to develop numerical material models, penetration tests were carried out at different test facilities of BAM. The tests contain static and dynamic penetration tests on cubic specimen with an edge length of 100 mm as well as mortared specimen with a size of 240 x 240 x 50 cm³. Indenters with different geometries and diameters were used for these model-sized penetration tests. Subsequently a full-scale cylindrical cast-iron indenter with a diameter of 110 cm was dropped of 5 m height on a realistic damping concrete footing.
This paper presents technical details of the drop test performance as well as some experimental results of tests carried out with the Japanese 'Yoyushindo-Disposal' waste container for intermediate depth disposal. The drop test program comprised three single 8 m drop tests at the specimen's corner edge orientation onto a concrete slab. The slab was connected to the unyielding IAEA target of the BAM's 200 t drop test facility. The three tested specimens had masses between 20 000 and 28 000 kg depending on their content mass. The tests were accompanied by various metrology, such as strain and deceleration measurements, optical three-dimensional deformation methods, leak tightness testing and test installation for potential particle release measurements to collect a set of data for establishing a basis for safety assessment.
This paper presents a comparison between full scale prototype and reduced scale model drop test data in regard to similarity mechanics. Together with a current BAM research project, the paper contributes to the further development of mechanical evaluation methods for safety assessment of RAM transport and storage packages including the transferability of package impact response from reduced scale models to full scale packages.
In context with Japanese disposal and transport container safety assessment the German Federal Institute for Materials Research and Testing (Bundesanstalt für Materialforschung und -prüfung) per-formed extensive drop test series with prototypes of RAM packages in recent years.
The paper presents two cooperative projects focused on project management, testing performance and experimental results.
In the first project, a full-scale prototype of a package for transport and storage of spent fuel elements with a total mass of 127,000 kg and its reduced-scale model which was similar to the prototype in both geometry and design were drop tested in 9 m and 1 m puncture tests at various drop orientations under regulatory conditions. In context with a corresponding research project the test data was used in combination with numerical methods to investigate the phenomenon of internal cask- content collisions during drop tests. Here, technological gaps between basket or radioactive content and cask body or primary lid can be a reason for significant high dynamic loadings of cask components and its internals due to additional impact interactions in the cask cavity caused by inner relative movement between content and cask. Further investigations were carried out in the field of similarity mechanics comparing experimental drop test data of the full-scale prototype and reduced-scale model in regard to the transferability of package impact response from reduced-scale models to full-scale packages.
In the second project, drop tests with a waste container for intermediate depth disposal were per-formed being contracted by Kobe Steel, Ltd. and a consortium of Japanese electric power plant com-panies. The drop test program comprised three single 8-m drop tests in a specimen’s corner edge orientation. For drop tests according to legal regulations for interim storage or final disposal it is often necessary to use a target which represents the real ground of the storage facility. In such cases the container hits directly onto a well-defined concrete slab on top of the IAEA target. Here, the directly impact target for the drop tests were concrete slabs manufactured in Japan and connected by mortar to the impact pad of the unyielding IAEA target.
Drop testing of a container for the storage. transport and disposal of intermediate level waste
(2017)
Impact tests were performed, as part of a corresponding container’s substantiation, during design development of a shielded container. The container will be used for storage, transport, and disposal of intermediate level waste in the UK.
The mechanical test program comprised a 9m free drop test onto an unyielding target in a container long lid edge down orientation at ambient conditions. Further, a 0,5m free drop test onto a punch target was performed. Here, the container was orientated with the lid downwards in a way that the punch, a mild steel bar, impacts a filter lid.
The test specimen was instrumented with strain gauges and accelerometers for the drop tests. Transient strains at selected points of the inner and outer container walls, at the shielding lid, as well as at the lid bolts were measured during the container’s impact. Furthermore, decelerations of the container body, container lid, and the skip were measured. The complex geometrical changes of the container due to impact were determined by optical 3d- deformation measures using the projected fringes method in combination with multi-image photogrammetry.
This paper summarizes the performance of the drop tests and various drop test results in context with the design development as well as aspects regarding the associated Finite Element (FE) analyses and post-test evaluation.
Instrumented measurements on radioactive waste disposal containers during experimental drop testing
(2011)
In context with disposal container safety assessment of containers for radioactive waste the German Federal Institute for Materials Research and Testing (BAM) performed numerous drop tests in the last years. The tests were accompanied by extensive and various measurement techniques especially by instrumented measurements with strain gages and accelerometers. The instrumentation of a specimen is an important tool to evaluate its mechanical behavior during impact. Test results as deceleration-time and strain-time functions constitute a main basis for the validation of assumptions in the safety analysis and for the evaluation of calculations based on finite-element methods. Strain gauges are useful to determine the time dependent magnitude of any deformation and the associated stresses. Accelerometers are widely used for the measuring of motion i.e. speed or the displacement of the rigid cask body, vibration and shock events. In addition high-speed video technique can be used to visualize and analyze the kinematical impact scenario by motion analysis. The paper describes some selected aspects on instrumented measurements and motion analysis in context with low level radioactive waste (LLW) container drop testing
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.
Internal cask content collisions during drop test of transport casks for radioactive materials
(2013)
In transport casks for radioactive materials, significantly large axial and radial gaps between cask and internal content are often present because of certain specific geometrical dimensions of the content (e.g. spent fuel elements) or thermal reasons. The possibility of inner relative movement between content and cask will increase if the content is not fixed. During drop testing, these movements can lead to internal cask content collisions, causing significantly high loads on the cask components and the content itself. Especially in vertical drop test orientations onto a lid side of the cask, an internal collision induced by a delayed impact of the content onto the inner side of the lid can cause high stress peaks in the lid and the lid bolts with the risk of component failure as well as impairment of the leak tightness of the closure system. This paper reflects causes and effects of the phenomenon of internal impact on the basis of experimental results obtained from instrumented drop tests with transport casks and on the basis of analytical approaches. Furthermore, the paper concludes the importance of consideration of possible cask content collisions in the safety analysis of transport casks for radioactive materials under accident conditions of transport.
Complementary to Part 1 of this work, the bi-continuous microstructure of porous synthetic cordierite ceramics for filtration applications was investigated using 3D x-ray computed tomography at different resolutions. Applying both Fast Fourier Transform and a newly developed image analysis algorithm, we quantitatively evaluated porosity and pore orientation. The statistical approach allows extraction of spatially resolved or average values. Porosity values based on x-ray absorption agree with mercury intrusion measurements, while pore orientation factors agree with x-ray refraction data (Part 1 of this work), and with published crystallographic texture data.
The paper presents technical details of the drop test performance as well as some experimental results of tests carried out with the Japanese 'Yoyushindo-disposal' waste container for intermediate depth disposal. The tests were accompanied by various metrology to collect data as basis for safety assessment.
For validation of structural integrity under normal and hypothetical accident conditions during transport and storage of radioactive material the Federal Institute for Materials Research and Testing (BAM) focuses its safety related scientific research on advanced mechanical safety assessment methods including simulation of high rate impact of model components and structures. A drop and crash test facility with an unyielding target and a load capacity of 1.200 kg was designed for materials testing of component size specimen under impact conditions at elevated and higher loading rates. The maximum drop height is 12 meters which enables impact velocities up to 15 m/s. An exactly falling test object or drop weight allows impact, bending, compression as well as crash and crush tests with maximum input energy of 118 kJ. An arresting unit has been developed to avoid multiple impacts during instrumented drop tests. The paper presents experimental techniques and examples of various measurement methods and advancements in order to assess assumption of materials and components behavior by definite displacement and stresses within mechanical testing. Instrumented drop weight tests are performed to complete materials data base and energy absorption of shock-absorbing materials and structures as well as to implement materials and structural parameters into FEA of reference structures. Furthermore, fracture mechanics parameters of thick walled DCI containers by means of dynamic bending tests are characterized by crack initiation and crack resistance behavior at the lowest operational temperature depending on the strain rate.
Methoden der Bauartprüfung und –zulassung von Behältern für radioaktive Stoffe, Sicherheitsnachweis von RAM –Behältern;
Versuchstechnische Anlagen der BAM für Gefahrgutverpackungen im Originalmaßstab; Durchführung experimenteller Untersuchungen mit Transport- und Lagerbehältern für radioaktive Stoffe; Fallprüfungen mit Prüfmustern und Modellbehältern; Beanspruchungsanalyse von Behälterkomponenten und Sicherheitsbewertung der Behälterkonstruktion; Vorstellung der BAM und des Testgeländes Technische Sicherheit
A management system based on international, national or other standards acceptable to the competent authority shall be established and implemented for all activities including design, manufacture, testing, documentation, use, maintenance, inspection in accordance with IAEA SSR-6. Hereby, quality assured testing and documentation can substantially contribute to the demonstration of package design compliance with the regulations. Nowadays, a drop test campaign within the approval process of packages for radioactive materials can be a very complex and extensive project including various test and measurement techniques. On this basis of procedures and documents the experimental tests of packages and containers are performed with quality proofed results and a high reliability. A complete traceability and direct transferability of package design test results can give particular importance to the type approval procedure.
For validation of structural integrity under normal and hypothetical accident conditions during transport and storage of dangerous goods the Federal Institute for Materials Research and Testing (BAM) focuses its safety related scientific research on advanced mechanical safety assessment methods including simulation of high rate impact of model components and structures.
An impact and crash test facility was recently developed for performing dynamic impact tests with component size specimen, or to crash specimens of impact limiter materials and structural components.
The paper presents experimental techniques of BAM drop test machine and options of several measurement methods and advancements in order to characterize typical shock-absorbing materials under impact loading conditions. Instrumented drop weight tests are performed to complete materials data base and energy absorption of shock-absorbing materials as well as to implement materials and structural parameters into FEA of reference structures.
BAM safety related research of containers for radioactive material focuses on advanced mechanical safety assessment methods for verification of the structural integrity and leak tightness under normal conditions of transport and hypothetical accident conditions during transport and storage. An essentially unyielding target with a rigid surface is required for impact tests performed for package approval according to IAEA regulations. In addition to specification of a target, e.g. with a combined mass more than 10 times that of the specimen for drop tests, unyielding target characteristics have been investigated with various package designs and different impact tests. The unyielding target of the BAM drop test facility, a reinforced concrete block together with an embedded and anchored mild steel plate, provides relatively large mass and stiffness with respect to the packages being tested. For monitoring reasons accelerometers and strain gauges are embedded in the concrete block of the foundation at several positions. Additionally, dynamic impact responses like vibrations and rigid body motion can be measured by seismic accelerometers. The mechanical characterisation of the target's rigidity is based on experimental results from various drop tests. Test containers with weights of 181 000 kg, 127 000 kg and 8010 kg hit the target with velocities up to 13·5 m s-1 in the horizontal and vertical drop positions. The rigidity of the impact target can be demonstrated with experimental results confirmed by analytical approaches. Some conclusions can be drawn about experimental testing as well as analytical calculations in order to compare impact effects.
Fire testing is an essential part of the hypothetical, cumulative mechanical and thermal test conditions that shall guarantee package safety in severe accidents. Within regulatory approval of transport or storage packages for radioactive material, specific thermal load tests are required in accordance to licensing conditions and international standards, respectively. The specifications of these thermal tests are based on test conditions with equivalent heat input to that of a hydrocarbon fuel fire. In the past, light heating oil, diesel or kerosene was mostly used as the fuel to generate the pool fire. In accordance with IAEA regulations for a fire in an accident, the temperature of 800 °C over a period of 30 minutes must be fulfilled. Furthermore, the delivery acceptance criteria for containers in nuclear waste repositories could reach for example average temperatures of 800 °C during a period of one hour in combination with defined requirements on activity release. BAM as a scientific and technical German federal government institute operates an open air Technical Safety Test Site for experimental investigations of dangerous good and its containment. In this areal a large fire test facility is under operation. Liquid Propane is utilized as fuel which is pumped via pipelines from a central storage tank to the fire exposed test facility areas. In the ring burner system, the gas is released from nozzles, and ignited by ignition burners. The paper includes examples of fire test performance with prototypes of a transport package and a storage container, respectively. In preparation of the thermal load, calorimeter tests have been performed using test specimens of appropriate size and behavior. For the fire test scenario is demonstrated that the IAEA thermal test requirements are fulfilled.
Anwendung des instrumentierten Kerbschlagbiegeversuchs zur Abschätzung der Rissauffangzähigkeit
(2001)
Die moderne Bauteilsicherheitsbewertung basiert auf Methoden der Bruchmechanik unter Anwendung von bruchmechanischen Kennwerten, die den Werkstoffwiderstand gegen Rissinitiierung und Rissfortschritt sowie das Rissauffangverhalten charakterisieren. Die experimentelle Ermittlung der Rissarrestzähigkeit ist im Allgemeinen jedoch schwierig und aufwendig. In diesem Beitrag werden Korrelationen für die Abschätzung der Sprödbruch-Übergangstemperatur (TNDT) und der Rissarrestzähigkeit (KIa) mit Hilfe einer Übergangstemperatur, die der Rissauffangkraft im instrumentierten Kerbschlagbiegeversuch entspricht, vorgestellt. Als Kriterien für den Zähigkeitsübergang gelten die an Charpy-V-Proben gemessene Rissauffangkraft 4 kN und die nach Master-Curve-Ansatz berechnete mittlere Rissarrestzähigkeit 100 MPam. Die für verschiedene Baustähle vorgeschlagenen Korrelationen zwischen den Übergangstemperaturen T(Fa = 4 kN), T(KIa) und TNDT werden am Beispiel des Stahles 18Ch2MFA bestätigt.
Three drop test campaigns have been performed with DN 30 Protective Structural Packaging (PSP) developed by DAHER NUCLEAR TECHNOLOGIES GmbH for the transport of natural, enriched and reprocessed uranium hexafluoride (up to 5 wt%) in 30B cylinders.
The mechanical prototype testing is intended to demonstrate that the package DN30 complies with regulatory requirements under normal and hypothetical accident conditions of transport (NCT, ACT) relevant to IF, AF and B(U)F packages, respectively.
The paper includes the results of the latest test campaign carried out in 2015-2016 at the drop test facility of BAM, Germany with new full scale prototypes of the DN30 PSP and 30B cylinders. Repetition of drop test sequences became necessary after changing to Polyisocyanurate foam as shock absorbing material with variable foam densities. Furthermore, the mechanical behavior of the UF6 content of the 30B cylinder is now simulated by a mixture of cement and steel grid as modified surrogate material; instead of small steel balls. The behavior of this new content simulation is assumed to be more realistic with respect to the properties of real UF6.