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 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 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 - 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 - Progress in Steel, Composite and Aluminium Structures 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 - GEN A1 - Pasternak, H. A1 - Komann, Steffen ED - Camotin, D. T1 - A new approach for determining the load-bearing capacity of locally supported shells T2 - Proceedings of SDSS 2006, International Colloquium on Stability and Ductility of Steel Structures 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 - 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 (Proceedings) 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 - Komann, Steffen A1 - Droste, Bernhard A1 - Wille, Frank A1 - Rittscher, D. T1 - Mechanical assessment of large nuclear power plant components in transport licensing T2 - 49. INMM-Konferenz 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 - 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, Nashville, USA (Proceedings) 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 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, July 13-17, 2008, Nashville, TN, USA (Proceedings) 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 - Radioactive Materials Transport Conference 2009 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 - JOUR A1 - Qiao, Linan A1 - Neumann, Martin A1 - Komann, Steffen A1 - Ballheimer, Viktor T1 - Dynamic and quasi-static FE calculation of impact from 9 metre drop of spent fuel transport cask JF - Packaging, transport, storage & security of radioactive materials (RAMTRANS) N2 - The drop from 9 m height onto a rigid target is one of the required proofs of safety for packages of radioactive materials. Direct dynamic finite element method (FEM) calculations and combined two step analytical quasi-static finite element (FE) calculations are both applied for the simulation of a 9 m drop test. This paper gives a comparative example of both approaches for the 9 m side drop simulation of the spent fuel transport cask with wood filled impact limiter. The model for dynamic FEM consists of cask body and impact limiter. Detailed material properties and geometry descriptions from each component of the impact limiter are required. The results (stress fields in the cask body) are obtained directly from the calculation. The combined method provides as intermediate results the force-deformation characteristic of impact limiter. The maximum impact limiter force determined by the law of energy conservation during the drop is then - in a second step - applied on the cask body in a quasi-static FE model in order to calculate the stresses. In this paper, the rigid body deceleration and the maximum stress in the middle of the cask body are used for the comparison between the dynamic FEM and the combined method. Similar maximum rigid body deceleration-time curves were obtained by both methods for the horizontal 9 m free fall. Concerning the stress in the cask body the dynamic FEM results oscillate about values calculated by the combined quasi-static approach. If the combined quasi-static approach is used in the safety assessment of a cask, a suitable factor has to be applied on its results to take into account the additional dynamic effects. KW - Drop test KW - Spent fuel transport cask KW - Finite element calculation KW - Dynamic simulation KW - Impact limiter KW - Wood PY - 2009 DO - https://doi.org/10.1179/174650909X12553336148026 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 20 IS - 4 SP - 174 EP - 178 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-20819 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 JF - Packaging, transport, storage & security of radioactive materials (RAMTRANS) 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 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 (Proceedings) 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 - CONF A1 - Kuschke, Christian A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Komann, Steffen T1 - Mechanical assessment criteria of spent fuel assemblies basket design T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials (Proceedings) 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 - Unterstützende Richtlinien und Normen in der sicherheitstechnischen Behälterprüfung T2 - 2. RAM-Behältersicherheitstage, BAM 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 - 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 (Proceedings) 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 - Komann, Steffen A1 - Neumann, Martin A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Weber, Mike A1 - Droste, Bernhard A1 - Qiao, Linan T1 - Static and Dynamic Calculation Approaches for Mechanical Design Assessment of Type B Packages for Radioactive Material Transport T2 - Waste Management Conference 2010 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 A1 - Droste, Bernhard A1 - Wille, Frank T1 - Transport von Großkomponenten aus der Stilllegung kerntechnischer Anlagen - Erfahrungen bei der mechanischen Bewertung T2 - Jahrestagung Kerntechnik 2010 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 - 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 (Proceedings) 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 - Komann, Steffen A1 - Neumann, Martin A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Weber, Mike A1 - Qiao, Linan A1 - Droste, Bernhard T1 - Static and dynamic calculation approaches for mechanical design assessment of type B packages for radioactive material transport - 10193 T2 - WM2010 Conference (Proceedings) T2 - WM2010 Conference CY - Phoenix, Arizona, USA DA - 2010-03-07 KW - Mechanische Bewertung KW - Radioaktives Material KW - Numerische Analyse KW - Typ B(U)-Verpackung PY - 2010 SP - 1 EP - 9 AN - OPUS4-21240 LA - eng 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 (Proceedings) 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 -