Dokument-ID Dokumenttyp Autoren/innen Persönliche Herausgeber/innen Haupttitel Abstract Auflage Verlagsort Verlag Herausgeber (Institution) Erscheinungsjahr Titel des übergeordneten Werkes Jahrgang/Band ISBN Veranstaltung Veranstaltungsort Beginndatum der Veranstaltung Enddatum der Veranstaltung Ausgabe/Heft Erste Seite Letzte Seite URN DOI Lizenz Datum der Freischaltung OPUS4-113 Dissertation Neumann, Martin Untersuchung des Verhaltens stoßdämpfender Bauteile von Transportbehältern für radioaktive Stoffe in Bauartprüfung und Risikoanalyse Transportbehälter für radioaktive Stoffe mit einer Typ-B-Versandstückzulassung müssen auch bei schweren Unfallbeanspruchungen sicherstellen, dass das radioaktive Inventar sicher umschlossen, eine unterkritische Anordnung gewährleistet und ionisierende Strahlung ausreichend abgeschirmt ist. Bei der Bewertung von Transportbehältern für radioaktive Stoffe im Rahmen der Bauartprüfung sowie für Risikoanalysen beim Transport radioaktiver Stoffe ist eine Simulation des Verhaltens holzgefüllter, stoßdämpfender Bauteile von Transportbehältern von großem Interesse, da diese in einer Unfallsituation einen Großteil der Aufprallenergie aufnehmen und damit die maximale Stoßkraft deutlich verringern. Damit haben die stoßdämpfenden Bauteile maßgeblichen Einfluss auf die Einhaltung der vom Versandstück zu gewährleistenden Schutzziele. Das Verhalten stoßdämpfender Bauteile wird von einer Vielzahl von Parametern wie Stoßdämpferkonstruktion, Materialeigenschaften und Beanspruchungsrandbedingungen beeinflusst. Es bestehen Unsicherheiten bei der Anwendung von vereinfachten numerischen Verfahren zur Berechnung derartiger Bauteile. Für die Simulation mit Hilfe von komplexen numerischen Verfahren wie dynamische Finite-Elemente-Methoden (FEM) ist bisher keine Modellbildung für die Kompression von Holz in axialer Richtung bei großen Deformationen erfolgt. Die in dieser Arbeit durchgeführten Untersuchungen haben sich daher auf die Modellbildung sowie die Untersuchung der Anwendbarkeit verschiedener Modellierungsformen konzentriert. Auf Basis von Erkenntnissen aus der Analyse stoßdämpfender Bauteile von Prototypen von Brennelementtransportbehältern nach einer 9-m-Fallprüfung auf ein unnachgiebiges Fundament und von in dieser Arbeit durchgeführten Stoßversuchen auf Holzproben wurde ein Modell für das Verhalten von Holz bei axialer Beanspruchung und großen Deformationen entwickelt. Das Modell beschreibt die bei der axialen Druckbeanspruchung von Holz auftretende Entfestigung als Funktion der seitlichen Dehnungsbehinderung. Die Energie, die vom Holz absorbiert werden kann, ist umso größer, je größer die seitliche Dehnungsbehinderung ist. Für das stoßdämpfende Bauteil resultiert daraus, dass die Energieabsorptionsfähigkeit des Stoßdämpfers von der Fähigkeit der äußeren Blechstruktur, ein Ausweichen der hoch belasteten Holzpakete zu verhindern, abhängt. Damit wurde ein Modell für das Verhalten von holzgefüllten Stoßdämpfern abgeleitet. Holz muss, um signifikant Energie zu absorbieren, durch starre Behälter- oder Stoßdämpferstrukturen lagestabilisierend abgedeckt sein. Für einen realistischen Vergleich zwischen gemessener und berechneter Stoßdämpferdeformation ist zu der gemessenen Verformung noch eine elastische Rückfederung des stoßdämpfenden Bauteils nach dem Aufprall zu addieren. Das optische, zur Vermessung von dreidimensionalen Objekten entwickelte Messverfahren der Streifenprojektion wurde erstmalig für die Vermessung von stoßdämpfenden Bauteilen von Transportbehältern für radioaktive Stoffe eingesetzt. Das Verfahren ermöglicht die Aufnahme der genauen Objektgeometrie vor und nach dem Versuch und eignet sich somit sehr gut für eine Schadens- und Verformungsdokumentation der stoßdämpfenden Bauteile von in Fallversuchen untersuchten Prüfmustern. Es wurde gezeigt, dass für Behälter mit großen, relativ zueinander beweglichen Massen das verbreitete Bewertungsschema der Begrenzung der Starrkörperverzögerung für eine Beanspruchungsermittlung an den Komponenten des Versandstücks nicht geeignet ist, da das System nicht mehr als Starrkörper aufgefasst werden kann. Es wurde das vereinfachte numerische Verfahren „ImpactCalc"', mit dem Starrkörperverzögerungen und Stoßdämpferdeformationen ermittelt werden können, entwickelt und bewertet. Das Verfahren kann für mechanische Nachweise der Einhaltung der Schutzziele für Versandstücke mit radioaktiven Stoffen in der Bauartprüfung zielführend eingesetzt werden, wenn das Versandstück exklusive der Stoßdämpfer als Starrkörper betrachtet werden kann und ein entsprechender Sicherheitsfaktor angewendet wird. Für die Risikoanalyse können auf einfache und kostengünstige Weise Beanspruchungen durch verschiedene Unfallsituationen, beispielsweise der Aufprall auf reale Fundamente, abgeschätzt und mit dem Aufprall auf das unnachgiebige Prüfstandsfundament verglichen werden. Für Finite-Elemente-Verfahren wurde aufbauend auf den Schlussfolgerungen zum Verhalten von Holz bei Kompression unter großen Deformationen ein kontinuumsmechanisches Ersatzmodell vorgeschlagen, das die seitliche Dehnungsbehinderung als Mehrachsigkeit des Spannungszustandes im Ersatzkontinuum in Betracht zieht. Mit Hilfe des kommerziellen Finite-Elemente-Programms LS-DYNA wurde die Anwendbarkeit verschiedener Materialmodelle auf dieses Ersatzmodell sowie weitere vorgeschlagene Modellierungsformen untersucht. Mit keiner der untersuchten Kombinationen ist es gelungen, global das Verhalten von Holz im Nachbruchbereich inkl. Entfestigung zu modellieren. Durch Simulation eines Fallversuchs mit einer behälterähnlichen Ersatzmasse und stoßdämpfenden Bauteilen wurden verschiedene Modellierungsformen und Detaillierungsgrade für stoßdämpfende Bauteile von Transportbehältern für radioaktive Stoffe untersucht und bewertet. Kann eine weitreichende Verifikation mit experimentellen Methoden vorausgesetzt werden, lässt sich die FEM in Bauartprüfung und Risikoanalyse zielführend für die Beanspruchungsermittlung anwenden. Durch eine experimentelle Verifikation muss das Simulationsmodell an die im Versuch herrschenden Randbedingungen bezüglich der seitlichen Stützung des Holzes angepasst werden. Berlin Bundesanstalt für Materialforschung und -prüfung (BAM) 2009 45 978-3-9812354-8-7 1 205 urn:nbn:de:kobv:b43-1135 http://www.gesetze-im-internet.de/urhg/index.html 2015-01-23 OPUS4-12269 Zeitschriftenartikel König, S.; Diersch, R.; Lührmann, A.; Müller, Karsten; Neumann, Martin; Quercetti, Thomas; Droste, Bernhard Full-Scale Drop Testing of the CONSTOR®, V/TC Package Program, and Preliminary Results Northbrook, Ill. Institute of Nuclear Materials Management 2005 Journal of nuclear materials management 33 3 4 10 2016-02-19 OPUS4-9157 Zeitschriftenartikel Petersohn, Dieter; Neumann, Martin Untersuchungen zur Kathodolumineszenz von Leuchtstoffen und bedampften Objekten. Vermessung der spektralen Transmission dünner Schichten Münster, Westf. Remy 1979 Beiträge zur elektronenmikroskopischen Direktabbildung von Oberflächen 10 10. Kolloquium des Arbeitskreises für Elektronenmikroskopische Direktabbildung und Analyse von Oberflächen (EDO) Münster, Deutschland 1977-09-04 1977-09-09 639 646 2016-02-19 OPUS4-26344 Beitrag zu einem Tagungsband Neumann, Martin; Günther, U.; Ballheimer, Viktor; Linnemann, Konrad; Wille, Frank; Droste, Bernhard Experiences by German authority with safety case approach for welding seams as part of SNF transport package containments Federal Institute for Materials Research and Testing (BAM) is the responsible authority for the assessment of mechanical and thermal safety as well as quality issues within the licensing procedure for transport casks for radioactive materials. The assessment includes a brittle fracture analysis of all relevant cask components. For cask bodies where a steel bottom is welded to a steel shell, specimens for testing of sufficient fracture resistance can normally not be extracted directly from the welding seam area of the cask. Therefore, a methodology has to be developed to ensure compliance with the safety analysis considerations and the approved design specification. This paper describes such a methodology including brittle fracture analysis and de-termination of required material properties as well as aspects of quality assurance during manufacturing. Nuclear institute (ni) 2012 RAMTRANSPORT 2012 - 9th International Conference on the Radioactive Materials Transport and Storage (Proceedings) RAMTRANSPORT 2012 - 9th International Conference on the Radioactive Materials Transport and Storage London, UK 2012-05-22 2012-05-24 Session 4.2 RAM 18 1 6 2016-02-19 OPUS4-26328 Vortrag Neumann, Martin Material Characterization and modeling within safety analysis of packages for transport of radioactive material 2012 ASME 2012 Pressure Vessels & Piping Division Conference ASME 2012 Pressure Vessels & Piping Division Conference Toronto, Canada 2012-07-15 2012-07-19 2016-02-19 OPUS4-26332 Vortrag Neumann, Martin Experiences by german authority with safety case approach for welding seams as part of SNF transport package containments 2012 RAMTRANSPORT 2012 RAMTRANSPORT 2012 London, England 2012-05-22 2012-05-24 2016-02-19 OPUS4-24236 Beitrag zu einem Tagungsband Eisenacher, Germar; Scheidemann, Robert; Neumann, Martin; Wille, Frank; Droste, Bernhard Approach for a finite element material model for wood for application in mechanical safety cases of transport packages BAM Federal Institute for Materials Research and Testing is the competent authority for mechanical safety assessment of transport packages for radioactive material in Germany. The further development of state-of-the-art technology concerning assessment methods is essential for a qualified work of involved designers and authority experts. The paper gives an example of current development done to improve understanding and modeling capabilities of wood filled impact limiter. In order to reduce the loads applied to the package containment, which result from regulatory drop tests, most packages are protected by energy dissipating impact limiter. Wood, encapsulated by steel sheets, is one of the materials typically used for energy dissipation in these impact limiter. Very often, mechanical safety cases regarding the 9 m drop test are performed computationally, where it is essential to use reliable and verified computational methods and models. In this context, the paper presents an approach for a finite element material model for wood. Thereby, the mechanical behavior of wood under compression loading is the focus of the development work. Additionally, material orientation as well as strain rate, temperature and lateral constraint may vary. A large number of experiments, particularly compression tests, was designed and performed to establish an adequate experimental database for modeling verification. The experimental results enabled the derivation of necessary requirements: The material model has to take into account strain rate and temperature dependencies as well as the anisotropic characteristics of the material, a proper yield criterion, flow rule and hardening law. Such a material model is currently not available in established commercial dynamic finite element codes. Thus it is necessary to create a user-defined material model considering the mentioned requirements. A first step was done by determining a yield surface as well as detecting flow and hardening mechanisms from experimental force-deflection curves. In a next step the LS-DYNA material model MAT_75 was altered according to conclusions of former BAM development work, regarding the modeling of post-peak softening as a function of lateral constraint. Future research will contain the further development, implementation and verification of a material model for wood. Institute of Nuclear Materials Management (INMM) 2011 52nd INMM Annual meeting (Proceedings) 52nd INMM Annual meeting Palm Desert, CA, USA 17.07.2011 21.07.2011 1 8 2016-02-19 OPUS4-27743 Zeitschriftenartikel Eisenacher, Germar; Scheidemann, Robert; Neumann, Martin; Droste, Bernhard; Völzke, Holger Dynamic crushing characteristics of spruce wood under large deformations An extensive series of large deformation crushing tests with spruce wood specimens was conducted. Material orientation, lateral constraint and loading rate were varied. Regarding material orientation, a reduction in the softening effect and the general force level was observed with a higher fiber-load angle. A comparison with characteristics gained by application of Hankinson's formula showed discrepancies in compression strength and the beginning of the hardening effect. Lateral constraint of the specimens caused a multiaxial stress state in the specimens, which was quantified with the applied measuring method. Further, a higher force level compared to specimens without lateral constraint and significant hardening effect at large deformations resulted. Thus, the influence of a multiaxial stress state on the force level could be determined. An increase in the loading rate led to higher force levels at any displacement value and material orientation. Berlin Springer 2013 Wood science and technology 47 2 369 380 10.1007/s00226-012-0508-5 2016-02-20 OPUS4-26241 Beitrag zu einem Tagungsband Eisenacher, Germar; Kuschke, Christian; Schubert, Sven; Neumann, Martin; Sterthaus, Jens; Nitz, Thilo; Wille, Frank Moisture content of wood - influence on mechanical behavior of wood filled impact limiter and importance for quality surveillance during manufacturing The moisture content of wood is known to have a significant influence on the wood’s mechanical properties. Using wood as an energy absorber in impact limiter of packages for the transport of radioactive material, it is of particu-lar importance to ensure the moisture content and thus relevant mechanical properties to be in specified limits. The paper surveys the influence of wood moisture content on the mechanical properties of wood. Different measuring methods are discussed with respect to in-situ applicability, accuracy and effort. The results of an experimental ana-lysis of the accuracy of hand-held moisture meters using the electrical resistance method are discussed. Conclu-sions are drawn regarding the measurement of moisture content of wood upon delivery as well as of complete im-pact limiter assemblies. Requirements for quality surveillance during manufacturing of wood filled impact limiter are derived and it is exemplified how to meet them. Construction, manufacturing and inspection of impact limiter encapsulation with regard to leak-tightness are addressed. Nuclear institute (ni) 2012 RAMTRANSPORT 2012 - 9th International Conference on the Radioactive Materials Transport and Storage (Proceedings) RAMTRANSPORT 2012 - 9th International Conference on the Radioactive Materials Transport and Storage London, UK 2012-05-22 2012-05-24 4.4 RAM 30 1 11 2016-02-19 OPUS4-26271 Beitrag zu einem Tagungsband Neumann, Martin; Ballheimer, Viktor; Sterthaus, Jens; Schubert, Sven; Eisenacher, Germar; Wille, Frank Material characterization and modeling within safety analysis of packages for transport of radioactive material New York American Society of Mechanical Engineers 2012 PVP2012 - Proceedings of the ASME 2012 Pressure vessels & piping division conference ASME 2012 Pressure vessels & piping division conference Toronto, Ontario, Canada 2012-07-15 2012-07-19 PVP2012-78297, 1-6 2016-02-19 OPUS4-16295 Vortrag Neumann, Martin Analytical and numerical impact limiter calculation methods; recent research results 2007 BAM - U.S. NRC Meeting BAM - U.S. NRC Meeting Rockville, MD, USA 2007-10-18 2016-02-19 OPUS4-17495 Beitrag zu einem Tagungsband Neumann, Martin; Droste, Bernhard; Wille, Frank Using Scale Model Impact Limiter in the Type Assessment of Transport Casks for Radioactive Material Institute of Nuclear Materials Management 2007 PATRAM 2007 - 15th International symposium on the packaging and transportation of radioactive materials (Proceedings) PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials Miami, Florida, USA 2007-10-21 2007-10-26 (Abstract # 86) 1 8 2016-02-19 OPUS4-17496 Beitrag zu einem Tagungsband Neumann, Martin; Ballheimer, Viktor; Wille, Frank Estimation of cask deceleration and impact limiter deformation under 9m drop test conditions using the calculation tool “ImpactCalc” Institute of Nuclear Materials Management 2007 PATRAM 2007 - 15th International symposium on the packaging and transportation of radioactive materials (Proceedings) PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials Miami, Florida, USA 2007-10-21 2007-10-26 1 8 2016-02-19 OPUS4-17498 Zeitschriftenartikel Neumann, Martin; Wille, Frank; Droste, Bernhard Scale model impact limiter in type assessment of radioactive material transport packages Ashford Ramtrans Publ. 2008 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 19 1 53 57 2016-02-19 OPUS4-17499 Zeitschriftenartikel Neumann, Martin; Wille, Frank; Ballheimer, Viktor Approximation of package deceleration and shock absorber deformation under 9 m drop test conditions using simplified numerical tool ImpactCalc Ashford Ramtrans Publ. 2008 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 19 1 35 40 2016-02-19 OPUS4-17911 Vortrag Neumann, Martin Simulation of crushing of wood filled impact limiter of packages for radioactive material 2008 9th International Conference on Computational Structures Technology (CST) 2008 9th International Conference on Computational Structures Technology (CST) 2008 Athens, Greece 2008-09-01 2008-09-05 2016-02-19 OPUS4-16013 Vortrag Neumann, Martin Using scale model impact limiter in the type assessment of transport casks for radioactive material 2007 PATRAM 2007 The 15th International Symposium on the Packaging and Transportation of Radioactive Material PATRAM 2007 The 15th International Symposium on the Packaging and Transportation of Radioactive Material Miami, FL, USA 2007-10-21 2007-10-26 2016-02-19 OPUS4-16015 Vortrag Neumann, Martin Estimation of cask deceleration and impact limiter deformation under 9m drop test conditions using the calculation tool "Impactcalc" 2007 PATRAM 2007 The 15th International Symposium on the Packaging and Transportation of Radioactive Material PATRAM 2007 The 15th International Symposium on the Packaging and Transportation of Radioactive Material Miami, FL, USA 2007-10-21 2007-10-26 2016-02-19 OPUS4-17838 Beitrag zu einem Tagungsband Musolff, André; Müller, Karsten; Neumann, Martin; Kadji, Arsène Brice; Droste, Bernhard Drop Test Results of the Full-scale CONSTOR V/TC Prototype Institute of Nuclear Materials Management 2007 PATRAM 2007 - 15th International symposium on the packaging and transportation of radioactive materials (Proceedings) PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials Miami, Florida, USA 2007-10-21 2007-10-26 Abstract #65 1 7 2016-02-19 OPUS4-17891 Beitrag zu einem Sammelband Neumann, Martin; Wille, Frank Topping, B. H. V.; M. Papadrakakis, Simulation of the Crushing of Wood Filled Impact Limiters for Packages of Radioactive Material Mechanical and thermal safety assessment of packages for transport of radioactive material in Germany is carried out by the Federal Institute for Materials Research and Testing (BAM). Both experimental and computational (analytical, numerical) methods combined with material and/or component tests are the basis for the state of the art safety assessment concept at BAM. The required mechanical tests according to IAEA regulations include, among others, a 9-m-drop-test on an unyielding target. Impact limiting components, which are attached to the cask at both ends, limit forces applied on the cask body and lid system by absorbing a major part of the impact energy. In Germany, impact limiters of packages for transport of radioactive materials are typically of steel-wood-sandwich construction, combining a relatively stiff steel structure bolted to the cask body, outer steel plates and different types of wood. By crushing the wood-steel-sandwich-structure between an unyielding target and the cask, the kinetic energy of a 9-m-free-fall is absorbed. The main energy absorber is wood under a high level of deformation. Wood under large deformations exhibits destruction of the fibre matrix. By analysing compression of the impact limiter wood after the drop tests with prototype casks for radioactive material, underlying mechanisms of wood crushing and corresponding energy absorption under large deformations are identified. Softening occuring at compression of the wood is a function of the lateral strain restriction of wood. Against the background of continuum mechanics an analogous model for compression of the fibre bundle is presented. The model takes the lateral strain restriction as triaxiality of the stress state into account. Further modelling possibilities for wood with a continuum approach are described. Different material laws in the explicit finite element code LS-DYNA are analysed for possible application using the analogous model for the fibre bundle. Small scale compression tests with wooden specimens are modelled in order to evaluate the ability of different modelling techniques to simulate softening. Although modelling of the compression of wood under large deformations is possible, softening could not be simulated purposefully. A drop test of a cask with impact limiting devices similar to existing impact limiters is simulated with different material laws for wood. The behaviour of impact limiting devices could not be simulated universally including the influence of the lateral strain restriction; nevertheless loading of the cask by crushing of the impact limiter could be simulated purposefully. Verification with experimental results is essential. Stirlingshire, Scotland, UK Civil Comp Press 2008 9th International Conference on Computational Structures Technology, September 2-5, 2008, Athens, Greece (Proceedings) 978-1-905088-22-5 9th International Conference on Computational Structures Technology Athens, Greece 2008-09-02 2008-09-05 Paper 22 1 21 2016-02-19 OPUS4-6875 Zeitschriftenartikel König, S.; Diersch, R.; Lührmann, A.; Müller, Karsten; Neumann, Martin; Quercetti, Thomas; Droste, Bernhard Full-scale Drop Testing of the CONSTOR V/TC Package - Program and Preliminary Results Northbrook, Ill. Institute of Nuclear Materials Management 2005 Journal of nuclear materials management 33 3 4 10 2016-02-19 OPUS4-29243 Zeitschriftenartikel Eisenacher, Germar; Kuschke, Christian; Schubert, Sven; Neumann, Martin; Sterthaus, Jens; Nitz, Thilo; Wille, Frank Moisture content of wood: influence on mechanical behaviour of wood filled impact limiters and importance for quality surveillance during manufacturing The moisture content of wood is known to have a significant influence on the wood's mechanical properties. Using wood as an energy absorber in impact limiters of packages for the transport of radioactive material, it is of particular importance to ensure the moisture content and thus relevant mechanical properties to be in specified limits. The paper surveys the influence of wood moisture content on the mechanical properties of wood. Different measuring methods are discussed with respect to in situ applicability, accuracy and effort. The results of an experimental analysis of the accuracy of hand held moisture metres using the electrical resistance method are discussed. Conclusions are drawn regarding the measurement of moisture content of wood upon delivery as well as of complete impact limiter assemblies. Requirements for quality surveillance during manufacturing of wood filled impact limiters are derived and it is exemplified how to meet them. Construction, manufacturing and inspection of impact limiter encapsulation with regard to leak tightness are addressed. Ashford Ramtrans Publ. 2012 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 23 3-4 179 185 10.1179/1746510913Y.0000000023 2016-02-20 OPUS4-19219 Vortrag Neumann, Martin Modelling of compression of wood filled impact limiter of casks for transportation of radioactive material 2009 Radioactive Materials Transport Conference 2009 Radioactive Materials Transport Conference 2009 Manchester, England 2009-05-12 2009-05-14 2016-02-19 OPUS4-19751 Beitrag zu einem Tagungsband Neumann, Martin; Wille, Frank Modelling of compression of wood filled impact limiter of casks for transportation of radioactive material Impact limiters of packages for transport of radioactive materials are in Germany typically steel-wood-sandwich-constructions, combining a relatively stiff steel structure bolted to the cask body, outer steel plates and different types of wood. By crushing the wood-steel-sandwich-structure between unyielding target and cask, kinetic energy of 9-m-free-fall is absorbed. Main energy absorber is wood under a high level of deformation. Wood under large deformations exhibits destruction of the fibre matrix. By analysing compression of impact limiter wood after drop tests with prototype casks for radioactive material, underlying mechanisms of wood crushing and corresponding energy absorption under large deformations are identified. Softening occurring at compression of wood is a function of lateral strain restriction of wood. Against the background of continuum mechanics an analogous model for compression of fibre bundle is presented. The model takes lateral strain restriction as triaxiality of stress state into account. Further modelling possibilities for wood with a continuum approach are described. Different material laws in the explicit Finite Element code LS-DYNA are analysed for possible application on the analogous model for the fibre bundle. Small scale compression tests with wooden specimens were modelled in order to evaluate the ability of different modelling techniques to simulate softening. Although modelling of compression of wood under large deformations is possible, softening could not be simulated purposefully. A drop test of a cask with impact limiting devices similar to existing impact limiters is simulated with different material laws for wood. Behaviour of impact limiting devices could not be simulated universally including influence of lateral strain restriction; nevertheless loading of the cask by crushing of impact limiter could be simulated purposefully. Verification with experimental results is compulsory. The Nuclear Institute (NI), London 2009 RAMTRANSPORT 09 - 8th International Conference on radioactive materials transport 2009 (Proceedings) Ramtransport 09 - 8th International Conference on radioactive materials transport 2009 Manchester, Great Britain 2009-05-12 2009-05-14 PAP31 1 20 2016-02-19 OPUS4-20819 Zeitschriftenartikel Qiao, Linan; Neumann, Martin; Komann, Steffen; Ballheimer, Viktor Dynamic and quasi-static FE calculation of impact from 9 metre drop of spent fuel transport cask 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. Ashford Ramtrans Publ. 2009 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 20 4 174 178 10.1179/174650909X12553336148026 2016-02-19 OPUS4-20804 Vortrag Neumann, Martin Simulation of Impact Limiter Crushing of RAM Packages under 9 m Drop Test Conditions 2010 Waste Management 2010 Waste Management 2010 Phoenix, AZ, USA 2010-03-06 2010-03-11 2016-02-19 OPUS4-21240 Beitrag zu einem Tagungsband Komann, Steffen; Neumann, Martin; Ballheimer, Viktor; Wille, Frank; Weber, Mike; Qiao, Linan; Droste, Bernhard Static and dynamic calculation approaches for mechanical design assessment of type B packages for radioactive material transport - 10193 2010 WM2010 Conference (Proceedings) WM2010 Conference Phoenix, Arizona, USA 2010-03-07 2010-03-11 1 9 2016-02-19 OPUS4-23216 Zeitschriftenartikel Dreßler, Martin; Dombrowski, Felix; Simon, Ulla; Börnstein, Julian; Hodoroaba, Vasile-Dan; Feigl, Michael; Grunow, Sabrina; Gildenhaar, Renate; Neumann, Martin Influence of gelatine coatings on compressive strength of porous hydroxyapatite ceramics Porous ceramics prepared by the foam replication technique have a high porosity and low mechanical stability. It has been reported that coating such porous ceramics with gelatin allows for an improved compressive strength. Little details regarding the influence of important gelatin parameters such as concentration, temperature and drying conditions as well as bloom number which is a measure of the gel rigidity, on this toughening effect are available. This paper investigates the influence of these parameters on compressive strength of gelatin coated porous hydroxyapatite ceramics. It was found that concentration in the gelatin sols has a marked impact whereas sol temperature, bloom number and differing conditions during subsequent drying have only little influence on the compressive strength of the coated ceramics. Oxford Elsevier Ltd. European Ceramic Society 2011 Journal of the European Ceramic Society 31 4 523 529 10.1016/j.jeurceramsoc.2010.11.004 2016-02-19 OPUS4-23851 Beitrag zu einem Tagungsband Neumann, Martin; Wille, Frank Rechnerische Simulation des mechanischen Verhaltens von holzgefüllten Stoßdämpfern von Transportbehältern für radioaktive Stoffe Basierend auf Fallversuchen mit Transportbehältern für radioaktive Stoffe sowie auf einem Versuchsprogramm mit Holzproben wurden die Energieabsorptionsmechanismen identifiziert und ein Modell für das Verhalten von Fichtenholz bei axialer Belastung entwickelt. Das Modell zieht für die Kompression von Holz die seitliche Dehnungsbehinderung - im kontinuumsmechanischen Zusammenhang wäre das die Mehrachsigkeit des Spannungszustandes im Kontinuum - in Betracht. Die Energie, die vom Holz absorbiert werden kann, ist umso größer, je größer die seitliche Dehnungsbehinderung ist. Für die Modellierung mit Finite Elemente Methoden wurden verschiedene Modellierungsstrategien untersucht, keine der vorgeschlagenen Modellierungsstrategien war in der Lage, dass Verhalten von Holz bei Druckbeanspruchung und großen Deformationen inkl. der Entfestigung zu modellieren. Bei Verwendung einer entfestigenden Fließkurve zeigt das Modell ausgeprägte Netzabhängigkeiten und numerischen Instabilitäten. Für die Modellierung der Entfestigung mit Hilfe einer von der Mehrachsigkeit des Spannungszustandes gesteuerten Fließflächenevolution ist kein geeignetes Materialmodell vorhanden. Anhand der Simulation eines Fallversuchs mit einem Behälterkörper und stoßdämpfenden Bauteilen im Maßstab 1:2 wurde gezeigt, dass zwar eine vollständige Modellierung des Stoßdämpferverhaltens inkl. Entfestigung nicht möglich war, aber das Stoßdämpferverhalten mit einer nicht-entfestigenden Fließkurve sinnvoll modelliert werden konnte. Eine Verifikation des Modellierungsansatzes am real zu modellierenden Bauteil ist zwingend erforderlich. Wenn signifikante Änderungen zwischen Verifikations- und Simulationsobjekt auftreten, ist die Zuverlässigkeit der Rechenergebnis als gering zu bewerten. Nur wenn die auftretenden Kompressionsmechanismen durch eine Analyse des Stoßdämpferholzes bestimmt werden können, ist eine zuverlässige Ermittlung von Stoßdämpferkräften- und verformungen möglich. Deutsches Atomforum e.V. / Kerntechnische Gesellschaft e.V. 2011 Jahrestagung Kerntechnik 2011 (Proceedings) Jahrestagung Kerntechnik 2011 Berlin, Germany 17.05.2011 19.05.2011 1 6 2016-02-19 OPUS4-26448 Zeitschriftenartikel Komann, Steffen; Neumann, Martin; Ballheimer, Viktor; Wille, Frank; Weber, Mike; Qiao, Linan; Droste, Bernhard Mechanical assessment within type B packages approval: application of static and dynamic calculation approaches 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. Ashford Ramtrans Publ. 2011 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 22 4 179 183 10.1179/1746510911Y.0000000012 2016-02-19 OPUS4-29764 Vortrag Neumann, Martin Reflection on BAM design assessment of TN24E spent fuel transport package 2013 PATRAM 2013 PATRAM 2013 San Francisco, CA, USA 2013-08-18 2013-08-23 2016-02-20 OPUS4-56342 Vortrag Neumann, Martin Friction coefficients for wood-wood and wood-steel contacts The friction at the interfaces between pieces of wood and steel is of crucial importance for the impact and energy absorption in impact limiters of transport casks for radioactive material. Here, the friction coefficient for the combinations wood-wood and wood-steel was measured in the temperature range between -40°C and 90°C. Results show decreasing friction with increasing temperature, ranging from 0.43 at -40°C to 0.22 for 90°C for wood-steel combinations and from 0.3 at -40°C to 0.24 at 90°C for a wood-wood combination. 2022 Sandia-BAM Workshop Berlin, Germany 21.11.2022 21.11.2022 2022-11-22 OPUS4-56343 Beitrag zu einem Tagungsband Gröke, Carsten; Neumann, Martin; Komann, Steffen; Wille, Frank Anforderungen an die Bauartprüfung und Maßnahmen zur Qualitätssicherung für nicht zulassungspflichtige Versandstücke Überblick über die Regelwerksanforderungen an die Bauarten von nicht zulassungspflichtigen Versandstücken, sowie die zu erfüllenden Maßnahmen zur Qualitätssicherung für die Auslegung, die Herstellung und den Betrieb. 2019 Kontec 2019 Tagungsband - Proceedings KONTEC 2019 Dresden, Germany 27.03.2019 136 142 2022-11-23 OPUS4-53180 Beitrag zu einem Tagungsband Schubert, Sven; Reichardt, Adrian; Wille, Frank; Komann, Steffen; Neumann, Martin Introduction of an ageing management approach for packages for the transport of radioactive materials 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. Mount Laurel, NJ Institute of Nuclear Materials Management (INMM) European Safeguards Research and Development Association (ESARDA) 2021 Proceedings of the INMM & ESARDA Joint Annual Meeting INMM & ESARDA Joint Annual Meeting Online meeting 30.08.2021 01.09.2021 1 6 2021-09-03 OPUS4-55375 Beitrag zu einem Tagungsband Gleim, Tobias; Neumann, Martin; Linnemann, Konrad; Komann, Steffen; Wille, Frank Fracture Mechanical Analyses of a Welding Seam of a Thick-Walled Transport Package 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. 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. 2022 Proceedings of the ASME 2022 Pressure Vessels & Piping Conference Pressure Vessels & Piping Conference® 2022 Las Vegas, NV, USA 17.07.2022 22.07.2022 1 9 2022-07-27 OPUS4-30219 Beitrag zu einem Tagungsband Eisenacher, Germar; Scheidemann, Robert; Neumann, Martin; Wille, Frank; Droste, Bernhard Crushing characteristics of spruce wood used in impact limiters of type B packages Omnipress Institute of Nuclear Materials Management (INMM) 2013 PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials (Proceedings) PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials San Francisco, CA, USA 2013-08-18 2013-08-23 1 10(?) 2016-02-20 OPUS4-30270 Beitrag zu einem Tagungsband Neumann, Martin; Wille, Frank; Linnemann, Konrad; Schubert, Sven; Ballheimer, Viktor; Sterthaus, Jens; Droste, Bernhard Reflection on BAM mechanical design assessment of TN®24E spent fuel transport package TN®24 E, a new package design, was developed and applied for by Areva TN for German transport approval certificate. The certificate was issued by BfS, Federal Office for Radiation Protection, on 24th of July 2013. The package is designed as a dual purpose cask for transport and storage of up to 21 PWR spent fuel assemblies from German NPPs. BAM is the German competent authority responsible for the design assessment of RAM packages regarding mechanical and thermal safety cases, activity release analysis and all issues of quality assurance during manufacturing and operation of packages. Certain assessment experiences as well as new developments resulting from the BAM TN®24E approval procedure are presented. The mechanical safety case of the TN®24E is based mainly on finite element calculations, which were verified by the TN®81 1/3 scale drop test program performed at BAM. Thermal analyses rely upon calculations, while the activity release criterion is based upon leakage rate results of TN®81 drop tests. The BAM-GGR 012 guideline for the analysis of bolted lid and trunnion systems has been fully implemented. Due to requirements by BAM, AREVA TN developed a new assessment strategy for fracture mechanical evaluation of welding seams. The material qualification and documentation is also an important aspect of BAM assessment; the qualification of borated aluminum basket material, the determination of strength values for thermal aged hardened aluminum alloys for the basket or consideration of high burn-up fuel assemblies are remarkable issues in this context. In addition, the consideration of the material compatibility, especially taking into account a transport after 40 years of dry interim storage in German facilities, has gained significant importance in the licensing process of the TN®24E. Next to obvious mechanical issues such as the assessment of shell ovalization under 9 m drop test scenario and its impact on basket load, thermo-mechanical interactions had to be addressed in the safety case. Due to BAM requirements, AREVA TN performed a full thermo-mechanical analysis of the cask behavior under fire test conditions. Omnipress Institute of Nuclear Materials Management (INMM) 2013 PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials (Proceedings) PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials San Francisco, CA, USA 18.08.2013 23.08.2013 1 12 2016-02-20 OPUS4-30653 Beitrag zu einem Tagungsband Eisenacher, Germar; Wille, Frank; Droste, Bernhard; Neumann, Martin Modeling of wood filled impact limiters for transport packages - 14111 Packages for the transport of SNF and HLW are usually equipped with impact limiters to reduce the loads that result from the regulatory 9 m drop test. A common impact limiter design in Germany is a welded steel sheet structure filled with wood. The material wood is the main energy absorber, while the steel sheet provides the integrity of the impact limiter. The IAEA allows mechanical safety cases of transport packages to be carried out computationally, as long as the models used are reliable. In this context, a Finite Element (FE) modeling approach for wood and its application to impact limiters in the calculation of a 9 m drop test is presented. A user material model for wood was developed for the dynamic FE-Code LS-DYNA. Its features are based on a series of crush tests with spruce wood specimens. The model considers wood as a material with transversely isotropic properties, i.e. in the directions parallel and perpendicular to the fiber. The plastic material behavior depends on the state of stress. This has shown to be important to account for the lateral constraint of wood in impact limiters resulting from steel sheet encapsulation. Lateral constraint or respectively, a multiaxial stress state, increases the compression strength level of wood, limits the softening effect and increases the hardening effect. Lateral constraint also increases volumetric and reduces deviatoric deformation. The wood material model considers various hardening and softening characteristics via input flow curves. It considers effects of temperature and strain rate on strength as well. The development of a multi-surface yield criterion and a plastic potential that enables the user input of plastic Poisson's ratios were the challenges during the development of material model. A dynamic FE calculation of a horizontal drop test with an 18,000 kg test package was performed. The wood material model was used to model the wooden impact limiter inlays. The impact limiter deformation and the package deceleration were compared to the experimental drop test results to rate the performance of the wood material model. WM Symposia, Inc. 2014 WM2014 Conference (Proceedings) 978-0-9836186-3-8 WM2014 Conference Phoenix, Arizona, USA 02.03.2014 06.03.2014 1 10 2016-02-20 OPUS4-23793 Vortrag Neumann, Martin Rechnerische Simulation des mechanischen Verhaltens von holzgefüllten Stoßdämpfern von Transportbehältern für radioaktive Stoffe 2011 Jahrestagung Kerntechnik, Berliner Congress Center (BBC) Jahrestagung Kerntechnik, Berliner Congress Center (BBC) Berlin, Germany 2011-05-17 2011-05-19 2016-02-19 OPUS4-23384 Beitrag zu einem Tagungsband Komann, Steffen; Neumann, Martin; Ballheimer, Viktor; Wille, Frank; Weber, Mike; Qiao, Linan; Droste, Bernhard Mechanical assessment within type B packages approval - the application of static and dynamic calculation approaches PATRAM 2010 PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials (Proceedings) PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials London, UK 2010-10-03 2010-10-08 1 8(?) 2016-02-19 OPUS4-18625 Zeitschriftenartikel Musolff, André; Müller, Karsten; Neumann, Martin; Kadji, Arsène Brice; Droste, Bernhard Results of full scale CONSTOR® V/TC prototype 9 m horizontal drop test Ashford Ramtrans Publ. 2008 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 19 4 228 232 10.1179/174651008X382951 2016-02-19 OPUS4-22980 Zeitschriftenartikel Neumann, Martin; Herter, Jürgen; Droste, Bernhard; Hartwig, S. Compressive behaviour of axially loaded spruce wood under large deformations at different strain rates Impact limiting components of packages for the transport of radioactivematerials are often designed as wood filled steel constructions. Wood absorbs major part of the impact energy in order to minimise the impact load acting upon the containment. Dynamic impact experiments with wood filled impact limiters showed different crushing mechanisms for axially loaded wood depending on their lateral constraint. Tests on spruce wood samples (Picea abies) were performed in order to clarify the influence of strain rate from static to 30 s-1 on a) compression strength, b) stress at a global strain level of 50%, and c) energy absorption capacity at 50% deformation, including statistical evaluation of the results. Results were as follows: strain rate increase led to significantly higher compression strength, stress and strain energy at a strain level of 50%. Lateral strain restriction had no effect on compression strength; it had a significant effect on stress and strain energy at strain level of 50%. Therefore, the definition of a general yield curve for wood under large deformations is not possible, the yield curve has to be chosen taking into account lateral constraints. Berlin ; Heidelberg Springer 2011 European journal of wood and wood products 69 3 345 357 10.1007/s00107-010-0442-x 2016-02-19 OPUS4-23684 Beitrag zu einem Tagungsband Eisenacher, Germar; Scheidemann, Robert; Neumann, Martin; Sterthaus, Jens; Kasparek, Eva Maria; Völzke, Holger Stauchversuche mit querdehnungsbehinderten Fichtenholzproben verschiedener Faserorientierungen bei veränderlicher Dehnrate Im Zuge des Forschungsvorhabens ENREA (Entwicklung rechnerischer Analysemethoden für stoßdämpfende Strukturen beim Anprall oder Absturz von Abfallgebinden) führt die BAM systematische Untersuchungen an stoßdämpfenden Werkstoffen, unter anderem an Fichtenholz, durch. Zweck der mit diesen Untersuchungen erzeugten Datenbasis ist die Erstellung und Parametrierung eines Finite-Elemente- (FE-) Materialmodells, das die Modellierung holzgefüllter stoßdämpfender Bauteile von Transportbehältern für radioaktive Stoffe in der FE-Simulation ermöglichen soll. Anhand von Ergebnissen aus der ersten Versuchsphase werden der Einfluss der Dehnrate und der Faserorientierung auf das Kraft-Verformungs-Verhalten von Fichtenholz diskutiert. Anschließend wird die rechnerische Modellierung von Fichtenholz diskutiert und die Anforderungen an ein Materialmodell werden erläutert. Kerntechnische Gesellschaft e.V. 2011 KONTEC 2011 - 10. Internationales Symposium "Konditionierung radioaktiver Betriebs- und Stilllegungsabfälle" (Proceedings) KONTEC 2011 - 10. Internationales Symposium "Konditionierung radioaktiver Betriebs- und Stilllegungsabfälle" Dresden, Germany 06.04.2011 08.04.2011 465 478 2016-02-19 OPUS4-37850 Beitrag zu einem Tagungsband Neumann, Martin; Wille, Frank; Droste, Bernhard Introduction of BAM safety assessment experience feedback list BAM as competent authority regarding assessment of mechanical and thermal design, activity release and quality assurance aspects of SNF and HLW transport packages developed a thesaurus of experience feedback topics from recent approval procedures. The list is structured according to the European PDSR guide. It involves issues, which from BAM point of view, needed clarification during last package design assessment procedures. The list contains issues from operation (e.g. deactivation of handling lugs not intended for package handling), maintenance (e.g. leak tightness of impact limiting devices) to technical assessment (e.g. formation of hydrogen by radiolysis and its impact on pressure and ignitability, consideration of ageing mechanisms, thermo-mechanical assessment, impact of gaps between content and flask, spent fuel behaviour) as well as to general and specific safety analysis report requirements (e.g. report structure and required data). 2016 Proceedings of PATRAM 2016 PATRAM 2016 Kobe, Japan 18.09.2016 23.09.2016 Paper 4002, 1 2016-10-18 OPUS4-37852 Vortrag Neumann, Martin Introduction of BAM safety assessment experience feedback list BAM as competent authority regarding assessment of mechanical and thermal design, activity release and quality assurance aspects of SNF and HLW transport packages developed a thesaurus of experience feedback topics from recent approval procedures. The list is structured according to the European PDSR guide. It involves issues, which from BAM point of view, needed clarification during last package design assessment procedures. The list contains issues from operation (e.g. deactivation of handling lugs not intended for package handling), maintenance (e.g. leak tightness of impact limiting devices) to technical assessment (e.g. formation of hydrogen by radiolysis and its impact on pressure and ignitability, consideration of ageing mechanisms, thermo-mechanical assessment, impact of gaps between content and flask, spent fuel behaviour) as well as to general and specific safety analysis report requirements (e.g. report structure and required data). 2016 PATRAM 2016 Kobe, Japan 18.09.2016 23.09.2016 2016-10-18 OPUS4-37848 Vortrag Neumann, Martin Experience feedback from BAM safety assessment of transport packages In order to facilitate approval procedures and reduce effort BAM has filed a list of recently encountered issues during different approval procedures. This presentation shows different examples from the list, which are structured according to the PDSR guide. 2016 RAM Tage Berlin, Germany 16.03.2016 17.03.2016 2016-10-18 OPUS4-33447 Vortrag Neumann, Martin Experience feedback from BAM safety assessment of transport packages 2015 10th Int. Conference on Transport and Storage of Radioactive Materials 10th Int. Conference on Transport and Storage of Radioactive Materials Oxford, GB 2015-05-19 2015-05-21 2016-02-20 OPUS4-33420 Beitrag zu einem Tagungsband Neumann, Martin; Wille, Frank; Droste, Bernhard Experience feedback from BAM safety assessment of transport packages BAM as competent authority regarding assessment of mechanical and thermal design, activity release and quality assurance measures of Type-B(U) transport packages developed a thesaurus of experience feedback topics from recent assessment procedures. The list is structured according to the European PDSR guide. It involves issues, which from BAM's point of view, needed clarification during the last package design assessment procedures. The list contains issues from Operation (e.g. deactivation of handling lugs not intended for package handling), maintenance (e.g. leak tightness of impact limiting devices) to technical assessment (e.g. formation of hydrogen by radiolysis and its impact on pressure and ignitability, consideration of ageing mechanisms, thermo-mechanical assessment, impact of gaps between content and flask) as well as to general and specific safety analysis report requirements (e.g. report structure and required data). 2015 RAMTRANS 2015 - 10th International conference on radioactive materials transport and storage (Proceedings) RAMTRANS 2015 - 10th International conference on radioactive materials transport and storage Oxford, UK 19.05.2015 21.05.2015 1 7 2016-02-20 OPUS4-45091 Beitrag zu einem Tagungsband Neumann, Martin; Eisenacher, Germar; Schönfelder, Thorsten; Wille, Frank Finite element simulation of the crush of package components made of encapsulated wood Typical transport packages used in Germany are equipped with encapsulated wooden impact limiting devices. We would like to present the current status regarding the development of a Finite Element (FE) material model for the crush of wood for the FE-code LS-DYNA. The crush of is a phenomenon governed by macroscopic fracture. Here, we would like to reproduce fracture and failure mechanisms over the continuous volume. In a first step we altered an existing LS-DYNA material model for foams, which considers an ellipse shaped yield surface. For the use for longitudinal compression of wood, we modified the existing material model to consider the deviatoric strain for the evolution of the yield surface as well. This is in accordance with the results of crush tests with spruce wood specimens, where the crushing deformation was rather deviatoric for uniaxial stress states and rather volumetric for multiaxial stress states We rate the basic idea of this approach to be reasonable, though other problems exist regarding the shape of the yield surface and the assumption of isotropic material properties. Therefore we developed a new transversal isotropic material model with two main directions, which considers different yield curves according to the multiaxiality of the stress state via a multi-surface yield criterion and a non-associated flow rule. The results show the ability to reproduce the basic strength characteristics of spruce wood. Nevertheless, problems with regularization etc. show that additional investigations are necessary. 2018 11th International Conference on the Transport, Storage and Disposal of Radioactive Materials 11th International Conference on the Transport, Storage and Disposal of Radioactive Materials London, UK 15.05.2018 17.05.2018 Paper 18517, 1 12 2018-06-04 OPUS4-45093 Vortrag Neumann, Martin Finite element simulation of the crush of package components made of encapsulated wood Typical transport packages used in Germany are equipped with encapsulated wooden impact limiting devices. We would like to present the current status regarding the development of a Finite Element (FE) material model for the crush of wood for the FE-code LS-DYNA. The crush of is a phenomenon governed by macroscopic fracture. Here, we would like to reproduce fracture and failure mechanisms over the continuous volume. In a first step we altered an existing LS-DYNA material model for foams, which considers an ellipse shaped yield surface. For the use for longitudinal compression of wood, we modified the existing material model to consider the deviatoric strain for the evolution of the yield surface as well. This is in accordance with the results of crush tests with spruce wood specimens, where the crushing deformation was rather deviatoric for uniaxial stress states and rather volumetric for multiaxial stress states We rate the basic idea of this approach to be reasonable, though other problems exist regarding the shape of the yield surface and the assumption of isotropic material properties. Therefore we developed a new transversal isotropic material model with two main directions, which considers different yield curves according to the multiaxiality of the stress state via a multi-surface yield criterion and a non-associated flow rule. The results show the ability to reproduce the basic strength characteristics of spruce wood. Nevertheless, problems with regularization etc. show that additional investigations are necessary. 2018 11th International Conference on the Transport, Storage and Disposal of Radioactive Materials London, UK 15.05.2018 17.05.2018 2018-06-04 OPUS4-45095 Posterpräsentation Neumann, Martin Assessment of Quality Management for Transport Packages not requiring Authority Design Approval The poster presents the german approach for the assessment of quality management systems for transport packages for radioactive material not requiring authority design approval. As legal basis the IAEA regulations, the ADR as well as the GGVSEB are highlighted and examples for these transport packages are given. The GGR 016 is mentioned, main duties and responsibilities as well as the manufacturing and quality surveillance system are described. 2018 11th International Conference on the Transport, Storage and Disposal of Radioactive Materials London, UK 15.05.2018 17.05.2018 2018-06-06 OPUS4-49056 Vortrag Neumann, Martin Requirements for management systems for manufacturing of transport packages: the new revision of BAM-GGR 011 guideline In accordance with IAEA SSR-6 para 306 a management system shall be established and implemented to ensure compliance with the relevant provisions of the IAEA regulations. BAM has issued an update of the guideline: the BAM-GGR 011. The new revision describes necessary quality assurance measures for design, manufacture, testing, documentation, use, maintenance and inspection of packagings for package designs requiring competent authority approval for the transport of radioactive material. The measures can be categorised as system-related and design-related. They are independently approved and monitored by the German competent authority BAM and its authorised expert (BAM/T). The qualification of the organisation applying for the design approval certificate is reviewed in the context of the design approval procedure. The quality assurance measures for manufacture consist of three main steps. Pre-assessment of manufacturing documents such as quality plans, specifications etc., Manufacturing inspections according the pre-assessed documents and inspection before commissioning including documentation review. Periodic inspections during operation as well as relevant specifications for use and maintenance ensure that the properties specified in the approval certificate are preserved over the package life time. Special provisions for the return on experience regarding operational feedback for design, manufacture, use, maintenance and inspection are given. Special focus shall be given here to the rearranged and meanwhile established system of manufacturing inspections. This includes more transparent roles for a) the producers authorised inspection 11282 representative, b) the independent inspection expert (S), acting on behalf of the manufacturer with acceptance of BAM, and c) BAM or its authorised expert (BAM/T). Additional attention shall be drawn to the management of deviations during manufacturing and provisions for maintenance and periodic inspections. 2019 19th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 2019 New Orleans, LA, USA 04.08.2019 09.08.2019 2019-09-23 OPUS4-49059 Beitrag zu einem Tagungsband Neumann, Martin; Schilling, O.; Kuschke, Christian; Darnstädt, A.; Schubert, Sven; Günther, U.; Wille, Frank Requirements for management systems for manufacturing of transport packages: the new revision of BAM-GGR 011 guideline In accordance with IAEA SSR-6 para 306 a management system shall be established and implemented to ensure compliance with the relevant provisions of the IAEA regulations. BAM has issued an update of the guideline: the BAM-GGR 011. The new revision describes necessary quality assurance measures for design, manufacture, testing, documentation, use, maintenance and inspection of packagings for package designs requiring competent authority approval for the transport of radioactive material. The measures can be categorised as system-related and design-related. They are independently approved and monitored by the German competent authority BAM and its authorised expert (BAM/T). The qualification of the organisation applying for the design approval certificate is reviewed in the context of the design approval procedure. The quality assurance measures for manufacture consist of three main steps. Pre-assessment of manufacturing documents such as quality plans, specifications etc., Manufacturing inspections according the pre-assessed documents and inspection before commissioning including documentation review. Periodic inspections during operation as well as relevant specifications for use and maintenance ensure that the properties specified in the approval certificate are preserved over the package life time. Special provisions for the return on experience regarding operational feedback for design, manufacture, use, maintenance and inspection are given. Special focus shall be given here to the rearranged and meanwhile established system of manufacturing inspections. This includes more transparent roles for a) the Producers authorised inspection 11282 representative, b) the independent inspection expert (S), acting on behalf of the manufacturer with acceptance of BAM, and c) BAM or its authorised expert (BAM/T). Additional attention shall be drawn to the management of deviations during manufacturing and provisions for maintenance and periodic inspections. 2019 Proceedings of the 19th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 2019 19th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 2019 New Orleans, LA, USA 04.08.2019 09.08.2019 Paper 1128, 1 2019-09-23 OPUS4-50981 Beitrag zu einem Tagungsband Quercetti, Thomas; Wille, Frank; Neumann, Martin; Linnemann, Konrad Baraldi, P.; Di Maio, F.; Zio, E. Safety Evaluation of a Package for Radioactive Waste by Full-Scale Drop Testing As part of the evaluation of a package for the safe transport of radioactive waste the regulations of the IAEA International Atomic Energy Agency shall be fulfilled. The regulations define requirements for the package and specify mechanical and thermal test conditions. Different methods are allowed for the test performance to demonstrate compliance with the regulations. Next to calculational approaches and the use of models of an appropriate scale, the performance of full-scale testing with prototype packages respectively full-scale models is applied. The use of full-scale models has several advantages within the complete safety assessment procedure for a transport package approval. Scaling and corresponding similarity questions don't have to be considered, additional material investigations can be limited and analyses to transfer test results to the original package design are reduced in number and complexity. Additionally, experience for future serial design procedures can be built up during manufacturing and assembling of the test model. BAM operates different drop and fire test facilities south of Berlin, Germany. BAM has started to perform a drop test campaign with a full-scale model of 120 metric tons weight for a transport package approval procedure. The paper describes experience with test preparation, drop performance and additional analyses. The measurement concept is explained and test goals regarding the package safety assessment and evaluation of safety margins are introduced. Singapore Research Publishing Services 2020 Proceedings of the 30th European Safety and Reliability Conference and 15th Probabilistic Safety Assessment and Management Conference (ESREL2020 PSAM15) 987-981-14-8593-0 30th European Safety and Reliability Conference and 15th Probabilistic Safety Assessment and Management Conference (ESREL2020 PSAM15) Online meeting 01.11.2020 06.11.2020 Paper 3809,1 8 2020-11-16 OPUS4-50049 Vortrag Neumann, Martin Maintenance and periodic inspections for packagings not requiring CA-approval In this presentation the main requirements of BAM-GGR 016 regarding maintenance and periodic inspections were explained. BAM ensures during acceptance of the quality management program that specific and relevant instructions for maintenance and periodic inspections are developed and handed to the operator of the packaging. Examples are given. 2019 FORO Iberoamericano Madrid, Spain 25.11.2019 29.11.2019 2019-12-19 OPUS4-41613 Beitrag zu einem Tagungsband Neumann, Martin; Eisenacher, Germar; Schönfelder, Thorsten; Wille, Frank Development of a material model for the crush of spruce wood Typical transport packages used in Germany are equipped with wooden impact limiting devices. In this paper we give an overview of the latest status regarding the development of a finite element material model for the crush of spruce wood. Although the crush of wood - mainly in longitudinal direction - is a phenomenon governed by macroscopic fracture and failure of wood fibres we smear fracture and failure mechanisms over the continuous voume. In first step we altered an existing LS-DYNA material model for foams, which considers an ellipse shaped yield surface written in terms of the first two stress invariants. The evolution of the yield surface in the existing model depends on the volumetric strain only. For the use with spruce wood, we modified the existing material model to consider the deviatoric strain for the evolution of the yield surface as well. This is in accordance with the results of crush tests with spruce wood specimens, where the crushing deformation was rather deviatoric for uniaxial stress states and rather volumetric for multiaxial stress states We rate the basic idea of this approach to be reasonable, though other problems exist regarding the shape of the yield surface and the assumption of isotropic material properties. Therefore we developed a new transversal isotropic material model with two main directions, which considers different yield curves according to the multiaxiality of the stress state via a multi-surface yield criterion and a non-associated flow rule. The results show the ability to reproduce the basic strength characteristics of spruce wood. Nevertheless, problems with regularization etc. show that additional investigations are necessary. ASME 2017 Proceedings of ASME PVP 2017 7 978-0-7918-5802-8 ASME PVP 2017 Waikaloa, HY, USA 16.07.2017 20.07.2017 Article UNSP V007T07A037, 1 9 2017-08-25 OPUS4-41617 Posterpräsentation Neumann, Martin Development of a material model for the crush of spruce wood Typical transport packages used in Germany are equipped with wooden impact limiting devices. In this paper we give an overview of the latest status regarding the development of a finite element material model for the crush of spruce wood. Although the crush of wood - mainly in longitudinal direction - is a phenomenon governed by macroscopic fracture and failure of wood fibres we smear fracture and failure mechanisms over the continuous voume. In first step we altered an existing LS-DYNA material model for foams, which considers an ellipse shaped yield surface written in terms of the first two stress invariants. The evolution of the yield surface in the existing model depends on the volumetric strain only. For the use with spruce wood, we modified the existing material model to consider the deviatoric strain for the evolution of the yield surface as well. This is in accordance with the results of crush tests with spruce wood specimens, where the crushing deformation was rather deviatoric for uniaxial stress states and rather volumetric for multiaxial stress states We rate the basic idea of this approach to be reasonable, though other problems exist regarding the shape of the yield surface and the assumption of isotropic material properties. Therefore we developed a new transversal isotropic material model with two main directions, which considers different yield curves according to the multiaxiality of the stress state via a multi-surface yield criterion and a non-associated flow rule. The results show the ability to reproduce the basic strength characteristics of spruce wood. Nevertheless, problems with regularization etc. show that additional investigations are necessary. 2017 ASME PVP 2017 Waikaloa, HY, USA 16.07.2017 20.07.2017 2017-08-25 OPUS4-57732 Beitrag zu einem Tagungsband Quercetti, Thomas; Wille, Frank; Neumann, Martin; Linnemann, Konrad Full-scale drop testing with a heavy-weight package for radioactive waste Packages for the transport of radioactive materials shall fulfil the requirements of the IAEA regulations for the safe transport. The requirements define mechanical and thermal test conditions including criteria ensuring the package design's ability to withstand severe accidents and provide a high level of technical safety. Different methods can be used for safety demonstration showing compliance with the regulations. The central part of a safety demonstration which is presented in this paper was a comprehensive drop test program with a full-scale model of a transport package accompanied by pre- and post-test FE analyses. Using full-scale drop test models allow the benefit that similarity and scaling issues become a significant smaller issue, additional material investigations can be limited and analyses for transferring test results to the original package design are reduced. Additionally, experience for the future serial packaging manufacturing and handling procedures can be collected in a very early state of the design approval process. The pre-test finite element analyses derived and justified the drop test program consisting of several drop sequences with different drop orientations of the specimen. The performance and the results of the drop test sequences shows the manageability and the advantage e.g., in view of the direct availability of test results for the package licensing. On the other hand, the drop test performance shows the difficulties during handling and the need for additional equipment during preparation of the specimen. The package presented was intended for the transport and storage of compacted radioactive waste from reprocessing of spent nuclear fuel assemblies - designed and applied for approval by the AGC consortium. The project ended in 2021. The package design was characterized by a cask body made of a forged thick stainless-steel shell, a bolted double lid system with metallic gaskets and wood filled shock absorbers at both ends. The total mass of the entire transport package including content was 120,000 kg, the total length was about 7000 mm and the diameter approximately 3000 mm, both measures include the shock absorbers. The paper provides an insight into the performance of a full-scale drop testing campaign within the package safety evaluation and shows some selected test results. 2023 Proceedings of the 20th International Symposium on the Packaging and Transportation of Radioactive Materials 20th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 22) Juan-Les-Pins, France 11.06.2023 15.06.2023 1 10 2023-06-22 OPUS4-57770 Beitrag zu einem Tagungsband Schubert, Sven; Reichardt, Adrian; Müller, Lars; Neumann, Martin; Komann, Steffen; Wille, Frank Introduction of the German ageing management guide for packages for transport of radioactive materials 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. London World Nuclear Transport Institute (WNTI) 2023 Proceedings of the 20th international symposium on the packaging and transportation of radioactive materials PATRAM22 - 20th International Symposium on the Packaging and Transportation of Radioactive Materials Juan-les-Pins, France 11.06.2023 15.06.2023 1 10 2023-06-28 OPUS4-57696 Beitrag zu einem Tagungsband Gleim, Tobias; Neumann, Martin; Linnemann, Konrad; Wille, Frank Fracture Mechanical Analyses of a Welding Seam of a Thick-Walled Transport Package The safety demonstration of heavy weight type B transport packages used for storing spent nuclear fuel (SNF) or radioactive waste is ensured by a combination of physical testing and numerical calculations. While experiments are performed in accordance with the IAEA regulations for selected drop scenarios, Finite-Element-Method (FEM) simulations are used to predict the most damaging case and to investigate additional drop positions. BAM as competent authority in Germany has performed different investigations of a welding seam for a typical large transport package made of A508 forged steel, where the bottom plate is welded to the cylindrical shell. The package has a mass of approx. 120 t. Results of physical drop tests with a full-scale model and accompanying preliminary FEM simulations are presented to determine the decisive stresses in the welding seam. A drop test only represents one set of a package and test parameters. A further parameter analysis is considered to account for allowable variations of packaging properties (e.g. resulting from the manufacturing process) and, based on IAEA requirements, the temperature dependence of the material behaviour. The results of the stress analyses from the drop test and the simulation form the basis and provide the input parameters for a fracture mechanics analysis. In addition to the IAEA specifications, further standards are taken into account for an in-depth investigation, see R6, BS 7910 and API 579-1/ASME FFS1. All the above-mentioned standards require a manufacturer-specific defect analysis with respect to size and position. Both result from the welding process and the following heat treatment regime. The maximum defect sizes are ensured with non-destructive test methods (such as ultrasonic or particle methods) as integral part of the manufacturing process of the welding seam. Another important parameter in the welding process is the residual stress (secondary stress). The combination of the primary and secondary stress determines the total stress in the welding seam. The most damaging case of the welding seam is determined and evaluated with help of the above-mentioned standards and taking into account the IAEA requirements with respect to defect sizes, material properties, primary and residual stress, yield strength etc. 2023 Proceedings of the 20th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 22 - The International Symposium on the Packaging and Transportation of Radioactive Materials Juan-Les-Pins, Antibes, France 11.06.2023 16.06.2023 1 10 2023-06-19 OPUS4-57702 Posterpräsentation Neumann, Martin Friction coefficients for wood-wood and wood-steel interfaces in impact limiters for transport casks Wood is widely used in impact limiters of transport casks for radioactive material. Encapsulated by an outer and inner steel structure, spruce wood is often applied in layers of alternating direction. The friction at the interfaces between these layers is of crucial importance for the impact and energy absorption e.g., at an accidental impact of a cask against a hard target. In order to get detailed information for corresponding numerical calculations, in this study the friction coefficient for the combinations wood-wood and wood-steel was measured in the temperature range between -40°C and 90°C according to the relevant stress conditions for such casks. Results show decreasing friction with increasing temperature, ranging from 0.43 at -40°C to 0.22 for 90°C for wood-steel combinations and from 0.3 at -40°C to 0.24 at 90°C to for a wood-wood combination. 2023 20th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 22) Juan-les-Pins, France 11.06.2023 15.06.2023 2023-06-19 OPUS4-57703 Beitrag zu einem Tagungsband Neumann, Martin; Quercetti, Thomas; Wille, Frank; Gröke, Carsten; Neumeyer, Tino Design assessment, approval of management systems and ageing aspects of transport packages for radioactive material not requiring competent authority approval of design Most transports of radioactive materials are carried out with packages not requiring competent authority approval of design. These encompass - in accordance with the IAEA SSR-6 regulations - packages of the classification excepted, Industrial packages Type 1, 2 and 3 and Type A packages. Currently an upsurge in number and variation of these package designs can be seen in Germany, resulting from the phase out of nuclear energy in Germany as well as e. g. increased use of radioactive material for medical purposes. A design assessment regarding the package safety is required in the international IAEA SSR-6 regulations. BAM operates facilities for the performance of all regulatory tests required such as drop towers for a wide range of package masses and dimensions, fire test, leak tightness measurements and pressure test facilities. Experiences with several package types are shown. Additionally, IAEA SSR-6 requires the establishment of a management system for design, manufacture, maintenance, and repair of the packaging as well as for the preparation, consigning, loading, carriage, unloading and receipt of the package. Relevant for Germany, BAM has published guidance material on the process of management system acceptance in the technical guide BAM-GGR 016. The requirements encompass quality management plans for the manufacturing of packages including independent manufacturing surveillance and specific instructions for operation, maintenance, and repair of packagings. Examples for management system specifics and requirements are given. Since the latest edition of the IAEA SSR-6 regulations an ageing evaluation including systematic ageing management measures are required for all kind of package types. BAM is going to update the guidance material BAM-GGR 016 to support the stakeholders with relevant information to fulfil the ageing aspect for packages not requiring competent authority approval. The paper explains how the ageing aspect may be included in the safety evaluation process and the management system measures and will give an outlook for the future guidance material. 2023 Proceedings of the 20th International Symposium on the Packaging and Transportation of Radioactive Materials 20th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 22) Juan-Les-Pins, Antibes, France 11.06.2023 15.06.2023 1 8 2023-06-19 OPUS4-57704 Vortrag Neumann, Martin Design assessment, approval of management systems and ageing aspects of transport packages for radioactive material not requiring competent authority approval of design Most transports of radioactive materials are carried out with packages not requiring competent authority approval of design. These encompass - in accordance with the IAEA SSR-6 [1] regulations - packages of the classification excepted, Industrial packages Type 1, 2 and 3 and Type A packages. Currently an upsurge in number and variation of these package designs can be seen in Germany, resulting from the phase out of nuclear energy in Germany as well as e. g. increased use of radioactive material for medical purposes. A design assessment regarding the package safety is required in the international IAEA SSR-6 [1] regulations. BAM operates facilities for the performance of all regulatory tests required such as drop towers for a wide range of package masses and dimensions, fire test, leak tightness measurements and pressure test facilities. Experiences with several package types are shown. Additionally, IAEA SSR-6 [1] requires the establishment of a management system for design, manufacture, maintenance, and repair of the packaging as well as for the preparation, consigning, loading, carriage, unloading and receipt of the package. Relevant for Germany, BAM has published guidance material on the process of management system acceptance in the technical guide BAM-GGR 016 [2]. The requirements encompass quality management plans for the manufacturing of packages including independent manufacturing surveillance and specific instructions for operation, maintenance, and repair of packagings. Examples for management system specifics and requirements are given. Since the latest edition of the IAEA SSR-6 [1] regulations an ageing evaluation including systematic ageing management measures are required for all kind of package types. BAM is going to update the guidance material BAM-GGR 016 [2] to support the stakeholders with relevant information to fulfil the ageing aspect for packages not requiring competent authority approval. The paper explains how the ageing aspect may be included in the safety evaluation process and the management system measures and will give an outlook for the future guidance material. 2023 20th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 22) Juan-les-Pins, France 11.06.2023 15.06.2023 2023-06-19 OPUS4-57705 Posterpräsentation Schilling, O.; Neumann, Martin System of Quality Assurance Measures in Manufacturing and Operation of Dual Purpose Casks for Spent Nuclear Fuel and High Level Waste in Germany German spent nuclear fuel and high level waste is stored in dry conditions in interim storage facilities until a final repository will be ready for operation in the future. Dual purpose casks are used for the packaging of the materials to ensure transportability at any time during long-term interim storage and fulfilling both requirements from interim storage as well as transport. Germany's 2011 decision to phase out utilization of nuclear energy has led to a high demand for casks for decommissioning power plants as quickly as possible. Cask serial production will continue at a high level for the next few years. In the process, a system of quality assurance measures ensures that every cask reliably complies with design specification according the transport approval certificate and storage license. When the first casks were manufactured in Germany about 40 years ago, quality assurance was oriented towards pressure vessel and general nuclear manufacturing. The system was continuously adapted to the state of the art. In particular serial production, globalization of manufacturing and deep supplier chains had to be taken into account. The system of quality assurance measures applied today for cask manufacturing shall be presented here. The quality assurance measures can be categorized as system-related and design-related. With respect to transport regulations for example, they are independently approved and monitored by the competent authority BAM and its authorized inspection experts. The qualification of the applicant is reviewed first in the context of the design approval procedure and then periodically. The qualification of component and cask manufacturers is also checked at the start of manufacturing and then periodically. Before the start of manufacturing documents such as quality plans are pre-assessed. Manufacturing and inspection are then performed according to the pre-assessed documents. Cask manufacturing is completed by a final inspection before commissioning. Periodic inspections during operation ensure preservation of the properties specified in the approval certificate over package life time. The type and the time interval of periodic inspections depend on the use of the package. For transport after interim storage a system of specific tests and inspections is prescribed. 2023 20th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 22) Juan-les-Pins, France 11.06.2023 15.06.2023 2023-06-19 OPUS4-57334 Beitrag zu einem Tagungsband Neumann, Martin; Gleim, Tobias; Gradt, Thomas; Wille, Frank Friction coefficients for wood-wood and wood-steel interfaces in impact limiters for transport casks Wood is widely used in impact limiters of transport casks for radioactive material. Encapsulated by an outer and inner steel structure, spruce wood is often applied in layers of alternating direction. The friction at the interfaces between these layers is of crucial importance for the impact and energy absorption e.g., at an accidental impact of a cask against a hard target. In order to get detailed information for corresponding numerical calculations, in this study the friction coefficient for the combinations wood-wood and wood-steel was measured in the temperature range between -40°C and 90°C according to the relevant stress conditions for such casks. Results show decreasing friction with increasing temperature, ranging from 0.43 at -40°C to 0.22 for 90°C for wood-steel combinations and from 0.3 at -40°C to 0.24 at 90°C to for a wood-wood combination. 2023 Proceedings of the 20th International Symposium on the Packaging and Transportation of Radioactive Materials 20th International Symposium on the Packaging and Transportation of Radioactive Materials Juan-les-Pins, France 11.06.2023 15.06.2023 1 11 2023-06-19 OPUS4-57787 Zeitschriftenartikel Neumann, Martin; Gleim, Tobias; Gradt, Thomas Friction coefficients for wood-wood and wood-steel high pressure contact under temperatures between -40 °C and 90 °C Wood is widely used in impact limiters of Transport casks for radioactive material. Encapsulated by an outer and inner Steel structure, spruce wood is offen applied in layers of altemating direction. The friction at the interfaces between these layers is of crucial importance for the impact and energy absorption e.g., at an accidental impact of a cask against a hard component. In order to get detailed Information for corresponding numerical calculations, in this study the friction coefficient for the combinations wood-wood and wood-steel was measured in the temperature ränge between -40 °C and 90 °C according to the relevant stress conditions for such casks. Results show decreasing friction with increasing temperature, ranging from 0.43 at -40 °C to 0.22 for 90 °C for wood-steel combinations and from 0.3 at -40 °C to 0.24 at 90 °C to for a wood-wood combination. expert verlag Gesellschaft für Tribologie e.V. 2023 Tribologie + Schmierungstechnik 70 2 5 12 10.24053/TuS-2023-0007 2023-06-29 OPUS4-59421 Beitrag zu einem Tagungsband Gleim, Tobias; Neumann, Martin; Linnemann, Konrad; Wille, Frank Welding Seam Safety Evaluation in a Thick-Walled Type B Transport Package The safety demonstration of heavy weight type B transport packages used for storing spent nuclear fuel (SNF) or radioactive waste is ensured by a combination of physical testing and numerical calculations. While experiments are performed in accordance with the IAEA regulations for selected drop scenarios, Finite-Element-Method (FEM) simulations are used to predict the most damaging case and to investigate additional drop positions. BAM as competent authority in Germany has performed different investigations of a welding seam for a typical large transport package made of A508 forged steel, where the bottom plate is welded to the cylindrical shell. The package has a mass of approx. 120 t. Results of physical drop tests with a full-scale model and accompanying preliminary FEM simulations are presented to determine the decisive stresses in the welding seam. A drop test only represents one set of a package and test parameters. A further parameter analysis is considered to account for allowable variations of packaging properties (e.g. resulting from the manufacturing process) and, based on IAEA requirements, the temperature dependence of the material behaviour. The results of the stress analyses from the drop test and the simulation form the basis and provide the input parameters for a fracture mechanics analysis. In addition to the IAEA specifications, further standards are taken into account for an in-depth investigation, see R6 [1], BS 7910 [2] and API 579-1/ASME FFS1 [3]. All the above-mentioned standards require a manufacturer-specific defect analysis with respect to size and position. Both result from the welding process and the following heat treatment regime. The maximum defect sizes are ensured with non-destructive test methods (such as ultrasonic or particle methods) as integral part of the manufacturing process of the welding seam. Another important parameter in the welding process is the residual stress (secondary stress). The combination of the primary and secondary stress determines the total stress in the welding seam. The most damaging case of the welding seam is determined and evaluated with help of the abovementioned standards and taking into account the IAEA requirements with respect to defect sizes, material properties, primary and residual stress, yield strength etc. 2023 Proceedings of the 20th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 22 - The International Symposium on the Packaging and Transportation of Radioactive Materials Juan-Les-Pins, Antibes 11.06.2023 16.06.2023 1 11 2024-01-25 OPUS4-59522 misc Neumann, Martin Maßnahmen zum Qualitäts- und Alterungsmanagement nicht zulassungspflichtiger Bauarten von Versandstücken zur Beförderung radioaktiver Stoffe Die BAM-GGR 016 erläutert die Anforderungen des ADR, RID, ADN und IMDG hinsichtlich notwendiger Maßnahmen zum Qualitäts- und Alterungsmanagement bei der Auslegung, Herstellung, Prüfung, Dokumentation, Gebrauch, Wartung und Inspektion von nicht-zulassungspflichtigen Versandstücken für radioaktive Stoffe für alle Bauarten von freigestellten Versandstücken, Industrieversandstücken des Typs IP-1, IP-2 und IP-3 und Versandstücken des Typs A. Revision 1 Berlin Bundesanstalt für Materialforschung und -prüfung (BAM) 2024 BAM-Gefahrgutregeln BAM-GGR 016 1 26 urn:nbn:de:kobv:b43-595229 https://creativecommons.org/licenses/by-nc-nd/4.0/deed.de 2024-02-19