TY - JOUR A1 - Droste, Bernhard A1 - Komann, Steffen A1 - Wille, Frank A1 - Rolle, Annette A1 - Probst, Ulrich A1 - Schubert, Sven T1 - Consideration of aging mechanism influence on transport safety of dual purpose casks for spent nuclear fuel of HLW N2 - When storage of spent nuclear fuel or high level waste is carried out in dual purpose casks (DPC), the effects of aging on safety relevant DPC functions and properties have to be managed in a way that a safe transport after the storage period of several decades is capable and can be justified and certified permanently throughout that period. The effects of aging mechanisms (e.g. radiation, different corrosion mechanisms, stress relaxation, creep, structural changes and degradation) on the transport package design safety assessment features have to be evaluated. Consideration of these issues in the DPC transport safety case will be addressed. Special attention is given to all cask components that cannot be directly inspected or changed without opening the cask cavity, like the inner parts of the closure system and the cask internals, like baskets or spent fuel assemblies. The design criteria of that transport safety case have to consider the operational impacts during storage. Aging is not the subject of technical aspects only but also of ‘intellectual’ aspects, like changing standards, scientific/technical knowledge development and personal as well as institutional alterations. Those aspects are to be considered in the management system of license holders and in appropriate design approval update processes. The paper addresses issues that are subject of an actual International Atomic Energy Agency TECDOC draft 'Preparation of a safety case for a dual purpose cask containing spent nuclear fuel'. KW - Transport KW - Storage KW - Spent fuel KW - High-level waste KW - Aging KW - Metal seals KW - Transport and storage casks KW - Spent nuclear fuel KW - Aging mechanisms KW - Corrosion KW - Safety assessment PY - 2014 DO - https://doi.org/10.1179/1746510914Y.0000000070 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 25 IS - 3-4 SP - 105 EP - 112 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-33428 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Droste, Bernhard A1 - Koch, Frank A1 - Komann, Steffen T1 - Design assessment of spent fuel and HLW Transport Casks T2 - 49th INMM Annual Meeting, July 13-17, 2008 CY - Nashville, USA DA - 2008-07-13 KW - Safety Analysis KW - Transport Packages KW - Drop tests KW - Finite Element Analysis KW - Thermal Design KW - Containment KW - Quality Management PY - 2008 SP - 1 EP - 8 AN - OPUS4-17780 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Mechanical assessment of large nuclear power plant components in transport licensing T2 - 49. INMM-Konferenz CY - Nashville, TN, USA DA - 2008-07-13 PY - 2008 AN - OPUS4-17760 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Unterstützende Richtlinien und Normen in der sicherheitstechnischen Behälterprüfung T2 - 2. RAM-Behältersicherheitstage, BAM CY - Berlin, Germany DA - 2010-03-18 PY - 2010 AN - OPUS4-21322 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Pasternak, H. A1 - Komann, Steffen ED - Gizejowski, ED - Kozlowski, ED - Sleczka, ED - Ziólko, T1 - A new design formula for determining the load-bearing capacity of locally supported shells T2 - XI. Miedzynarodowa Konferencja Naukowo-Techniczna "Konstrukcje Metalowe" CY - Rzeszów, Poland DA - 2006-06-21 KW - Cylindrical shell KW - Stability KW - Steel KW - Buckling KW - Longitudinal stiffeners PY - 2006 SN - 0-415-40120-8 SP - 160 EP - 161 PB - Taylor & Francis CY - London, UK AN - OPUS4-19152 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Transport of Large Nuclear Power Plant Components - Experiences in Mechanical Design Assessment - T2 - Radioactive Materials Transport Conference 2009 CY - Manchester, England DA - 2009-05-12 PY - 2009 AN - OPUS4-19220 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Pasternak, H. A1 - Komann, Steffen ED - Camotin, D. T1 - A new approach for determining the load-bearing capacity of locally supported shells N2 - In practice usually thin-walled cylindrical silos are supported locally at the bottom rim of the shell. In this area a stress concentration may occur, which is responisble for buckling of the shell. In the currently applied codes, there is no information, how to analyze the load-bearing capacity of theselocally supported shells. In this paper, a new design formula is given for determining the load-bearing capacity. T2 - International Colloquium on Stability and Ductility of Steel Structures CY - Lisbon, Portugal DA - 2006-09-06 KW - Cylindrical shells KW - Stability KW - Steel KW - Buckling KW - Longiudinal stiffeners PY - 2006 SN - 972-846961-6 VL - 2 SP - 595 EP - 602 PB - IST Press CY - Lisabon AN - OPUS4-19153 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Wille, Frank T1 - Transport von Großkomponenten aus der Stilllegung kerntechnischer Anlagen - Erfahrungen bei der mechanischen Bewertung T2 - Jahrestagung Kerntechnik 2010 CY - Berlin, Deutschland DA - 2010-05-04 KW - Kerntechnische Anlagen KW - Rückbau KW - Mechanische Bewertung KW - Großkomponenten KW - Numerische Analyse PY - 2010 IS - Sektion 7 / 706 SP - 1 EP - 5 CY - Berlin AN - OPUS4-21239 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Droste, Bernhard A1 - Zencker, Uwe A1 - Komann, Steffen T1 - Reflektion der verkehrsrechtlichen Bauartprüfung des CASTOR HAW 28M aus Sicht der zuständigen Behörde BAM T2 - Jahrestagung Kerntechnik 2010 CY - Berlin, Deutschland DA - 2010-05-04 KW - Bauartprüfung KW - Fallprüfungen KW - Transportbehälter KW - FEM PY - 2010 SP - 1 EP - 5 CY - Berlin AN - OPUS4-21241 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Static and Dynamic Calculation Approaches for Mechanical Design Assessment of Type B Packages for Radioactive Material Transport T2 - Waste Management Conference 2010 CY - Phoenix, AZ, USA DA - 2010-03-07 PY - 2010 AN - OPUS4-21227 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Transport von Großkomponenten aus der Stilllegung kerntechnischer Anlagen - Erfahrungen bei der mechanischen Bewertung T2 - Jahrestagung Kerntechnik 2010 CY - Berlin, Germany DA - 2010-05-04 PY - 2010 AN - OPUS4-21228 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Musolff, André A1 - Quercetti, Thomas A1 - Müller, Karsten A1 - Droste, Bernhard A1 - Komann, Steffen T1 - Drop test program with the half-scale model CASTOR HAW/TB2 T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Spent fuel transport cask KW - Drop test KW - Impact limiter KW - Measurement procedure PY - 2010 SP - 1 EP - 8 AN - OPUS4-22771 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Günther, U. A1 - Baden, M. A1 - Komann, Steffen A1 - Nitz, Thilo T1 - Performance and restrictions of non-destructive testing (NDT) within the quality surveillance during manufacturing of type B-packages T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Mechanische Bewertung KW - Radioaktives Material KW - Numerische Analyse KW - Qualitätsüberwachung PY - 2010 SP - 1 EP - 8 AN - OPUS4-23675 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Qiao, Linan A1 - Zencker, Uwe A1 - Musolff, André A1 - Komann, Steffen T1 - Dynamic finite element analyses of a spent fuel transport and storage cask with impact limiters by 9 meter drop tests N2 - The 9 meter drop onto an unyielding target is one of the important mechanical tests within the safety assessment of transport casks for radioactive material. In general, the cask is equipped with impact limiters to reduce the dynamic load on the cask body by absorbing a major part of the kinetic energy. The impact limiters are often made of wood or aluminium. In this study an elastic-plastic material model with volume change was used to describe the stress-strain behaviour of wood found in crush tests. For aluminium, an elastic-incremental plastic material model with Cowper-Symonds parameters for strain rate depending material hardening was used to model the adiabatic stress-strain relations measured at specimens at constant ambient temperature. Hereafter simulations with a sophisticated finite element model were carried out and compared with different drop tests. Four drop tests of a half-scale cask model equipped with wood and aluminium impact limiters with different drop positions were selected to investigate the impact limiter behaviour during a 9 meter drop test. All drop tests were simulated with the same FE mesh but under different boundary and initial conditions. T2 - SIMULIA Customer conference CY - Barcelona, Spain DA - 17.05.2011 KW - Cask KW - Drop test KW - Impact limiter KW - Wood KW - Aluminium KW - Dynamics PY - 2011 SP - 932 EP - 944 AN - OPUS4-23706 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Wille, Frank T1 - Transport of large nuclear power plant components - experiences in mechanical design assessment T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Mechanische Bewertung KW - Radioaktives Material KW - Numerische Analyse PY - 2010 SP - 1 EP - 8(?) AN - OPUS4-23383 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Wille, Frank A1 - Rittscher, D. T1 - Mechanical assessment of large nuclear power plant components in transport licensing T2 - 49th INMM Annual Meeting CY - Nashville, TN, USA DA - 2008-07-13 KW - Rückbau KW - Kerntechnische Anlagen KW - Großkomponenten KW - Transport KW - Mechanik PY - 2008 SP - 1 EP - 8 AN - OPUS4-18440 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Wille, Frank T1 - Transport of large nuclear power plant components - experiences in mechanical design assessment T2 - Ramtransport 09 - 8th International Conference on radioactive materials transport 2009 CY - Manchester, Great Britain DA - 2009-05-12 KW - Rückbau KW - Kerntechnische Anlagen KW - Großkomponenten KW - Transport KW - Mechanik PY - 2009 IS - Session 5 / PAP 12 SP - 1 EP - 8 AN - OPUS4-20557 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Wille, Frank T1 - Transport of large nuclear power plant components: experiences in mechanical design assessment N2 - In the course of decommissioning of power plants in Germany large nuclear components (steam generator, reactor pressure vessel) must be transported over public traffic routes to interim storage facilities, where they are dismantled or stored temporarily. Since it concerns surface contaminated objects or low specific activity materials, a safety evaluation considering the IAEA transport regulations mainly for industrial packages (type IP-2) is necessary. For these types of industrial packages the requirements from normal transport conditions are to be covered for the mechanical proof. For example, a free drop of the package from a defined height, in dependence of its mass, onto an unyielding target, and a stacking test are required. Since physical drop tests are impossible generally due to the singularity of such 'packages', a calculation has to be performed, preferably by a complex numerical analysis. The assessment of the loads takes place on the basis of local stress distributions, also with consideration of radiation induced brittleness of the material and with consideration of recent scientific investigation results. Large nuclear components have typically been transported in an unpackaged manner, so that the external shell of the component provides the packaging wall. The investigation must consider the entire component including all penetration areas such as manholes or nozzles. According to the present IAEA regulations the drop position is to be examined, which causes the maximum damage to the package. In the case of a transport under special arrangement a drop only in an attitude representing the usual handling position (administratively controlled) is necessary. If dose rate values of the package are higher than maximum allowable values for a public transport, then it is necessary that additional shielding construction units are attached to the large component. KW - Radioactive material KW - Large components KW - Decommissioning KW - Nuclear power plant KW - Mechanical assessment KW - Numerical analysis PY - 2009 DO - https://doi.org/10.1179/174650909X12543085665266 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 20 IS - 4 SP - 149 EP - 153 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-20820 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Mechanical Assessment within Type B Packages Approval, The Application of Static and Dynamic Calculation Approaches T2 - 16th International Symposium on the Packaging and Transport of Radioactive Materials CY - London, England DA - 2010-10-03 PY - 2010 AN - OPUS4-22252 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Transport of Large Nuclear Power Plant Components - Experiences in Mechanical Design Assessment - T2 - 16.th International Symposium on the Packaging and Transport of Radioactive Materials CY - London, England DA - 2010-10-03 PY - 2010 AN - OPUS4-22216 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Pasternak, Hartmut T1 - A new design formula for determining the load-bearing capacity of locally supported shells T2 - International Colloquium on Stability and Ductility of Steel Structures CY - Lisbon, Portugal DA - 2006-09-06 PY - 2006 AN - OPUS4-12275 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Pasternak, Hartmut T1 - A new design formula for determining the load-bearing capacity of locally supported shells T2 - Wissenschaftlich-Technische Konferenz zum Metallbau CY - Rzeszów, Poland DA - 2006-06-21 PY - 2006 AN - OPUS4-12276 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Droste, Bernhard A1 - Koch, Frank A1 - Schubert, Sven A1 - Komann, Steffen T1 - State-of-the-art assessment of package design safety analyses T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 KW - Transportation of radioactive materials KW - Safety KW - Design assessment KW - Mechanical tests KW - Thermal tests KW - Drop tests KW - Numerical calculations KW - Quality assurance PY - 2007 SP - 1 EP - 8 PB - Institute of Nuclear Materials Management AN - OPUS4-16105 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Musolff, André A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Müller, Karsten A1 - Quercetti, Thomas T1 - Drop test program with a HLW cask model - performance, measurements and results N2 - BAM (Federal Institute for Material Research and Testing) is the competent authority for mechanical and thermal safety assessment of transport packages for spent fuel and high level waste (HLW) in Germany. In context with package design approval of the new German HLW cask CASTOR HAW28M, BAM performed several drop tests with a half-scale model of the CASTOR HAW/TB2. The test model was manufactured by GNS (Gesellschaft fur Nuklear Service mbH) and tested under accident transport conditions on the 200 tons BAM drop test facility at the BAM Test Site Technical Safety. For this comprehensive test program the test specimen CASTOR HAW/TB2 was instrumented at 21 measurement planes with altogether 23 piezo-resistive accelerometers, five temperature sensors and 131 tri-axial strain gauges in the container interior and exterior, respectively. The strains of four representative lid bolts were recorded by four uniaxial strain gauges per each bolt. Helium leakage rate measurements were performed before and after each test in the above noted testing sequence. The paper presents some experimental results of the half-scale CASTOR HAW/TB2 prototype (14,500 kg) and measurement data logging. T2 - 52nd INMM Annual meeting CY - Palm Desert, CA, USA DA - 17.07.2011 KW - Drop test results KW - Spent fuel transport cask KW - Impact limiter KW - Measurement methods KW - Drop test program PY - 2011 SP - 1 EP - 9 AN - OPUS4-24245 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Transport of Large Nuclear Power Plant Components - Experiences in Mechanical Design Assessment - T2 - Workshop BAM/US.NRC CY - Washington, D.C., USA DA - 2011-07-11 PY - 2011 AN - OPUS4-24230 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Kuschke, Christian A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Komann, Steffen T1 - Mechanical assessment criteria of spent fuel assemblies basket design N2 - Packages for the transport of radioactive material are generally equipped with specific structures (basket) to support the radioactive content in defined position. The safety function of the basket depends on the kind of transported inventory. In case of transport cask for spent fuel, the basket design has to ensure the subcriticality of the fissile material in all conditions of transport in particular. Therefore the evaluation of structural integrity and neutron absorption capability of the basket is an important part of complete safety analysis. Sufficient heat transfer to maintain fuel assembly and cask temperature within allowable limits has to be verified as well. Corrosion resistance is an additional requirement on basket materials owing to contact with water during loading and unloading operations. Computational and experimental methods or their combination along with additional material and component tests can be used to analyse the mechanical and thermal basket behaviour under transport conditions defined in IAEA regulations. By deciding between the analysis methods, the design features (including material selection concept) as well as specific safety function should be accounted. In approval procedures of transport packages for radioactive materials, the competent authority mechanical and thermal safety assessment is carried out in Germany by BAM. Some questions of safety evaluation of basket designs are discussed in this paper based on the BAM experience within approval procedures. The paper focuses primarily on the mechanical behaviour of baskets with regard to the assumptions that have to be used in the criticality safety demonstration. The state of the art methodologies for computational basket stress and deformation analysis as well as for interpretation of drop tests results are presented. T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Transport conditions KW - Spent fuel assemblies KW - Basket design PY - 2010 SP - 1 EP - 7 (Thursday T36/92) AN - OPUS4-24345 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Assessment of Ductile Cast Iron Fracture Mechanics Analysis within Licensing of German Transport Packages T2 - INMM, 52nd Annual Meeting CY - Palm Desert, CA, USA DA - 2011-07-17 PY - 2011 AN - OPUS4-25008 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Kiyak, Yusuf A1 - Wille, Frank A1 - Zerbst, Uwe A1 - Weber, Mike A1 - Klingbeil, Dietmar T1 - Assessment of ductile cast iron fracture mechanics analysis within licensing of German transport packages N2 - In the approval procedure of transport packages for radioactive materials, the mechanical and thermal safety assessment is carried out in Germany by competent authority BAM. In recent years BAM was involved in several licensing procedures of new spent fuel and HLW package designs, where the cask body was made of Ductile Cast Iron (DCI). According to IAEA regulations package designs have to fulfill requirements for specific conditions of transport. Type B(U) packages must withstand the defined accident conditions of transport. The temperature range from -40°C up to the operational temperature has to be considered. For the cask material DCI, it is necessary to determine the brittle fracture behavior. The German guideline BAM-GGR 007 defines requirements for the fracture mechanics of DCI. Due to complex structure of the cask body and the dynamic loading a fracture mechanical assessment in an analytical kind is not always possible. Experience of recent design approval procedures show that the application of numerical calculations are applicable to determine the fracture mechanical load in the cask body. At the first step a numerical analysis has to be done to identify the loading state at the whole cask body. Secondly an analysis of a detail of the cask body is made considering the displacement boundary conditions of the global model. An artificial flaw is considered in this detailed model to calculate the fracture mechanical loading state. The finite element mesh was strongly refined in the area of flaw. The size of the artificial flaw is characterized by the ultrasonic inspection used for the quality assurance of the package. The applicant developed additional analysis tools for calculation of stress intensity factor and/or J-Integral. The assessment approach by BAM led to the decision to develop own tools to the possibility for independent check of the results. The paper describes the authority assessment approach for the DCI fracture mechanics analysis. The validation procedure incl. the development of own tools is explained. BAM developed a post-processor called JINFEM to determine the fracture mechanical loads. The regulatory 1 m puncture bar drop test is used to give an example of the assessment procedure. T2 - 52nd INMM Annual meeting CY - Palm Desert, CA, USA DA - 17.07.2011 KW - Mechanische Bewertung KW - Radioaktives Material KW - Numerische Analyse KW - Bruchmechanik PY - 2011 SP - 1 EP - 10 AN - OPUS4-25022 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Musolff, André A1 - Quercetti, Thomas A1 - Müller, Karsten A1 - Droste, Bernhard A1 - Komann, Steffen T1 - Drop test program with half scale model CASTOR HAW/TB2 N2 - Federal Institute for Materials Research and Testing (BAM) is the competent authority for mechanical and thermal safety assessment of transport packages for spent fuel and high level waste in Germany. In context with package design approval of the new German high level waste cask CASTOR® HAW28M, BAM performed several drop tests with a half scale model of the CASTOR® HAW/TB2. The cask is manufactured by Gesellschaft für Nuklear Service mbH and was tested under accident transport conditions on the 200 tons BAM drop test facility at the BAM Test Site Technical Safety. For this comprehensive test program, the test specimen CASTOR® HAW/TB2 was instrumented at 21 measurement planes with altogether 23 piezo resistive accelerometers, five temperature sensors and 131 triaxial strain gauges in the container interior and exterior respectively. The strains of four representative lid bolts were recorded by four uniaxial strain gauges per each bolt. Helium leakage rate measurements were performed before and after each test in the above noted testing sequence. The paper presents some experimental results of the half scale CASTOR® HAW/TB2 prototype (14 500 kg) and measurement data logging. It illustrates the extensive instrumentation and analyses that are used by BAM for evaluating the cask performance to the mechanical tests required by regulations. Although some of the quantitative deceleration, velocity and strain values cannot be shown because of confidentially issues, they are provided qualitatively to illustrate the types of measurements and methodologies used at BAM. KW - IAEA drop testing KW - Half scale model KW - Experimental test PY - 2011 DO - https://doi.org/10.1179/1746510911Y.0000000013 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 22 IS - 3 SP - 154 EP - 160 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-25293 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Gröke, Carsten T1 - Verpackungen Bestandsaufnahme - Pflichten und Vorschriften bei schwach radioaktiven Stoffen PY - 2012 SN - 0944-6117 IS - 6 SP - 20 EP - 25 PB - Vogel CY - München AN - OPUS4-26362 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Assessment of ductile Cast Iron Fracture Mechanics Analysis within Licensing of German Transport Packages T2 - ASME-Conference 2012 CY - Toronto, Canada DA - 2012-07-15 PY - 2012 AN - OPUS4-26333 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Assessment of Ductile Cast Iron Fracture Mechanics Analysis within Licensing of German Transport Packages T2 - RAMTRANSPORT 2012, Royal Geographical Society CY - London, England DA - 2012-05-23 PY - 2012 AN - OPUS4-26334 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Prüfung der qualitätssichernden Maßnahmen an Verpackungen püfpflichtiger Versandstücke durch die BAM T2 - 3. RAM-Behältersicherheitstage, BAM CY - Berlin, Germany DA - 2012-03-22 PY - 2012 AN - OPUS4-26335 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Transport of Large Nucklear Power Plant Components - Experiences in Mechanical Desig Assessment - T2 - 3. RAM-Behältersicherheitstage, BAM CY - Berlin, Germany DA - 2012-03-22 PY - 2012 AN - OPUS4-26336 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Assessment of Quality Assurance Measures für Radioactive Material Transport Packages not Requiring Competent Authority Design Approval T2 - Waste Management conference 2013 CY - Phoenix, AZ, USA DA - 2013-02-24 PY - 2013 AN - OPUS4-28512 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Gröke, Carsten A1 - Droste, Bernhard T1 - Assessment of quality assurance measures for radioactive material transport packages not requiring competent authority design approval N2 - The majority of transports of radioactive materials are carried out in packages which don’t need a package design approval by a competent authority. Low-active radioactive materials are transported in such packages e.g. in the medical and pharmaceutical industry and in the nuclear industry as well. Decommissioning of NPP’s leads to a strong demand for packages to transport low and middle active radioactive waste. According to IAEA regulations the “non-competent authority approved package types” are the Excepted Packages and the Industrial Packages of Type IP-1, IP-2 and IP-3 and packages of Type A. For these types of packages an assessment by the competent authority is required for the quality assurance measures for the design, manufacture, testing, documentation, use, maintenance and inspection (IAEA SSR 6, § 306). In general a compliance audit of the manufacturer of the packaging is required during this assessment procedure. Their regulatory level in the IAEA regulations is not comparable with the “regulatory density” for packages requiring competent authority package design approval. Practices in different countries lead to different approaches within the assessment of the quality assurance measures in the management system as well as in the quality assurance program of a special package design. To use the package or packaging in a safe manner and in compliance with the regulations a management system for each phase of the life of the package or packaging is necessary. The relevant IAEA-SSR6 § 801 requires documentary verification by the consignor concerning package compliance with the requirements. T2 - WM2013 Conference CY - Phoenix, Arizona, USA DA - 24.02.2013 PY - 2013 SN - 978-0-9836186-2-1 SP - 1 EP - 8 CY - Phoenix, Arizona, USA AN - OPUS4-28504 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Gröke, Carsten T1 - Qualitätssicherung und -überwachung bei Verpackungen für prüfpflichtige Versandstücke zur Beföderung radioaktiver Stoffe N2 - Ziel dieses Beitrages soll es sein, zum einen das Vorgehen bei der Erlangung einer Anerkennung zur qualitätsgesicherten Herstellung einer Verpackung für prüfpflichtige Versandstücke der zuständigen Behörde im Sinne des ADR Unterabschnittes 1.7.3 'Qualitätssicherung' darzustellen und zum anderen Probleme bei der Umsetzung der rechtsverbindlichen Vorschriften des Gefahrgutrechts aufzuzeigen. T2 - Jahrestagung Kerntechnik 2013 CY - Berlin, Germany DA - 14.05.2013 PY - 2013 IS - Sektion 5: Entsorgung radioaktiver Abfälle, Lagerung SP - 1 EP - 6 AN - OPUS4-28653 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Reichardt, Adrian A1 - Komann, Steffen T1 - Experience regarding ageing management and maintenance of transport packages in Germany N2 - The presentation gives an overview about the current experiences of BAM regarding ageing management of transport packages in Germany. The concept of the BAM-GGR 023 for ageing management of transport packagings will be described. The fundamentals of BAM-GGR 023 will be shown, including the following key aspects: -the organization of an Ageing Management System (AMS), -the issue of an Ageing Management Plan (AMP), -the ageing evaluation as a part of the AMP, -the Ageing Surveillance Program (ASP) as a part of the AMP, -the Ageing Management Documentation (AMD). T2 - First Consultancy Meeting on Drafting the Safety Guide on Ageing Management and Maintenance of Radioactive Material Transport Packages CY - Vienna, Austria DA - 20.11.2023 KW - Ageing Management KW - Dual Purpose Cask KW - BAM-GGR 023 PY - 2023 AN - OPUS4-58863 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schubert, Sven A1 - Reichardt, Adrian A1 - Müller, Lars A1 - Neumann, Martin A1 - Komann, Steffen A1 - Wille, Frank T1 - Introduction of the German ageing management guide for packages for transport of radioactive materials N2 - The consideration of ageing mechanisms is with integration of the new para 613A into IAEA SSR-6 (Rev. 1) now obligatory for the design of transport packages. In addition, para 809(f) requires for packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance. Para 503(e) requires that all packaging components and radioactive contents have been maintained during storage in a manner that all requirements specified in IAEA SSR-6 (Rev.1) and in the applicable certificates of approval have been fulfilled. The evaluation of ageing mechanisms and their effects including monitoring are part of BAM’s authority assessment tasks related to the mechanical and thermal package design and quality assurance aspects. BAM has compiled a guideline for the implementation of ageing assessment and of the measures for ageing management of the approval procedure based on requirements of IAEA SSR-6 (Rev.1). The guideline is applicable only for packages requiring a competent authority approval. The paper aims to describe the structure of the guideline and the general approach for ageing management requirements. The type and amount of measures for ageing management depend mainly on the use of the package and on the ageing effects for the component, which result from relevant ageing mechanisms during package operation time. The implementation of measures for ageing management is divided into three levels – systemic measures, package design related measures and documentation. The systemic measures are attributed to the general management system and define the whole activities for organization of ageing management like structure, responsibilities, documentation, reports and evaluation. The package design related measures are defined in an ageing management plan (AMP). These measures shall ensure that the anticipated changes of the package design under consideration of ageing effects still complies with the design approval specification. Therefore, an ageing surveillance program (ASP) and, if necessary, a gap analysis program shall be developed. The ageing management documentation (AMD) ensures the continuous documentation of the compliance of a specific package to the approved package design, comprising mainly records resulting from operation and surveillance. T2 - PATRAM22 - 20th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Juan-les-Pins, France DA - 11.06.2023 KW - Guide KW - Ageing KW - Mechanism KW - Package KW - Management PY - 2023 SP - 1 EP - 10 PB - World Nuclear Transport Institute (WNTI) CY - London AN - OPUS4-57770 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rolle, Annette A1 - Wille, Frank A1 - Komann, Steffen A1 - Neumann, Martin T1 - Qualification Procedure for Seal Designs for Spent Fuel Transport and Storage Cask Containments N2 - The seal is a key component of the containment and closure system of transport and storage casks for radioactive material. It is a major contributor to ensuring compliance with the acceptable limits for activity release according to IAEA regulations. The requirements for a safe seal performance are high, accordingly. Every new seal design intended for use in the containment of a transport cask for radioactive material passes a qualification process in Germany. The qualification process is supervised by BAM as German competent authority for mechanical, thermal and containment assessment of packages requiring design approval. The closure system including the seal shall be able to withstand the corrosive, mechanical and thermal loads associated with routine, normal and accident conditions of transport according to the IAEA regulations without losing the required sealing function. Metal seals of the Helicoflex® type are often used to ensure required package leak tightness for both storage and transport, including transport after long term interim storage. The poster will provide an overview of requirements during a seal qualification process on the example of a Helicoflex® type metal seal. T2 - 21st International Symposium on the Packaging and Transportation of Radioactive Materials, PATRAM 2025 CY - San Antonio, Texas , US DA - 27.07.2025 KW - Spent fuel transport KW - Seals KW - Radioactive KW - Containment PY - 2025 SP - 1 EP - 5 AN - OPUS4-63911 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Managementsystem Guide der IAEA (TS-G-1.4) N2 - Es wird der Safety Guide der IAEA für das Managementsystem für den Transport radioaktiver Stoffe vorgestellt. Des Weiteren werden die BAM-Gefahrgutregeln für das Managementsystem erläutert. T2 - Informationsaustausch zur verkehrsrechtlichen Aufsicht bei der Beförderung radioaktiver Stoffe CY - Bonn, Germany DA - 04.02.2025 KW - Radioaktive Stoffe KW - Rückbau kerntechnischer Anlagen KW - Transport KW - Gefahrgut PY - 2025 AN - OPUS4-62654 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schubert, Sven A1 - Reichardt, Adrian A1 - Wille, Frank A1 - Komann, Steffen A1 - Neumann, Martin T1 - Introduction of an ageing management approach for packages for the transport of radioactive materials N2 - With integration of the new para 613A into SSR-6 [1] the consideration of ageing mechanisms is now obligatory for the design of packages and their approval. In addition, para 809(f) of SSR-6 [1] requires consideration of the effects of storage on ageing mechanisms, safety analyses and operation and maintenance instructions. German competent authorities Bundesanstalt für Materialforschung und -prüfung (BAM) and Bundesamt für die Sicherheit der nuklearen Entsorgung (BASE) are considering the aspect of ageing in approval procedures. Ageing assessment is mainly focused on dual purpose casks (DPC) package designs which are long-term stored in interim storage facilities. For these package designs, the evaluation of ageing management is now mandatory for the maintenance of the package design approvals with a validity period of 5 years and beyond. The ageing management includes amongst others a gap analysis, the assessment of ageing effects and operational experiences during operation and interim storage. BAM works on the compilation of a guideline for implementation of paras 613A, 809(f) and 809(k) for packages requiring competent authority approval at the application procedure in Germany. The paper describes essential items of ageing mechanisms and will give a foresight to the ageing management evaluation by BAM. T2 - INMM & ESARDA Joint Annual Meeting CY - Online meeting DA - 30.08.2021 KW - Dual purpose casks KW - Ageing KW - SSR-6 KW - Interim storage KW - Ageing mechanisms KW - Transport of radaioactive materials PY - 2021 UR - https://www.abstractsonline.com/pp8/#!/10383/presentation/964 SP - 1 EP - 6 PB - Institute of Nuclear Materials Management (INMM) CY - Mount Laurel, NJ AN - OPUS4-53180 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schubert, Sven A1 - Neumann, Martin A1 - Reichardt, Adrian A1 - Komann, Steffen A1 - Wille, Frank T1 - Experiences with the implementation of ageing management for packages for transport of radioactive materials in Germany N2 - The consideration of ageing mechanisms is now obligatory for the design of transport packages with integration of the para 613A into IAEA SSR-6 (Rev. 1). In addition, para 809(f) of SSR-6 (Rev. 1) requires for packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance. Para 503(e) requires that these packages have been maintained during storage in a manner that all requirements specified in SSR-6 (Rev.1) and in the applicable certificates of approval have been fulfilled. The evaluation of ageing mechanisms and their effects including monitoring are part of BAM’s authority assessment tasks related to the mechanical and thermal package design and quality assurance aspects. BAM has compiled the guideline BAM-GGR 023 for the implementation of ageing assessment and related measures into the approval procedure. The implementation of ageing management measures is obligatory in case of extension/renewal of package design approval certificates. BAM has evaluated package designs which are used only for transport as well as package designs for long term interim storage. The assessment of ageing mechanisms associated with the identification of ageing effects on components is the main part of the ageing management plan (AMP). Different approaches regarding AMP structure are introduced. Experiences and approaches about the evaluation of components for the expected package operating time are shown. We are focusing the evaluations of proofs for not accessible and not replaceable components. Operational experiences for these package designs are available and should be considered in the ageing evaluation. Corresponding measures for package monitoring are to be derived based on these results. The measures for monitoring shall be fixed in the Ageing Surveillance Program (ASP) to maintain a specification conform package for the transport on public routes. We show exemplary how results from ageing evaluation during the approval procedure are transferred into the ASP. T2 - PATRAM 2025 CY - San Antonio, Texas , US DA - 27.07.2025 KW - RAM KW - Ageing management KW - Radioactive material KW - Transport PY - 2025 SP - 1 EP - 8 PB - INMM CY - Washington D.C. AN - OPUS4-63987 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Müller, Lars A1 - Scheidemann, Robert A1 - Neumeyer, Tino A1 - Neumann, Martin A1 - Komann, Steffen A1 - Wille, Frank T1 - Thightness Assessment of welded Lids for Encapsulations of damaged Spent Nuclear Fuel in the Design Approval Process of Dual-Purpose Casks (DPC) N2 - The disposal of spent nuclear fuel in Germany is ensured using dual-purpose casks (DPC) for transport and interim storage. The leak tightness of the DPC and resulting containment is one of the most important aspects. Additional encapsulations are required for damaged spent nuclear fuel (DSNF) to guarantee safe handling and a separate tight closure. Due to the general design of DPCs for standard fuel assemblies should special requirements be considered for the design of the encapsulations for DSNF to ensure the loading in existing package designs. The absence of a replaceable sealing in the tightness barrier is the main difference for the encapsulations for damaged spent nuclear fuel. Instead, they are welded shut with a lid. The leak tightness of the encapsulation shall be proven in the design approval process for all transport conditions. This is especially valid for accident conditions of transport, where high internal impact forces may occur. BAM as German competent authority is responsible for the safety assessment of mechanical and thermal design, retention of radioactive material and quality assurance aspects of manufacturing and operation. BAM carried out a comprehensive safety assessment concerning the mechanical package design. As there are no representative standards for verifying the leak tightness of a welded lid, two approaches were being pursued. Established German standards may be used for verifying the leak tightness of a weld - but limited to low stresses. Therefore, physical tests were required for higher impact loads. Representative drop tests and highly sensitive leakage tests were performed. The paper presents an overview of the containment assessment by BAM and points out the main findings for the design of welds regarding leak tightness. Both verification procedures are described, on one hand with German standards for lower loads and on the other hand with physical tests for higher impact loads. The leak tightness of the encapsulation weld could be approved based on leakage tests and a corresponding evaluation for all transport conditions. T2 - PATRAM 2025 CY - San Antonio, Texas, USA DA - 27.07.2025 KW - Transport packages KW - Tightness assessment KW - Welded lids KW - Encapsulations PY - 2025 VL - 2025 SP - 1 EP - 11 PB - Institute of Nuclear Materials Management (INMM) CY - Indianapolis AN - OPUS4-64023 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Müller, Lars A1 - Neumann, Martin A1 - Wille, Frank T1 - Shipment of SCO-II – Authority assessment of mechanical aspects and quality management N2 - The decommissioning of nuclear facilities necessitates either the storage or disposal of large radioactive components such as steam generators, pressurizers, reactor pressure vessels and heads, or coolant pumps. These components or objects are large in size and mass with up to 6 meters in diameter and 20 meters in length and a weight of up to 400 tons. They are often transported to a storage, disposal, or recycling facility. Large components from nuclear facilities may often not be packed and need to be transported unpackaged due to size and weight. T2 - PATRAM 2025 CY - San Antonio, TX, USA DA - 27.07.2025 KW - radioaktive Stoffe, Rückbau kerntechnischer Anlagen, Transport, Gefahrgut PY - 2025 SP - 1 EP - 10 AN - OPUS4-63878 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Shipment of SCO-II – Authority assessment of mechanical aspects and quality management N2 - The decommissioning of nuclear facilities necessitates either the storage or disposal of large radioactive components such as steam generators, pressurizers, reactor pressure vessels and heads, or coolant pumps. These components or objects are large in size and mass with up to 6 meters in diameter and 20 meters in length and a weight of up to 400 tons. They are often transported to a storage, disposal, or recycling facility. Large components from nuclear facilities may often not be packed and need to be transported unpackaged due to size and weight. T2 - PATRAM 2025 CY - San Antonio, TX, USA DA - 27.07.2025 KW - Transport KW - Radioaktive Stoffe KW - Rückbau kerntechnischer Anlagen KW - Gefahrgut PY - 2025 AN - OPUS4-63877 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schubert, Sven A1 - Komann, Steffen A1 - Neumann, Martin A1 - Reichardt, Adrian A1 - Müller, Lars A1 - Wille, Frank T1 - Ageing management measures of transport packages for radioactive materials N2 - The consideration of ageing mechanisms is with integration into the IAEA-requirements now obligatory for the design of transport packages. For packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance are required. Therefore, these packages have been maintained during storage in a manner that all requirements specified in the IAEA-requirements and in the applicable certificates of approval have been fulfilled. BAM is the competent authority in Germany for evaluating the thermal and mechanical design of packages for the transport of radioactive materials. In this context, BAM also evaluates the aging mechanisms and aging effects occurring during the long-term storage period of such transport packages. BAM has developed a guideline for the implementation of ageing assessment and of the measures for ageing management into the approval procedure based on IAEA-requirements. The goal of the presented paper is to introduce this guideline and the general approach for ageing management requirements and to describe the application to a specific package design. The type and amount of the ageing management not only depend on the use of the packaging, but also on the accessibility of the components that are considered in the ageing assessment. The different operating phases of a packaging are considered for the ageing assessment, such as loading, interim storage or transport. The implementation of measures for ageing management is divided into three levels – systemic measures, package design related measures and documentation. The systemic measures are attributed to the general management system and define the whole activities for organization of ageing management like structure, responsibilities, documentation, reports and evaluation. The package design related measures are defined in an ageing management plan. These measures shall ensure that the anticipated changes of the package design under consideration of ageing effects still complies with the design approval specification. Therefore, an ageing surveillance program and, if necessary, a gap analysis program shall be developed. The ageing management documentation ensures the continuous documentation of the compliance of a specific package to the approved package design, comprising mainly records resulting from operation and surveillance. T2 - RAMTRANS 2024 CY - London, United Kingdom DA - 15.05.2024 KW - Radioactive Materials KW - Ageing Management KW - Transport Packages KW - Dual Purpose Casks PY - 2024 VL - 2024 SP - 1 EP - 8 PB - Nuclear Institute CY - London AN - OPUS4-60186 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Transportbehälter für Klasse 7 - Ein Überblick N2 - Die Präsentation gibt einen Überblick über die Tranportbehälter der Klasse 7. Behandelt werden neben der Versandstückklassifikation auch die Anforderungen an diese Verpackungen gemäß der gefahrgutrechtlichen Vorschriften. T2 - 30. Münchner Gefahrguttage CY - Online meeting DA - 20.07.2020 KW - Gefahrgutrecht KW - Transportbehälter KW - Radioaktives Material KW - Zulassungspflichtige Versandstücke PY - 2020 AN - OPUS4-51104 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Komann, Steffen A1 - Neumann, Martin A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Weber, Mike A1 - Qiao, Linan A1 - Droste, Bernhard T1 - Mechanical assessment within type B packages approval: application of static and dynamic calculation approaches N2 - This paper demonstrates exemplarily how numerical and experimental approaches can be combined reasonably in mechanical assessment of package integrity according to the IAEA regulations. The paper also concentrates on the question about how static mechanical approaches can be applied, and what their problems are in relation to dynamic calculation approaches. Under defined impact tests, which represent accident transport conditions, the package has to withstand impact loading, e.g. resulting from a 9 m free drop onto an unyielding target in sequence with a 1 m puncture drop test. Owing to the local character of the interaction between the puncture bar and the cask body, it is possible to develop a dynamic numerical model for the 1 m puncture drop which allows an appropriate simulation of the interaction area. Results from existing experimental drop tests with prototype or small scale cask models can be used for verification and validation of applied analysis codes and models. The link between analysis and experimental drop testing is described exemplarily by considering a regulatory 1 m puncture bar drop test onto the cask body of a recently approved German high level waste transport package. For the 9 m drop test of the package, it is difficult to develop a dynamic numerical model of the package due to the complexity of the interaction between cask body, impact limiters and unyielding target. Dynamic calculations require an extensive verification with experimental results. The simulation of a 9 m drop of a package with impact limiters is thereby often more complex than the simulation of a 1 m puncture drop onto the cask body. A different approximation method can be applied for the consideration of dynamic effects on the impact loading of the package. In a first step, maximum impact force and rigid body deceleration of the cask body during the impact process can be calculated with simplified numerical tools. This rigid body deceleration can subsequently be applied on a verified static numerical model. Dynamic effects, which cannot be covered by the static numerical analysis, have therefore to be considered by using an additional dynamic factor. The paper describes this approach exemplarily for a 9 m horizontal drop of a typical spent fuel cask design. KW - Package assessment KW - Package KW - Packaging KW - Structural analysis PY - 2011 DO - https://doi.org/10.1179/1746510911Y.0000000012 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 22 IS - 4 SP - 179 EP - 183 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-26448 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias A1 - Komann, Steffen T1 - Fracture Mechanical Analyses of a Welding Seam of a Thick-Walled Transport Package N2 - Transport packages shall satisfy various safety criteria regarding mechanical, thermal and radiation phenomena. Typical requirements focusing mechanical aspects are usually drop tests in accordance with IAEA regulations [1]. The drop tests are usually carried out experimentally and, as an additional measure, finite element analyses (FEA) are performed. A specific part of the investigations presented is the evaluation of the welding seam connecting cask shell and cask bottom. Experimental results and FEA are presented and compared. The evaluation of the welding seam performed includes a variety of aspects. In addition to the experimental and analytical stresses determined, different standards are used to investigate a possible crack initiation. Several destructive and non-destructive tests are performed for quality assurance in the manufacturing process as well as for different input parameters. The necessary monitoring and non-destructive measurement methods to define the boundary conditions of the standards are introduced. Taking into account all required parameters, the welding seam is examined and evaluated using the failure assessment diagrams (FAD) of the respective standards. It can be shown under the given boundary conditions that considering the experimental data, the welding seam is in the context of crack initiation below the enveloping curve in the acceptable region. More critical drop tests to be conducted are proposed and need to be investigated in future work. T2 - Pressure Vessels & Piping Conference® 2022 CY - Las Vegas, NV, USA DA - 17.07.2022 KW - Drop test KW - Fracture initiation KW - Transport package PY - 2022 AN - OPUS4-55374 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -