TY - CONF A1 - Wille, Frank T1 - Bauartprüfung von Transportbehältern für verglaste Abfälle aus der Wiederaufarbeitung N2 - Aufgrund zwischenstaatlicher Verträge werden in den nächsten Jahrzehnten zahlreiche Transporte von hoch radioaktiven Abfällen notwendig. Die BAM führt die Bauartprüfung von dafür vorgesehenen Castor-Behältern durch. In diesem Zusammenhang sind 17 Fallprüfungen durchgeführt worden. Ergänzt werden diese durch komplexe numerische Analysen, die die BAM prüft und eigene Modellierungen vornimmt. Der Beitrag stellt darüber hinaus das mehrjährige Validierungsverfahren zur Akzeptanz der bruchmechanischen Berechnungswerkzeuge vor. T2 - VdTÜV Forum Kerntechnik CY - Berlin, Germany DA - 16.04.2018 KW - Transport KW - Bauartprüfung KW - Fallprüfungen KW - Radioaktive Stoffe PY - 2018 AN - OPUS4-44853 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Linnemann, Konrad A1 - Nehrig, Marko A1 - Musolff, André A1 - Wille, Frank T1 - Experience by BAM in the transport package safety assessment of German waste containers N2 - Transport and storage containers for low and midlevel radioactive waste are getting more and more of relevance due to the nuclear phase out decision in 2011. For higher activities Type B(U) approved waste containers will be needed for the shut down and dismantling phases of NPPs. It is expected that large quantities are required in the near future. German waste containers are generally approved for transport and interim storage and are also intended for the final disposal in the Konrad repository. BAM is involved in the authority licensing of transport package designs in Germany. In this context, BAM is responsible for the assessment of safe containment, mechanical, thermal and quality management issues. BAM also operates test facilities and performs drop as well as thermal tests during package licensing procedures. This paper summarizes our experience in the transport package design assessment of Type B(U) waste containers. A general overview of the approval process, the requirements and approaches BAM applies are described. Some examples are used to illustrate different aspects and technical issues we are addressing during the package assessment. In the first part of the paper the specific design aspects of German waste containers are described. Here, a general overview is given e.g. about closure systems, impact limiter designs, and the handling concepts. Furthermore, the wide range of radioactive content and their physical behavior including the impact on the packages assessment are described. The second part is focused on questions about the licensing and assessment process of German waste containers from the BAM authority point of view. The general approaches for the strategy of demonstration are outlined on the basis of the test conditions according to IAEA Regulations SSR-6. Furthermore, particular issues of the mechanical and thermal assessment with respect to the specific test conditions are discussed. For accident conditions of transport, aspects to be mentioned are e.g. the assessment of the lid bolts, the axial gap applied between content and lid, and the thermal behavior of the wood filled impact limiter after the fire test. However, issues of the assessment for routine and normal conditions of transport are addressed in this paper, too. The intention of this paper is introduce recent approval procedure experience in Germany, describing technical evaluation issues and so reduce rounds of questions during applications. T2 - 2018 WM Symposia CY - Phoenix, AZ, USA DA - 18.03.2018 KW - Transport packages KW - Safety assessment KW - Lowlevel and midlevel radioactive waste PY - 2018 SP - Paper 18469, 1 EP - 10 AN - OPUS4-44861 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Linnemann, Konrad A1 - Ballheimer, Viktor A1 - Sterthaus, Jens A1 - Rolle, Annette A1 - Wille, Frank A1 - Nasyrow, R. A1 - Papaioannou, D. A1 - Rondinella, V. A1 - Vlassopoulos, E. A1 - Pautz, A. T1 - Finite element modeling of spent fuel rod segments under bending loads N2 - Transport packages for spent nuclear fuel have to be assessed with respect to specific transport conditions which are defined in the regulations of the International Atomic Energy Agency. The physical state of the spent fuel and the fuel rod cladding as well as the geometric configuration of the fuel assemblies are important Inputs for the evaluation of the package capabilities under These conditions. Cracks or failures in the fuel rod cladding can cause the release of gas, volatiles or fuel particles into the cavity. The amount of substances in the cavity has to be considered in the assessment of the activity release and criticality safety. The mechanical analysis of the compound system formed by the fuel rod cladding and the spent fuel pellets is very difficult due to the limited knowledge of the material properties and the insufficient understanding of the interaction between pellets and cladding and between adjacent pellets. The variation of fuel assembly properties regarding cladding material, burn-up and the history of usage makes reliable predictions of the fuel rod behavior even harder. For a better understanding about the behavior of spent fuel rods, JRC and BAM have started a joint research project. In this context, JRC has developed a test device which allows quasi-static 3-point-bending test on fuel rod segments in the hot cell. The loads are applied with respect to the boundary conditions of the activity release assessment. This paper deals with the numerical calculation of a single fuel rod segment under bending load. The aim is to identify the governing mechanical parameters by the variation of constitutive assumptions, contact conditions, inner constraints, etc. This knowledge helps for the interpretation of the experimental results. Furthermore, the improved understanding about the behavior of the cladding-pellets system will be beneficial for the assessment of spent fuel transport conditions. T2 - SMIRT24 - 24th Conference on Structural Mechanics in Reactor Technology CY - Busan, Korea DA - 20.08.2017 KW - Finite element methods KW - Spent fuel assessment KW - Transport packages PY - 2017 SP - 1 EP - 8 AN - OPUS4-45316 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CHAP A1 - Nehrig, Marko A1 - Wille, Frank ED - Saegusa, Toshiari ED - Sert, Gilles ED - Völzke, Holger ED - Wille, Frank T1 - Internal Pressure build-up of Waste Packages with Wet Contents Under Fire Impact N2 - Intermediate level waste often contains residual water or other liquids. The liquids can be decomposed due to radiolysis and can also vaporize especially under fire impact. These pressure generating processes are described. One example for the pressure determination inside a closed cask is discussed using two different approaches: analytical and CFD KW - Wet Content KW - Pressure build-up KW - Type-B Package PY - 2018 SN - 978-981-3234-03-1 SP - 195 EP - 209 PB - World Scientific Publishing CY - Singapore ET - Erste AN - OPUS4-45301 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko A1 - Erenberg, Marina A1 - Feldkamp, Martin A1 - Bletzer, Claus A1 - Musolff, André A1 - Wille, Frank T1 - Large Scale IAEA Thermal Test with Wood filled Impact Limiters N2 - Packages for the transport of radioactive material are often equipped with impact limiters consisting of wood. Mostly this wood is encapsulated by steel sheets. The impact limiters are needed to ensure that the transport casks meet the IAEA safety requirements. According to the IAEA safety requirements a package has to withstand consecutively severe mechanical tests followed by a thermal test. The mechanical tests have to produce maximum damage concerning the thermal test. Following this, the impact limiters may have serious pre-damage when the thermal tests begins. The IAEA safety requirements state that during and following the fire test, the specimen shall not be artificially cooled and any combustion of materials of the package shall be permitted to proceed naturally. Small scale fire tests with wood filled metal drums by BAM and works of the French Institute for Radiological Protection and Nuclear Safety (IRSN) showed that pre-damaged steel encapsulated wooden structures could start smoldering initiated by the thermal test. These processes supply additional energy to the cask which should be considered within the safety assessment of the package. As not much is known about smoldering processes in encapsulated wooden structures with a reduced oxygen supply the need for a test was identified. To investigate the influence of a smoldering impact limiter concerning the amount of energy supplied to the cask in dependence of the time BAM conducted a large scale impact limiter thermal test. For that, a pre-damaged impact limiter with a diameter of 2,3 m was mounted on a water tank simulating a cask. A complex system of a regulated pump, a heater, a cooler, a slide valve, a flow meter and numerous thermocouples were installed and connected to a control unit to ensure all needed operating conditions. After a pre-heating compared to typical SNF decay-heat, the 30 min lasting fire phase of the thermal test was started. After that, the expected and initiated smoldering began. The results of the large scale test are presented in this poster. Systematic small scale tests will follow to identify the influence of different parameters, e.g. moisture content and scale effects. The tests took place at BAM Test Site for Technical Safety (TTS) with its various possibilities for mechanical and thermal tests. The results of these tests will have direct influence in the safety assessment of transport cask for the transport of radioactive material T2 - 2018 WM Symposia CY - Phoenix, AZ, USA DA - 18.03.2018 KW - Type-B Package KW - Thermal Test PY - 2018 SP - Paper 18257, 1 EP - 11 AN - OPUS4-45311 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank T1 - Recent developments in standards and IAEA guidance material for package load attachment points N2 - For transport package design and operation according to IAEA regulations, the package shall be securely stowed and its retention system shall be capable to withstand load conditions of routine transport. The supporting IAEA Advisory Material SSG-26 provides information how to do that. Up to now package designers in different countries use other load factors for the design of attachment points than those specified in the IAEA guidance material. In particular the acceleration values vary between different countries and lead to difficulties during the validation of foreign approval certificates. Therefore the IAEA started a discussion process to review the existing guidance text. An international working group was constituted in 2013. Representatives came from different stakeholders, e.g. transport operators, competent authorities and modal organizations. The discussions concluded especially on the transport conditions which has to be considered for stowage design, including on the one hand the relevance of the load factors used for strength and fatigue analysis and on the other hand the criteria which have to be considered for the attachment points. Another standard with relevance to the load attachment of packages is ISO 10276. This standard deals with trunnion design, manufacturing and operational aspects. The regular standard revision phase started in 2017. An expert group discussed new state-of-the-art technology and proposed revised text for the ISO standard for international discussion. The paper describes relevant tie-down aspects, gives background argumentation, and tries to support harmonized application of the revised IAEA guidance material and future ISO 10276 standard. T2 - 11th International Conference on the Transport, Storage and Disposal of Radioactive Materials CY - London, UK DA - 15.05.2018 KW - Acceleration KW - Package design KW - ISO KW - Ladungssicherung PY - 2018 AN - OPUS4-45293 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Moutarde, M. A1 - Apel, Andreas A1 - Ballheimer, Viktor A1 - Sterthaus, Jens T1 - Recent developments in standards and IAEA guidance material for package load attachment points N2 - For transport package design and operation according to IAEA regulations, the package shall be securely stowed and its retention system shall be capable to withstand load conditions of routine transport. The supporting IAEA Advisory Material SSG-26 provides information how to do that. Up to now package designers in different countries use other load factors for the design of attachment points than those specified in the IAEA guidance material. In particular the acceleration values vary between different countries and lead to difficulties during the validation of foreign approval certificates. Therefore the IAEA started a discussion process to review the existing guidance text. An international working group was constituted in 2013. Representatives came from different stakeholders, e.g. transport operators, competent authorities and modal organizations. The discussions concluded especially on the transport conditions which has to be considered for stowage design, including on the one hand the relevance of the load factors used for strength and fatigue analysis and on the other hand the criteria which have to be considered for the attachment points. Another standard with relevance to the load attachment of packages is ISO 10276. This standard deals with trunnion design, manufacturing and operational aspects. The regular standard revision phase started in 2017. An expert group discussed new state-of-the-art technology and proposed revised text for the ISO standard for international discussion. The paper describes relevant tie-down aspects, gives background argumentation, and tries to support harmonized application of the revised IAEA guidance material and future ISO 10276 standard. T2 - 11th International Conference on the Transport, Storage and Disposal of Radioactive Materials CY - London, UK DA - 15.05.2018 KW - Verzögerungswerte KW - Lastanschlag KW - Trunnion design KW - ISO KW - Retention PY - 2018 SP - 18511, 1 EP - 8 AN - OPUS4-45294 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Debruyne, M. A1 - Eckert, B. A1 - Wille, Frank A1 - Gauthier, F. A1 - Le Bars, I. A1 - Cordier, N. A1 - Jouve, A.-C. T1 - Assessment of safety demonstrations relative to packages containing UF6 N2 - Specific attention should be paid on safety demonstrations transmitted by applicants in the case of approval request for the package designs containing enriched UF6. Concerning the shipment of enriched UF6, the package designs consist in general of a filled 30B cylinder surrounded by an overpack. The description of the content, considering the UF6 origin, i.e. natural or reprocessed, shall be clearly justified especially when the UF6 isotopic composition exceeds the limits specified in ASTM standards. Concerning the containment of the UF6, the applicant shall demonstrate in all conditions of Transport the leak-tightness of the valve and plug of the cylinders filled with enriched UF6. In this regard, when justifications are based on numerical calculations, the absence of contact between These components of the cylinder and the internal surfaces of the overpack after the regulatory drop tests shall be shown. In particular, absence of contact between the valve and any other component of the packaging shall be confirmed to respect the current IAEA regulations [3]. If complementary calculations show a contact between the plug and the internal surfaces of the overpack, additional tests are required to confirm that the strength resulting from this contact will not affect the plug leak-tightness. It can be noticed that the future revision of the IAEA regulations will include additional provision in case of contact of the plug with any other component of the packaging. In addition, the applicant shall demonstrate that the melting temperature of the valve, including the tinned joint, will not be exceeded during the regulatory fire test. Furthermore, the representativeness of the ballast used to simulate the behaviour of the UF6 loaded within the cylinder shall be justified if drop tests are performed. Finally, specific provisions relative to the use of plugs and the maintenance of cylinders should be included in the safety analysis reports. T2 - 11th International Conference on the Transport, Storage and Disposal of Radioactive Materials CY - London, UK DA - 15.05.2018 KW - Uranhexaflourid KW - Package safety KW - Valve KW - Drop testing KW - Radioactive material PY - 2018 SP - 18523, 1 EP - 8 AN - OPUS4-45295 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CHAP A1 - Ballheimer, Viktor A1 - Quercetti, Thomas A1 - Wille, Frank ED - Saegusa, Toshiari ED - Sert, Gilles ED - Völzke, Holger ED - Wille, Frank T1 - Internal cask content collision during drop tests N2 - The interaction between the package lid system and internal Content during mechanical drop testing is a decisive matter in evaluating Impact loads and the safety of the package. In the case of movable contents ist impact onto the inner side of the package lid can cause additional load peaks on the lid and the lid bolts. Some aspects of this issue were discussed on the basis of experimental results from instrumented drop tests with transport casks and on the basis of analytical approaches. KW - Transport casks KW - Drop tests KW - Internal collision PY - 2018 SN - 978-981-3234-03-1 SP - Chapter 7, 103 EP - 120 PB - World Scientific Publishing CY - Singapore ET - 1 AN - OPUS4-47539 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank T1 - KI-unterstützte Begutachtung der Behältersicherheit N2 - Die BAM führt sicherheitswissenschaftliche Begutachtungen von Gefahrgutbehältern durch, die mechanische, thermische, abschirmende und transportbezogene Analysen sowie Materialbewertungen und experimentelle Prüfungen umfassen. Diese Begutachtungen basieren auf umfassenden Sicherheitsberichten und Betriebsdokumentationen, die zahlreiche verknüpfte Dokumente und Daten enthalten. Änderungen an Komponenten oder regulatorischen Vorgaben können große Auswirkungen auf den Prüfumfang haben. Das Projekt sieht vor, die Datenanalyse und -bereitstellung mittels KI-Ansätzen zu verbessern. Es sollen Methoden zur automatischen Analyse und Verknüpfung komplexer Dokumentationen entwickelt werden. Ziel ist es, die Effizienz und Sicherheit der Datenanalyse und späteren Sicherheitsbewertung zu steigern, menschliche Fehler zu minimieren und die Qualität der Sicherheitsbewertungen zu verbessern. Die Qualität der Datenbereitstellung aus Zeichnungen, Tabellen, Texten und Berechnungen ist entscheidend für die Verarbeitung digitaler Formate der Behälterdokumentation. Ein neuro-symbolischer KI-Ansatz kombiniert neuronale Netze und symbolische KI, um die komplexen Inhalte zu analysieren und zu verknüpfen, was für die spätere Sicherheitsbewertung der Gefahrgutbehälter entscheidend ist. In vortrainierten Large Language Models (LLMs) fehlen für diesen Anwendungsfall spezifische fachliche Daten zur Behältersicherheit was zu fehlerhaften Ergebnissen führen kann. Für die Datenbereitstellung und Analyse im Zuge einer Sicherheitsbewertung gilt es dieses auszuschließen. Hierzu soll die RAG-Architektur (Retrieval-Augmented Generation) im Zusammenspiel mit LLMs angewendet werden. Dieser neue Ansatz der natürlichen Sprachverarbeitung und generativen KI soll die Stärken vortrainierter Sprachmodelle mit Fachwissen und Informationen aus Datenbanken und Dokumentensammlungen kombinieren. Die generierten Ergebnisse sollen dabei zusammen mit den verwendeten Quellen bereitgestellt werden, um eine fundierte und nachvollziehbare Basis für die Sicherheitsbewertung bilden. T2 - Informationsaustausch zur verkehrsrechtlichen Aufsicht bei der Beförderung radioaktiver Stoffe CY - Bonn, Germany DA - 04.02.2025 KW - KI KW - RAG KW - LLM PY - 2025 AN - OPUS4-62538 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -