TY - CONF A1 - Gleim, Tobias A1 - Neumann, Martin A1 - Linnemann, Konrad A1 - Komann, Steffen A1 - Wille, Frank T1 - Fracture Mechanical Analyses of a Welding Seam of a Thick-Walled Transport Package N2 - Transport packages shall satisfy various safety criteria regarding mechanical, thermal and radiation phenomena. Typical requirements focusing mechanical aspects are usually drop tests in accordance with IAEA regulations. The drop tests are usually carried out experimentally and, as an additional measure, finite element analyses (FEA) are performed. A specific part of the investigations presented is the evaluation of the welding seam connecting cask shell and cask bottom. Experimental results and FEA are presented and compared. The evaluation of the welding seam performed includes a variety of aspects. In addition to the experimental and analytical stresses determined, different standards are used to investigate a possible crack initiation. Several destructive and non-destructive tests are performed for quality assurance in the manufacturing process as well as for different input parameters. The necessary monitoring and non-destructive measurement methods to define the boundary conditions of the standards are introduced. Taking into account all required parameters, the welding seam is examined and evaluated using the failure assessment diagrams (FAD) of the respective standards. It can be shown under the given boundary conditions that considering the experimental data, the welding seam is in the context of crack initiation below the enveloping curve in the acceptable region. More critical drop tests to be conducted are proposed and need to be investigated in future work. T2 - Pressure Vessels & Piping Conference® 2022 CY - Las Vegas, NV, USA DA - 17.07.2022 KW - Transport package KW - Drop test KW - Fracture initiation PY - 2022 SP - 1 EP - 9 AN - OPUS4-55375 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin T1 - Nuclear disposal - transport and storage of radioactive waste N2 - This presentation deals with transport, interim storage, and final disposal of radioactive material in Germany in the context of the University of Magdeburg course "Introduction to nuclear plant design and safety". The IAEA regulatory framework, relevant tests for ensuring safety, and transport packages are a major part of the transport aspect. Different interim storage designs are discussed as well as the current state of final repositories in Germany analyzed. Finally, a European perspective is given. T2 - Vorlesungsreihe "Introduction to nuclear plant design and safety" CY - Magdeburg, Germany DA - 13.06.2025 KW - Nuclear KW - Transport KW - Radioactive KW - Material PY - 2025 AN - OPUS4-63433 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schubert, Sven A1 - Reichardt, Adrian A1 - Wille, Frank A1 - Komann, Steffen A1 - Neumann, Martin T1 - Introduction of an ageing management approach for packages for the transport of radioactive materials N2 - With integration of the new para 613A into SSR-6 [1] the consideration of ageing mechanisms is now obligatory for the design of packages and their approval. In addition, para 809(f) of SSR-6 [1] requires consideration of the effects of storage on ageing mechanisms, safety analyses and operation and maintenance instructions. German competent authorities Bundesanstalt für Materialforschung und -prüfung (BAM) and Bundesamt für die Sicherheit der nuklearen Entsorgung (BASE) are considering the aspect of ageing in approval procedures. Ageing assessment is mainly focused on dual purpose casks (DPC) package designs which are long-term stored in interim storage facilities. For these package designs, the evaluation of ageing management is now mandatory for the maintenance of the package design approvals with a validity period of 5 years and beyond. The ageing management includes amongst others a gap analysis, the assessment of ageing effects and operational experiences during operation and interim storage. BAM works on the compilation of a guideline for implementation of paras 613A, 809(f) and 809(k) for packages requiring competent authority approval at the application procedure in Germany. The paper describes essential items of ageing mechanisms and will give a foresight to the ageing management evaluation by BAM. T2 - INMM & ESARDA Joint Annual Meeting CY - Online meeting DA - 30.08.2021 KW - Dual purpose casks KW - Ageing KW - SSR-6 KW - Interim storage KW - Ageing mechanisms KW - Transport of radaioactive materials PY - 2021 UR - https://www.abstractsonline.com/pp8/#!/10383/presentation/964 SP - 1 EP - 6 PB - Institute of Nuclear Materials Management (INMM) CY - Mount Laurel, NJ AN - OPUS4-53180 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Quercetti, Thomas T1 - Full-scale drop testing with a heavy-weight package for radioactive waste N2 - 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. T2 - 20th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 22) CY - Juan-Les-Pins, France DA - 11.06.2023 KW - Full-scale KW - Drop testing KW - Package KW - Radioactive waste PY - 2023 AN - OPUS4-57731 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - John, Sebastian T1 - Delfin - Statusbericht zum 4.HJM N2 - Präsentation über den Fortschritt der BAM zum Vorhaben Delfin, welches sich mit der Entwicklung und Schädigungsneigung von Composite-Wasserstoffbehältern für den Anwendungsfall KFZ beschäftigt T2 - 4. Halbjahresmeeting zum Vorhaben Delfin CY - Online meeting DA - 21.10.2020 KW - Wasserstoff KW - Impact KW - Druckbehälter PY - 2020 AN - OPUS4-51495 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Quercetti, Thomas T1 - A fire test stand for thermal testing of extra-large packages N2 - Packages for the transport of high-level radioactive materials are designed to withstand severe accidents. These packages must adhere to the specification-based criteria of the International Transport Regulations of the International Atomic Energy Agency (IAEA). To ensure compliance with these requirements, specific mechanical and thermal tests need to be addressed with respect to the package type. Typically, the Regulations prescribe mechanical tests followed by a thermal test as part of a cumulative test scenario. The thermal test is specified by the exposure of a test specimen for a period of 30 minutes to a thermal environment that provides a heat flux equivalent to that of a hydrocarbon fuel-air fire with an average fire temperature of at least 800 °C fully flame engulfing the test specimen. The Federal Institute for Materials Research and Testing (BAM) operates various test facilities for this purpose at their test site (TTS) near Berlin in Germany. Thermal tests for large packages are carried out in an established fire test stand that can be adapted by the test-setup to the geometric boundary conditions of a test specimen. This fire test stand is built for test specimens with masses up to 200,000 kg and geometric dimensions relating to large transport packages including their impact limiters. The test specimen is usually placed on a water-cooled support frame in the middle of the test-stand. The fire is realized by burning propane gas which is released in liquid state from an array of gas nozzles arranged in the form of a burner ring surrounding the test specimen. For particularly extra-large test specimens, two burner rings are used on top of each other and at different heights in order to firstly achieve full fire engulfment with a significantly larger volume of fire and secondly to achieve the required heat output. In advance of a regular thermal test BAM usually performs so-called fire reference tests to determine the test conditions for compliance with the IAEA requirements. These tests are performed using a generic package which corresponds to the external geometric dimensions of the test specimen used later in the approval test. Then, this reference package is exposed to a fire under defined test parameters whereas the corresponding heat input determined from the temperature changes measured is regarded as main criterion for proofing compliance with the IAEA criteria. The paper shows the experimental proof of the suitability of BAM’s fire test stand for thermal testing of extra-large packages. The heat input and fire temperatures fully meet the IAEA criteria but can also be set significantly higher for e.g. extra-regulatory testing. T2 - ASME PVP 2025 CY - Montreal, Quebec, Canada DA - 20.07.2025 KW - Package KW - Thermal testing KW - Test stand KW - Fire PY - 2025 AN - OPUS4-63893 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schubert, Sven A1 - Neumann, Martin A1 - Reichardt, Adrian A1 - Komann, Steffen A1 - Wille, Frank T1 - Experiences with the implementation of ageing management for packages for transport of radioactive materials in Germany N2 - The consideration of ageing mechanisms is now obligatory for the design of transport packages with integration of the para 613A into IAEA SSR-6 (Rev. 1). In addition, para 809(f) of SSR-6 (Rev. 1) requires for packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance. Para 503(e) requires that these packages have been maintained during storage in a manner that all requirements specified in SSR-6 (Rev.1) and in the applicable certificates of approval have been fulfilled. The evaluation of ageing mechanisms and their effects including monitoring are part of BAM’s authority assessment tasks related to the mechanical and thermal package design and quality assurance aspects. BAM has compiled the guideline BAM-GGR 023 for the implementation of ageing assessment and related measures into the approval procedure. The implementation of ageing management measures is obligatory in case of extension/renewal of package design approval certificates. BAM has evaluated package designs which are used only for transport as well as package designs for long term interim storage. The assessment of ageing mechanisms associated with the identification of ageing effects on components is the main part of the ageing management plan (AMP). Different approaches regarding AMP structure are introduced. Experiences and approaches about the evaluation of components for the expected package operating time are shown. We are focusing the evaluations of proofs for not accessible and not replaceable components. Operational experiences for these package designs are available and should be considered in the ageing evaluation. Corresponding measures for package monitoring are to be derived based on these results. The measures for monitoring shall be fixed in the Ageing Surveillance Program (ASP) to maintain a specification conform package for the transport on public routes. We show exemplary how results from ageing evaluation during the approval procedure are transferred into the ASP. T2 - PATRAM 2025 CY - San Antonio, Texas , US DA - 27.07.2025 KW - RAM KW - Ageing management KW - Radioactive material KW - Transport PY - 2025 SP - 1 EP - 8 PB - INMM CY - Washington D.C. AN - OPUS4-63987 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin A1 - Feldkamp, Martin A1 - Linnemann, Konrad A1 - Wille, Frank T1 - Conclusions from the first return campaign of vitrified High-Level Waste on sea going vessels from the competent authority N2 - Germany has to take back vitrified waste from the reprocessing plants in France and Great Britain. The waste resulted from decades of transporting spent fuel for reprocessing to La Hague and Sellafield. The return campaign from France was concluded in 2024 with the transport of five CASTOR® HAW28M casks to the interim storage facility in Philippsburg in southern Germany. The return of waste from Sellafield comprises three campaigns and a total of 20 CASTOR® HAW28M casks. The first campaign was performed in 2020, consisting of six CASTOR® HAW28M casks, while the second campaign was performed in March 2025, consisting of seven CASTOR® HAW28M casks. The casks were transported by rail from Sellafield to the port in Barrow-in-Furness, where they were loaded into a dedicated seagoing vessel, certified as INF Class 3 according to the INF Code. This was the first time that vitrified high level waste with considerable heat load was transported under a German design approval certificate. The third campaign is expected to be performed during 2026. BAM as part of the German competent authority system was among others involved in the assessment of the sea transport. BAM required for the first transport, among others, an assessment of temperature distribution during transport, logging of temperatures of cargo bays and graphical imaging of temperatures of the bay with the cask to ensure compliance with temperature specifications, e.g. maximal neutron absorber and gasket temperatures. Special interest was taken in the identification of possible events exceeding the specified temperatures considering the different philosophies of the IMDG code and its supplement the INF code regarding temperature control of hatches. Results show compliance with assumed conditions. T2 - PATRAM 2025 CY - San Antonio, Texas, USA DA - 27.07.2025 KW - RAM KW - Transport KW - Radioactive material KW - Sea PY - 2025 SP - 1 EP - 8 PB - INMM CY - Washington D.C. AN - OPUS4-63984 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin T1 - Experiences with the implementation of ageing management for packages for transport of radioactive materials in Germany N2 - The consideration of ageing mechanisms is now obligatory for the design of transport packages with integration of the para 613A into IAEA SSR-6 (Rev. 1). In addition, para 809(f) of SSR-6 (Rev. 1) requires for packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance. Para 503(e) requires that these packages have been maintained during storage in a manner that all requirements specified in SSR-6 (Rev.1) and in the applicable certificates of approval have been fulfilled. The evaluation of ageing mechanisms and their effects including monitoring are part of BAM’s authority assessment tasks related to the mechanical and thermal package design and quality assurance aspects. BAM has compiled the guideline BAM-GGR 023 for the implementation of ageing assessment and related measures into the approval procedure. The implementation of ageing management measures is obligatory in case of extension/renewal of package design approval certificates. BAM has evaluated package designs which are used only for transport as well as package designs for long term interim storage. The assessment of ageing mechanisms associated with the identification of ageing effects on components is the main part of the ageing management plan (AMP). Different approaches regarding AMP structure are introduced. Experiences and approaches about the evaluation of components for the expected package operating time are shown. We are focusing the evaluations of proofs for not accessible and not replaceable components. Operational experiences for these package designs are available and should be considered in the ageing evaluation. Corresponding measures for package monitoring are to be derived based on these results. The measures for monitoring shall be fixed in the Ageing Surveillance Program (ASP) to maintain a specification conform package for the transport on public routes. We show exemplary how results from ageing evaluation during the approval procedure are transferred into the ASP. T2 - PATRAM 2025 CY - San Antonio, TX USA DA - 27.07.2025 KW - RAM KW - Ageing management KW - Transport KW - Radioactive material PY - 2025 AN - OPUS4-63985 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin T1 - Conclusions from the first return campaign of vitrified High-Level Waste on sea going vessels from the competent authority N2 - Germany has to take back vitrified waste from the reprocessing plants in France and Great Britain. The waste resulted from decades of transporting spent fuel for reprocessing to La Hague and Sellafield. The return campaign from France was concluded in 2024 with the transport of five CASTOR® HAW28M casks to the interim storage facility in Philippsburg in southern Germany. The return of waste from Sellafield comprises three campaigns and a total of 20 CASTOR® HAW28M casks. The first campaign was performed in 2020, consisting of six CASTOR® HAW28M casks, while the second campaign was performed in March 2025, consisting of seven CASTOR® HAW28M casks. The casks were transported by rail from Sellafield to the port in Barrow-in-Furness, where they were loaded into a dedicated seagoing vessel, certified as INF Class 3 according to the INF Code. This was the first time that vitrified high level waste with considerable heat load was transported under a German design approval certificate. The third campaign is expected to be performed during 2026. BAM as part of the German competent authority system was among others involved in the assessment of the sea transport. BAM required for the first transport, among others, an assessment of temperature distribution during transport, logging of temperatures of cargo bays and graphical imaging of temperatures of the bay with the cask to ensure compliance with temperature specifications, e.g. maximal neutron absorber and gasket temperatures. Special interest was taken in the identification of possible events exceeding the specified temperatures considering the different philosophies of the IMDG code and its supplement the INF code regarding temperature control of hatches. Results show compliance with assumed conditions. T2 - PATRAM 2025 CY - San Antonio, TX, USA DA - 27.07.2025 KW - RAM KW - Transport KW - Radioactive material KW - Sea PY - 2025 AN - OPUS4-63983 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Müller, Lars A1 - Scheidemann, Robert A1 - Neumeyer, Tino A1 - Neumann, Martin A1 - Komann, Steffen A1 - Wille, Frank T1 - Thightness Assessment of welded Lids for Encapsulations of damaged Spent Nuclear Fuel in the Design Approval Process of Dual-Purpose Casks (DPC) N2 - The disposal of spent nuclear fuel in Germany is ensured using dual-purpose casks (DPC) for transport and interim storage. The leak tightness of the DPC and resulting containment is one of the most important aspects. Additional encapsulations are required for damaged spent nuclear fuel (DSNF) to guarantee safe handling and a separate tight closure. Due to the general design of DPCs for standard fuel assemblies should special requirements be considered for the design of the encapsulations for DSNF to ensure the loading in existing package designs. The absence of a replaceable sealing in the tightness barrier is the main difference for the encapsulations for damaged spent nuclear fuel. Instead, they are welded shut with a lid. The leak tightness of the encapsulation shall be proven in the design approval process for all transport conditions. This is especially valid for accident conditions of transport, where high internal impact forces may occur. BAM as German competent authority is responsible for the safety assessment of mechanical and thermal design, retention of radioactive material and quality assurance aspects of manufacturing and operation. BAM carried out a comprehensive safety assessment concerning the mechanical package design. As there are no representative standards for verifying the leak tightness of a welded lid, two approaches were being pursued. Established German standards may be used for verifying the leak tightness of a weld - but limited to low stresses. Therefore, physical tests were required for higher impact loads. Representative drop tests and highly sensitive leakage tests were performed. The paper presents an overview of the containment assessment by BAM and points out the main findings for the design of welds regarding leak tightness. Both verification procedures are described, on one hand with German standards for lower loads and on the other hand with physical tests for higher impact loads. The leak tightness of the encapsulation weld could be approved based on leakage tests and a corresponding evaluation for all transport conditions. T2 - PATRAM 2025 CY - San Antonio, Texas, USA DA - 27.07.2025 KW - Transport packages KW - Tightness assessment KW - Welded lids KW - Encapsulations PY - 2025 VL - 2025 SP - 1 EP - 11 PB - Institute of Nuclear Materials Management (INMM) CY - Indianapolis AN - OPUS4-64023 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Guitton, Matthieu A1 - Chrupek, Thierry A1 - Leblanc, Vincent A1 - Van derTuijn, Jeroen A1 - Kaufhold, Dominik A1 - Kesting, Frederik A1 - Müller, Lars T1 - Multilateral approval of a SCO-III (three spent steam generator lower parts from EDF Fessenheim nuclear power plant) multimodal shipment N2 - A Surface Contaminated Object (SCO) is defined as a solid object which is not itself radioactive, but which has radioactive material distributed on its surfaces. The 2018 Edition of the IAEA Regulations for the Safe Transport of Radioactive Material (SSR-6 Rev. 1) introduced the group SCO-III to transport unpackaged large objects. The two pressurized water reactors of the Fessenheim Nuclear Power Plant, owned by EDF, were shut down in 2020. Previously, for maintenance operations in the year 2002 and 2010, the three steam generators – over 20 metres long, 300 tons – of each reactor were taken out from the reactors, divided in two and stored on site: - EDF shipped the six upper parts, as SCO-I, to Cyclife, in Studsvik (Sweden), in 2021, to be recycled; - EDF plans two transports of the lower parts (three parts for each transport), as SCO-III (considering the higher activity due to the NPP primary coolant) to the same facility. Modes of transport are, from consignor to consignee, road, inland waterways and maritime. The countries crossed by inland waterways, from Neuf-Brisach to Dunkerque (France), are France, Germany, Belgium and the Netherlands. According to the para. 825 of SSR-6 Rev. 1, “multilateral approval shall be required for the shipment of SCO-III”. EDF has submitted to all Competent Authorities an application (para. 827A of SSR-6 Rev. 1), including a transport plan and demonstrations to withstand normal conditions of transport. Despite SSR-6 Rev. 1, national regulations have their own specificities and each Competent Authority has its own assessment procedures. Nevertheless, involved Authorities agreed for a joint review, which included: - the understanding of national regulatory requirements, - the expected level of detail and quality of the safety case, - the feedback from previous shipments of similar type, - the contents, including the conditions, of the approvals to be issued. This joint review demonstrated good coordination between authorities, enabling the application to be processed rapidly, and the various authorities to benefit from each other's expertise and feedback. This was of particular importance, as it was the first application for the transport of an SCO-III assessed by the Competent Authorities involved. Finally, the authorities were able to issue approvals, whose format is certainly in line with their national provisions, but whose content and level of requirements in terms of transport safety are consistent. T2 - PATRAM 2025 CY - San Antonio, Texas, USA DA - 27.07.2025 KW - Shipment KW - Multilateral approval KW - Steam generator KW - SCO-III PY - 2025 VL - 2025 SP - 1 EP - 8 PB - Institute of Nuclear Materials Management (INMM) CY - Indianapolis AN - OPUS4-64026 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Müller, Lars T1 - Thightness Assessment of welded Lids for Encapsulations of damaged Spent Nuclear Fuel in the Design Approval Process of Dual-Purpose Casks (DPC) N2 - The disposal of spent nuclear fuel in Germany is ensured using dual-purpose casks (DPC) for transport and interim storage. The leak tightness of the DPC and resulting containment is one of the most important aspects. Additional encapsulations are required for damaged spent nuclear fuel (DSNF) to guarantee safe handling and a separate tight closure. Due to the general design of DPCs for standard fuel assemblies should special requirements be considered for the design of the encapsulations for DSNF to ensure the loading in existing package designs. The absence of a replaceable sealing in the tightness barrier is the main difference for the encapsulations for damaged spent nuclear fuel. Instead, they are welded shut with a lid. The leak tightness of the encapsulation shall be proven in the design approval process for all transport conditions. This is especially valid for accident conditions of transport, where high internal impact forces may occur. BAM as German competent authority is responsible for the safety assessment of mechanical and thermal design, retention of radioactive material and quality assurance aspects of manufacturing and operation. BAM carried out a comprehensive safety assessment concerning the mechanical package design. As there are no representative standards for verifying the leak tightness of a welded lid, two approaches were being pursued. Established German standards may be used for verifying the leak tightness of a weld - but limited to low stresses. Therefore, physical tests were required for higher impact loads. Representative drop tests and highly sensitive leakage tests were performed. The paper presents an overview of the containment assessment by BAM and points out the main findings for the design of welds regarding leak tightness. Both verification procedures are described, on one hand with German standards for lower loads and on the other hand with physical tests for higher impact loads. The leak tightness of the encapsulation weld could be approved based on leakage tests and a corresponding evaluation for all transport conditions. T2 - PATRAM 2025 CY - San Antonio, TX, USA DA - 27.07.2025 KW - Tightness assessment KW - Welded lids KW - Transport packages KW - Encapsulations PY - 2025 AN - OPUS4-64017 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias ED - Monavari, Mehran ED - Bertovic, Marija ED - Wille, Frank T1 - AI-Based Documentation Analysis for Safety Assessment of Packages for Radioactive Material N2 - The transportation of radioactive material requires, dependent on type and quantity of the radioactive material, a regulatory approval based on the package type. Safety assessments shall be conducted in compliance with the International Atomic Energy Agency (IAEA) regulations and documented in a comprehensive package design safety report to obtain approval from authority. This comprehensive safety report evaluates a broad range of requirements from the regulations, including mechanical, thermal, shielding, criticality and transport requirements and controls, and testing assessments. Additionally, it encompasses supporting documents such as specifications, inspections, certifications, drawings, and guidelines in a variety of complex documents. Safety and manufacturing reports contain multiple interconnected sub-reports covering various topics. Changes, such as component modifications, material property updates, or regulatory revisions, often impact multiple sections of the safety analysis reports, making even minor adjustments complex and time-consuming. Each transport package has unique requirements to be fulfilled, making every safety report distinct, despite following the same regulatory framework. Most documentation exists in standard digital formats but is often not machine interpretable, preventing automated analysis of the critical dependencies between them. This paper argues that moving beyond simple digitization towards structured knowledge representation is essential for addressing these challenges. We propose a multi-stage approach, beginning with foundational AI technologies such as Large Language Models (LLMs) and Retrieval-Augmented Generation (RAG), and progressing toward the construction of Knowledge Graphs (KGs). KGs convert unstructured and semi-structured information into a connected, queryable network, enabling precise tracing and visualization of complex interdependencies within the documentation landscape. By linking interpretable content directly to datasheets, tables, simulations, experimental results, standards, and regulations, such a system would automatically identify changes and interdependencies. Related conditions could be validated using AI-based tools, reducing the need for manual intervention, improving both efficiency and safety. Human error plays a significant role in drafting, reviewing, and revising safety reports, often requiring iterative review cycles and multiple reviewers before approval. A digital quality infrastructure could reduce iterations and further improve efficiency. Integrating AI into this process could optimize safety assessments and enhance their robustness by leveraging interpretability to enhance safety. This preliminary study explores the readiness and requirements for using intelligent documentation analysis system in the context of regulatory compliance for package safety for the transport of radioactive material. By analysing current documentation workflows, we identify how LLM-based tools can interpret complex safety reports and highlight critical interdependencies and then demonstrate why a KG-based architecture is necessary to robustly manage and query critical interdependencies. This lays the groundwork for future agentic AI systems capable of proactively supporting the safety assessment lifecycle, while stressing the importance of robust data governance and AI reliability in this highly regulated context. T2 - PATRAM 2025 CY - San Antonio, TX, USA DA - 27.07.2025 KW - AI, RAG, LLM, Knowledge Graph PY - 2025 SP - 1 EP - 10 PB - Institute of Nuclear Materials Management (INMM) AN - OPUS4-63863 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Naster, Maximilian A1 - Gleim, Tobias A1 - Wille, Frank T1 - Experimental and numerical analyses of hydrogen flames for the thermal testing of transport packages for radioactive material N2 - In this paper we present an update of the hydrogen based test rig for an ongoing feasibility study of using hydrogen as an energy source for the thermal testing of transport packages containing radioactive materials [ The test rig is capable of combusting hydrogen for a wide range of different burner geometries, mass flows , hydrogen blends and single jet flame operation s as well as a full array of burners for thermal testing can be set up. As this type of fire test according to the IAEA boundary conditions does not yet exist, a large number of preliminary investigations, safety assessments and simulations must be carried out in order to develop a viable concept for hydrogen fires. In a first step of the feasibility study, the temperature , structure, and radiative behavior of hydrogen jet flames must be surveyed. The simulation with a single hydrogen flame was investigated in a previous work. In the next step the results are used to study the interaction and structural behavior of multiple jet flames in proximity with varying nozzle distances. With the test rig completed, it will be possible in future works to design burner frames suitable for fire reference tests to make comparisons with pool and propane fires used in assessment procedure today. Thus, preliminary comparative numerical simulations are conducted to model the behavior of overlapping hydrogen jet flames using the software package Ansys®. This paper gives an overview on the current state and design of the test rig. Furthermore, the results of the simulations show that nozzle geometry, mas s flow and nozzle distance provide significant design margin for designing a test fire capable of fully engulfing a specimen. T2 - PVP2025, Pressure Vessels & Piping Conference CY - Montreal, Quebec, Canada DA - 20.07.2025 KW - Computational Fluid Dynamics (CFD) KW - Fire testing KW - Hydrogen KW - IAEA PY - 2025 SP - 1 EP - 10 AN - OPUS4-63864 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Affagard, Jean-Sebastien A1 - Gleim, Tobias A1 - Louis, Baptiste A1 - Quercetti, Thomas A1 - Ledroit, Frédéric A1 - Létang, Eric T1 - Towards a simplifiedmodel of the delayed impact: numerical and experimental outlook N2 - The IAEA Regulations for the Safe Transport of Radioactive Material No. SSR-6 require drop tests for demonstrating the ability of a package to withstand accident conditions of transport. In case a gap exists between the contents and the lid, it can result in a delayed impact of the content onto the lid system during a vertical drop test. The kinematic energy transmitted to the lid in such cases can be significant due to the stiffness of the impact, leading to high stresses in the bolts compared to a configuration without a gap. In the past, IRSN and BAM have individually investigated the modelling of the delayed impact phenomenon. BAM has examined the effects of the delayed impact phenomenon for spent fuel packages in a comparative analysis between experiments and simulations, which was presented at SMIRT 2013. Meanwhile, IRSN’s has developed a simple numerical tool that can quickly evaluate the influence of various parameters before considering a more complex finite element numerical calculation. This tool was presented at PATRAM 2022. In 2023, BAM and IRSN (now ASNR - French nuclear safety and radiation protection authority) decided to jointly pursue their study on the delayed impact phenomenon, incorporating damping effects, by developing new insights and techniques. To this end, a controlled and simplified set of experiments needs to be developed to calibrate and validate the simplified model. These experiments will record velocity, position of parts, strain and accelerations. The parameters and the configurations necessary for the development of the mock-up, as well as the placement and quantity of sensors, are determined through extensive pre-calculations using both complex finite element models and the simplified approach. A key challenge involves precisely controlling the drop of the mock-up to accurately replicate the theoretical contact and damping conditions. Advanced sensor technologies will be employed to acquire reliable and sufficient data. The tests are designed and conducted at BAM's TTS drop test facility in collaboration with ASNR. T2 - PATRAM 2025 CY - San Antonio, TX, USA DA - 27.07.2025 KW - Experiments KW - Impact KW - Drop Tower PY - 2025 SP - 1 EP - 11 CY - Institute of Nuclear Materials Management (INMM) AN - OPUS4-63870 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Quercetti, Thomas A1 - Feldkamp, Martin A1 - Gleim, Tobias A1 - Musolff, André A1 - Werner, Jan A1 - Wille, Frank T1 - Fire Test Stand for Thermal Testing of Large Packages for the Transport of Radioactive Materials N2 - Packages for the transport of high level radioactive materials are designed to withstand severe accidents. These packages must comply with the specific safety requirements SSR 6 [ of the International Atomic Energy Agency (IAEA). To guarantee compliance with these requirements, specific mechanical and thermal tests need to be addressed r egard ing the package type. Typically, the r egulations prescribe mechanical tests followed by a thermal test as part of a cumulative test scenario. The thermal test is specified by the exposure of a test specimen for a period of 30 minutes to a thermal environment that provides a heat flux equivalent to that of a hydrocarbon fuel air fire with an av erage fire temperature of at least 800 °C fully flame engulfing the test specimen. The Federal Institute for Materials Research and Testing (BAM) operates various test facilities for this purpose at their Test Site for Technical Safety (near Berlin in Germany). Thermal tests for large packages are conducted in an established fire test stand that may be adapted by the test setup to the geometric boundary conditions of a test specimen. This fire test stand is built for test specimens with masses up to 200,000 kg an d geometric dimensions relating to large transport packages including their impact limiters. The test specimen is usually placed on a water cooled support frame in the middle of the test stand. The fire is realized by burning propane gas which is released in liquid state from an array of gas nozzles arranged in the form of a burner ring surrounding the test specimen. For particularly extra large test specimens, two burner rings are used on top of each other and at different heights to firstly achieve full f ire engulfment with a significantly larger volume of fire and secondly to achieve the required heat output , cf. In advance of a regular thermal test BAM usually performs so called fire reference tests to determine the test conditions for compliance with the IAEA requirements. These tests are performed using a generic package which corresponds to the external geometr ic dimensions of the test specimen used later in the approval test. Then, this reference package is exposed to a fire under defined test parameters whereas the corresponding heat input determined from the temperature changes measured is regarded as main cr iterion for proofing compliance with the IAEA criteria. The paper shows the experimental proof of the suitability of BAM’s fire test stand for thermal testing of extra large packages. The heat input and fire temperatures fully meet the IAEA criteria and can also be set significantly higher for example for extra regulatory testing. T2 - PATRAM 2025 CY - San Antonio, TX, USA DA - 27.07.2025 KW - IAEA Regu-lations KW - Fire Test Stand KW - Accident Scenario KW - Fire Qualification PY - 2025 SP - 1 EP - 10 CY - Institute of Nuclear Materials Management (INMM) AN - OPUS4-63872 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Naster, Maximilian T1 - Experimental and numerical analyses of hydrogen flames for the thermal testing of transport packages for radioactive material N2 - In this paper we present an update of the hydrogen-based test rig for an ongoing feasibility study of using hydrogen as an energy source for the thermal testing of transport packages containing radioactive materials. The test rig is capable of combusting hydrogen for a wide range of different burner geometries, mass flows, hydrogen blends and single jet flame operations as well as a full array of burners for thermal testing can be set up. As this type of fire test according to the IAEA boundary conditions does not yet exist, a large number of preliminary investigations, safety assessments and simulations must be carried out in order to develop a viable concept for hydrogen fires. In a first step of the feasibility study, the temperature, structure, and radiative behavior of hydrogen jet flames must be surveyed. The simulation with a single hydrogen flame was investigated in a previous work. In the next step the results are used to study the interaction and structural behavior of multiple jet flames in proximity with varying nozzle distances. With the test rig completed, it will be possible in future works to design burner frames suitable for fire reference tests to make comparisons with pool and propane fires used in assessment procedure today. Thus, preliminary comparative numerical simulations are conducted to model the behavior of overlapping hydrogen jet flames using the software package Ansys®. This paper gives an overview on the current state and design of the test rig. Furthermore, the results of the simulations show that nozzle geometry, mass flow and nozzle distance provide significant design margin for designing a test fire capable of fully engulfing a specimen. T2 - PVP2025, Pressure Vessels & Piping Conference CY - Montreal, Quebec, Canada DA - 20.07.2025 KW - Computational Fluid Dynamics (CFD) KW - Hydrogen KW - IAEA fire test PY - 2025 AN - OPUS4-63865 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias A1 - Affagard, Jean-Sebastien T1 - Towards a simplifiedmodel of the delayed impact: numerical and experimental outlook N2 - The IAEA Regulations for the Safe Transport of Radioactive Material No. SSR-6 require drop tests for demonstrating the ability of a package to withstand accident conditions of transport. In case a gap exists between the contents and the lid, it can result in a delayed impact of the content onto the lid system during a vertical drop test. The kinematic energy transmitted to the lid in such cases can be significant due to the stiffness of the impact, leading to high stresses in the bolts compared to a configuration without a gap. In the past, IRSN and BAM have individually investigated the modelling of the delayed impact phenomenon. BAM has examined the effects of the delayed impact phenomenon for spent fuel packages in a comparative analysis between experiments and simulations, which was presented at SMIRT 2013. Meanwhile, IRSN’s has developed a simple numerical tool that can quickly evaluate the influence of various parameters before considering a more complex finite element numerical calculation. This tool was presented at PATRAM 2022. In 2023, BAM and IRSN (now ASNR – French nuclear safety and radiation protection authority) decided to jointly pursue their study on the delayed impact phenomenon, incorporating damping effects, by developing new insights and techniques. To this end, a controlled and simplified set of experiments needs to be developed to calibrate and validate the simplified model. These experiments will record velocity, position of parts, strain and accelerations. The parameters and configurations necessary for the development of the mock-up, as well as the placement and quantity of sensors, are determined through extensive pre-calculations using both complex finite element models and the simplified approach. A key challenge involves precisely controlling the drop of the mock-up to accurately replicate the theoretical contact and damping conditions. Advanced sensor technologies will be employed to acquire reliable and sufficient data. The tests are designed and conducted at BAM's TTS drop test facility in collaboration with ASNR. T2 - PATRAM 2025 CY - San Antonio, TX, USA DA - 27.07.2025 KW - Experiments KW - Impact KW - Drop Tower PY - 2025 AN - OPUS4-63869 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias T1 - AI-Driven Documentation Analysis Supporting Safety Assessment of Transport Packages N2 - The transportation of radioactive material requires, dependent on type and quantity of the radioactive material, a regulatory approval based on the package type. Safety assessments shall be conducted in compliance with the International Atomic Energy Agency (IAEA) regulations and documented in a comprehensive package design safety report to obtain approval from authority. This comprehensive safety report evaluates a broad range of requirements from the regulations, including mechanical, thermal, shielding, criticality and transport requirements and controls, and testing assessments. Additionally, it encompasses supporting documents such as specifications, inspections, certifications, drawings, and guidelines in a variety of complex documents. Safety and manufacturing reports contain multiple interconnected sub-reports covering various topics. Changes, such as component modifications, material property updates, or regulatory revisions, often impact multiple sections of the safety analysis reports, making even minor adjustments complex and time-consuming. Each transport package has unique requirements to be fulfilled, making every safety report distinct, despite following the same regulatory framework. Most documentation exists in standard digital formats but is often not machine interpretable, preventing automated analysis of the critical dependencies between them. This paper argues that moving beyond simple digitization towards structured knowledge representation is essential for addressing these challenges. We propose a multi-stage approach, beginning with foundational AI technologies such as Large Language Models (LLMs) and Retrieval-Augmented Generation (RAG), and progressing toward the construction of Knowledge Graphs (KGs). KGs convert unstructured and semi-structured information into a connected, queryable network, enabling precise tracing and visualization of complex interdependencies within the documentation landscape. By linking interpretable content directly to datasheets, tables, simulations, experimental results, standards, and regulations, such a system would automatically identify changes and interdependencies. Related conditions could be validated using AI-based tools, reducing the need for manual intervention, improving both efficiency and safety. Human error plays a significant role in drafting, reviewing, and revising safety reports, often requiring iterative review cycles and multiple reviewers before approval. A digital quality infrastructure could reduce iterations and further improve efficiency. Integrating AI into this process could optimize safety assessments and enhance their robustness by leveraging interpretability to enhance safety. This preliminary study explores the readiness and requirements for using intelligent documentation analysis system in the context of regulatory compliance for package safety for the transport of radioactive material. By analysing current documentation workflows, we identify how LLM-based tools can interpret complex safety reports and highlight critical interdependencies and then demonstrate why a KG-based architecture is necessary to robustly manage and query critical interdependencies. This lays the groundwork for future agentic AI systems capable of proactively supporting the safety assessment lifecycle, while stressing the importance of robust data governance and AI reliability in this highly regulated context. T2 - Sandia-BAM Technical Exchange CY - Albuquerque, NM, USA DA - 23.07.2025 KW - AI, RAG, LLM, Knowledge Graph PY - 2025 AN - OPUS4-63860 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias T1 - Enhancement of Fire Test Stand Performance at Test Site of BAM: Installation and Evaluation of an Augmented System with a Fire Reference Package N2 - Packages for the transport of radioactive material are designed to endure severe accidents. Packages for the transportation of radioactive material must demon-strate that the package can withstand certain prescribed tests from the IAEA Reg-ulations [1]. In addition to mechanical tests, a thermal test in form of a fire test must be carried out. As packages to be tested at BAM are significantly larger than previous package designs, BAM has expanded an existing fire test stand. A modular concept is chosen, which means that the arrangement of the burner noz-zles can be adapted to the test specimen. The dimensions of the burner rings, the type, the orientation and the number of burner nozzles can be varied depending on the test specimen. In addition, various pumps can be used to set the corre-sponding mass flow. With the help of a calorimeter test, the fire test stand can be qualified for a specific size of packages regarding the boundary conditions of the IAEA Regulations [1]. Due to the typically wood filled impact limiters in German package designs, a fire test is necessary, as experiments have shown that possible openings that occurred during a mechanical test contributed to the ignition of the wood filled impact limiters within the prescribed 30 minutes of the IAEA Regula-tions [1]. From a series of experiments, two experiments are presented to show the possibilities to obtain different temperatures and temperature rates in the test specimen. In addition to sensor data, the heat flux into the package is calculated to verify that the IAEA boundary conditions are satisfied. In addition to the tem-perature data, other data such as wind speed and wind direction are also recorded to explain subsequent effects in the measurement data in a comprehensible man-ner. T2 - Sandia-BAM Technical Exchange CY - Albuquerque, NM, USA DA - 23.07.2025 KW - IAEA Regulations KW - Fire Test Stand KW - Accident Scenario KW - Fire Qualification PY - 2025 AN - OPUS4-63861 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Müller, Lars A1 - Neumann, Martin A1 - Wille, Frank T1 - Shipment of SCO-II – Authority assessment of mechanical aspects and quality management N2 - The decommissioning of nuclear facilities necessitates either the storage or disposal of large radioactive components such as steam generators, pressurizers, reactor pressure vessels and heads, or coolant pumps. These components or objects are large in size and mass with up to 6 meters in diameter and 20 meters in length and a weight of up to 400 tons. They are often transported to a storage, disposal, or recycling facility. Large components from nuclear facilities may often not be packed and need to be transported unpackaged due to size and weight. T2 - PATRAM 2025 CY - San Antonio, TX, USA DA - 27.07.2025 KW - radioaktive Stoffe, Rückbau kerntechnischer Anlagen, Transport, Gefahrgut PY - 2025 SP - 1 EP - 10 AN - OPUS4-63878 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Shipment of SCO-II – Authority assessment of mechanical aspects and quality management N2 - The decommissioning of nuclear facilities necessitates either the storage or disposal of large radioactive components such as steam generators, pressurizers, reactor pressure vessels and heads, or coolant pumps. These components or objects are large in size and mass with up to 6 meters in diameter and 20 meters in length and a weight of up to 400 tons. They are often transported to a storage, disposal, or recycling facility. Large components from nuclear facilities may often not be packed and need to be transported unpackaged due to size and weight. T2 - PATRAM 2025 CY - San Antonio, TX, USA DA - 27.07.2025 KW - Transport KW - Radioaktive Stoffe KW - Rückbau kerntechnischer Anlagen KW - Gefahrgut PY - 2025 AN - OPUS4-63877 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Quercetti, Thomas T1 - Fire Test Stand for Thermal Testing of Large Packages for the Transport of Radioactive Materials N2 - Packages for the transport of spent nuclear fuel are designed to withstand severe accidents and must ensure compliance with the IAEA-Regulations prescribing mechanical tests followed by a thermal test. The thermal test involves that a test specimen is exposed to a thermal environment for 30 minutes, simulating the conditions of a hydrocarbon fuel-air fire. The average fire temperature is at least 800°C, and the fire completely engulfs the test specimen. In advance of a regular fire test, BAM performs so-called fire reference tests or calorimeter tests with a fire reference package (FRP) to determine the test conditions for compliance with the IAEA-requirements. T2 - PATRAM 2025 CY - San Antonio, TX, USA DA - 27.07.2025 KW - Experiment KW - Thermal Test KW - Fire PY - 2025 AN - OPUS4-63871 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias T1 - AI-Based Documentation Analysis for Safety Assessment of Packages for Radioactive Material N2 - The transportation of radioactive material requires, dependent on type and quantity of the radioactive material, a regulatory approval based on the package type. Safety assessments shall be conducted in compliance with the International Atomic Energy Agency (IAEA) regulations and documented in a comprehensive package design safety report to obtain approval from authority. This comprehensive safety report evaluates a broad range of requirements from the regulations, including mechanical, thermal, shielding, criticality and transport requirements and controls, and testing assessments. Additionally, it encompasses supporting documents such as specifications, inspections, certifications, drawings, and guidelines in a variety of complex documents. Safety and manufacturing reports contain multiple interconnected sub-reports covering various topics. Changes, such as component modifications, material property updates, or regulatory revisions, often impact multiple sections of the safety analysis reports, making even minor adjustments complex and time-consuming. Each transport package has unique requirements to be fulfilled, making every safety report distinct, despite following the same regulatory framework. Most documentation exists in standard digital formats but is often not machine interpretable, preventing automated analysis of the critical dependencies between them. This paper argues that moving beyond simple digitization towards structured knowledge representation is essential for addressing these challenges. We propose a multi-stage approach, beginning with foundational AI technologies such as Large Language Models (LLMs) and Retrieval-Augmented Generation (RAG), and progressing toward the construction of Knowledge Graphs (KGs). KGs convert unstructured and semi-structured information into a connected, queryable network, enabling precise tracing and visualization of complex interdependencies within the documentation landscape. By linking interpretable content directly to datasheets, tables, simulations, experimental results, standards, and regulations, such a system would automatically identify changes and interdependencies. Related conditions could be validated using AI-based tools, reducing the need for manual intervention, improving both efficiency and safety. Human error plays a significant role in drafting, reviewing, and revising safety reports, often requiring iterative review cycles and multiple reviewers before approval. A digital quality infrastructure could reduce iterations and further improve efficiency. Integrating AI into this process could optimize safety assessments and enhance their robustness by leveraging interpretability to enhance safety. This preliminary study explores the readiness and requirements for using intelligent documentation analysis system in the context of regulatory compliance for package safety for the transport of radioactive material. By analysing current documentation workflows, we identify how LLM-based tools can interpret complex safety reports and highlight critical interdependencies and then demonstrate why a KG-based architecture is necessary to robustly manage and query critical interdependencies. This lays the groundwork for future agentic AI systems capable of proactively supporting the safety assessment lifecycle, while stressing the importance of robust data governance and AI reliability in this highly regulated context. T2 - PATRAM 2025 CY - San Antonio, TX, USA DA - 27.07.2025 KW - Knowledge Graph KW - AI KW - RAG KW - LLM PY - 2025 AN - OPUS4-63862 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin A1 - Gleim, Tobias A1 - Quercetti, Thomas A1 - Wille, Frank T1 - Evaluation of Convective Heat Transfer Coefficients with CFD for Heat Flux Calculation in Combustion Chamber N2 - Packages for the transport of high-level radioactive waste are designed to withstand severe accidents. To obtain approval for transport, these packages must adhere to the specification-based criteria of regulations established by the International Atomic Energy Agency (IAEA). To ensure compliance with the regulations, mechanical and thermal tests need to be conducted regarding the package type. The requirements define mechanical tests followed by a thermal test, including criteria ensuring the package design’s ability to withstand severe accidents. Heavy-weight packages for the safe transport of radioactive materials are equipped with impact limiters, which are often built with porous materials such as densely packed wood reinforced by steel sheet structures. These components absorb the kinetic energy during the impact of the package in drop tests and thus dampen the acceleration of other package components which supports the package to meet the requirements of the IAEA regulations. Following the mechanical tests, the package must, with its predamaged impact limiters, endure a thermal test defined precisely in the IAEA regulations. The thermal test is defined as a 30-min, fully engulfing 800 °C fire and a following time under ambient conditions for a sufficient period to ensure that temperatures in the specimen decrease in all parts of the specimen. During and following the thermal test, the specimen shall not be artificially cooled, and any combustion of materials of the specimen shall be permitted to proceed naturally. A wood-filled impact limiter can continue to release thermal energy during an ongoing combustion process, thus defining relevant package temperatures. Heat flux from a potentially burning impact limiter to the package is important for the safety evaluation of transport packages. A test setup was developed to approach the energy flow investigation and examine the combustion behaviour of porous materials encapsulated in predamaged cylindrical metal enclosures under various conditions. The setup consists of a combustion chamber for thermal tests under adjustable and defined boundary conditions. The temperature development of the test specimens can be observed from outside using a thermographic imager with high-definition cameras, and the mass loss of the test specimen can be measured in the combustion chamber. Convective heat transfer coefficients for various boundary conditions must be defined for use with experimentally gathered test specimen surface temperature data for heat flux evaluations. The airflow conditions in the combustion chamber were analysed using computational fluid dynamics (CFD) calculations in OpenFOAM with respect to the convective heat transfer coefficients at the surface of a hot test specimen. A convergence study was performed, and sensitivity analyses for different test specimen surface temperatures and exhaust gas volume flows were conducted. T2 - ASME PVP2025, Pressure Vessels & Piping Conference CY - Montreal, Quebec, Canada DA - 20.07.2025 KW - Heat Transfer KW - Convection KW - OpenFOAM KW - Combustion PY - 2025 SP - 1 EP - 7 PB - American society of mechanical engineers (ASME) AN - OPUS4-63901 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Quercetti, Thomas A1 - Feldkamp, Martin A1 - Gleim, Tobias A1 - Musolff, Andre A1 - Werner, Jan A1 - Wille, Frank T1 - A fire test stand for thermal testing of extra-large packages N2 - Packages for the transport of high-level radioactive materials are designed to withstand severe accidents. These packages must adhere to the specification-based criteria of the International Transport Regulations of the International Atomic Energy Agency (IAEA). To ensure compliance with these requirements, specific mechanical and thermal tests need to be addressed with respect to the package type. Typically, the Regulations prescribe mechanical tests followed by a thermal test as part of a cumulative test scenario. The thermal test is specified by the exposure of a test specimen for a period of 30 minutes to a thermal invironment that provides a heat flux equivalent to that of a hydrocarbon fuel-air fire with an average fire temperature of at least 800 °C fully flame engulfing the test specimen. The Federal Institute for Materials Research and Testing (BAM) operates various test facilities for this purpose at their test site (TTS) near Berlin in Germany. Thermal tests for large packages are carried out in an established fire test stand that can be adapted by the test-setup to the geometric boundary conditions of a test specimen. This fire test stand is built for test specimens with masses up to 200,000 kg and geometric dimensions relating to large transport packages including their impact limiters. The test specimen is usually placed on a water-cooled support frame in the middle of the test-stand. The fire is realized by burning propane gas which is released in liquid state from an array of gas nozzles arranged in the form of a burner ring surrounding the test specimen. For particularly extra-large test specimens, two burner rings are used on top of each other and at different heights in order to firstly achieve full fire engulfment with a significantly larger volume of fire and secondly to achieve the required heat output. In advance of a regular thermal test BAM usually performs so-called fire reference tests to determine the test conditions for compliance with the IAEA requirements. These tests are performed using a generic package which corresponds to the external geometric dimensions of the test specimen used later in the approval test. Then, this reference package is exposed to a fire under defined test parameters whereas the corresponding heat input determined from the temperature changes measured is regarded as main criterion for proofing compliance with the IAEA criteria.The paper shows the experimental proof of the suitability of BAM’s fire test stand for thermal testing of extra-large packages. The heat input and fire temperatures fully meet the IAEA criteria but can also be set significantly higher for e.g. extra-regulatory testing. T2 - ASME PVP 2025 CY - Montreal, Quebec, Kanada DA - 20.07.2025 KW - Test stand KW - Thermal testing KW - Package KW - Fire PY - 2025 SP - 1 EP - 6 AN - OPUS4-63892 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias T1 - Potential Effects of Battery and Hydrogen Fires regarding Regulatory Requirements N2 - Die internationalen Sicherheitsanforderungen für den Transport radioaktiver Stoffe sind in den IAEO-Vorschriften SSR-6 festgelegt. Diese wurden in den 1960er Jahren entwickelt und seitdem nur in begrenztem Umfang angepasst. Sie bilden die Basis für die Regelwerke der verschiedenen Verkehrsträger – darunter auch das ADR (Europäisches Übereinkommen über die internationale Beförderung gefährlicher Güter auf der Straße). Die SSR-6 wird regelmäßig vom TRANSSC-Gremium der IAEO überprüft und aktualisiert. In diesen Prozess fließen aktuelle wissenschaftliche Erkenntnisse sowie praktische Erfahrungen ein, um die Sicherheit beim Transport radioaktiver Materialien kontinuierlich zu verbessern. Im Rahmen der 47. TRANSSC-Sitzung stellte die BAM (Bundesanstalt für Materialforschung und -prüfung) aktuelle Forschungsergebnisse zu Unfallszenarien mit Batterien und Wasserstoff vor und adressierte zentrale sicherheitsrelevante Fragestellungen. Aufgrund des großen internationalen Interesses, insbesondere da vergleichbare Erkenntnisse aus anderen UN-Mitgliedstaaten bislang nicht vorlagen, wurden diese Fragestellungen ab der 48. Sitzung offiziell in das Arbeitsprogramm aufgenommen. Vor der 48. TRANSSC-Sitzung führten BAM und BASE eine gemeinsame Befragung aller UN-Mitgliedstaaten mittels eines Fragebogens durch. Die Ergebnisse wurden im Rahmen der 48. TRANSSC-Sitzung vorgestellt. Dabei zeigte sich, dass in den befragten Ländern bislang keine spezifischen nationalen Regelungen oder Einschränkungen im Hinblick auf Fahrzeuge mit alternativen Antrieben bestehen. Gleichzeitig wurde jedoch auf ein potenzielles Risiko mit derzeit nicht abschätzbarem Ausmaß hingewiesen. N2 - Hier: The IAEA regulations for the safe transport of radioactive material (IAEA SSR-6) define the safety requirements for different package types and consider different transport conditions. The accident conditions of transport specify different mechanical and thermal tests based on investigations of real accident scenarios. Considering the rapid development of new boundary conditions of transport such as electric mobility and the use of hydrogen as energy source for trucks and other kind of vehicles, potential effects of battery and hydrogen fires in transport accidents should be investigated. The aim is to evaluate the existing test requirements developed and derived decades ago, whether they are covering the current transport situation. This presentation will briefly present the reasons for detailed investigations as bases for a coordinated research project under the roof of the IAEA. T2 - WP.15 IWG-EV 22nd session CY - Online-Meeting DA - 23.07.2025 KW - Requirements KW - Battery Fire KW - Experiment KW - IAEA PY - 2025 AN - OPUS4-63900 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin T1 - Evaluation of Convective Heat Transfer Coefficients with CFD for Heat Flux Calculation in Combustion Chamber N2 - Packages for the transport of high-level radioactive waste are designed to withstand severe accidents. To obtain approval for transport, these packages must adhere to the specification-based criteria of regulations established by the International Atomic Energy Agency (IAEA). To ensure compliance with the regulations, mechanical and thermal tests need to be conducted regarding the package type. The requirements define mechanical tests followed by a thermal test, including criteria ensuring the package design’s ability to withstand severe accidents. Heavy-weight packages for the safe transport of radioactive materials are equipped with impact limiters, which are often built with porous materials such as densely packed wood reinforced by steel sheet structures. These components absorb the kinetic energy during the impact of the package in drop tests and thus dampen the acceleration of other package components which supports the package to meet the requirements of the IAEA regulations. Following the mechanical tests, the package must, with its predamaged impact limiters, endure a thermal test defined precisely in the IAEA regulations. The thermal test is defined as a 30-min, fully engulfing 800 °C fire and a following time under ambient conditions for a sufficient period to ensure that temperatures in the specimen decrease in all parts of the specimen. During and following the thermal test, the specimen shall not be artificially cooled, and any combustion of materials of the specimen shall be permitted to proceed naturally. A wood-filled impact limiter can continue to release thermal energy during an ongoing combustion process, thus defining relevant package temperatures. Heat flux from a potentially burning impact limiter to the package is important for the safety evaluation of transport packages. A test setup was developed to approach the energy flow investigation and examine the combustion behaviour of porous materials encapsulated in predamaged cylindrical metal enclosures under various conditions. The setup consists of a combustion chamber for thermal tests under adjustable and defined boundary conditions. The temperature development of the test specimens can be observed from outside using a thermographic imager with high-definition cameras, and the mass loss of the test specimen can be measured in the combustion chamber. Convective heat transfer coefficients for various boundary conditions must be defined for use with experimentally gathered test specimen surface temperature data for heat flux evaluations. The airflow conditions in the combustion chamber were analysed using computational fluid dynamics (CFD) calculations in OpenFOAM with respect to the convective heat transfer coefficients at the surface of a hot test specimen. A convergence study was performed, and sensitivity analyses for different test specimen surface temperatures and exhaust gas volume flows were conducted. T2 - ASME PVP2025, Pressure Vessels & Piping Conference CY - Montréal, Quebec, Canada DA - 20.07.2025 KW - Heat Transfer KW - Convective Heat Transfer Coefficient KW - Combustion KW - OpenFOAM KW - Computational Fluid Dynamics (CFD) PY - 2025 AN - OPUS4-63902 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin T1 - Design assessment, approval of management systems and ageing aspects of transport packages for radioactive material not requiring competent authority approval of design N2 - 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. T2 - 20th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 22) CY - Juan-les-Pins, France DA - 11.06.2023 KW - Radioactive material KW - Type A package KW - Management system KW - Tests KW - Non-approved PY - 2023 AN - OPUS4-57704 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schubert, Sven A1 - Komann, Steffen A1 - Neumann, Martin A1 - Reichardt, Adrian A1 - Müller, Lars A1 - Wille, Frank T1 - Ageing management measures of transport packages for radioactive materials N2 - The consideration of ageing mechanisms is with integration into the IAEA-requirements now obligatory for the design of transport packages. For packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance are required. Therefore, these packages have been maintained during storage in a manner that all requirements specified in the IAEA-requirements and in the applicable certificates of approval have been fulfilled. BAM is the competent authority in Germany for evaluating the thermal and mechanical design of packages for the transport of radioactive materials. In this context, BAM also evaluates the aging mechanisms and aging effects occurring during the long-term storage period of such transport packages. BAM has developed a guideline for the implementation of ageing assessment and of the measures for ageing management into the approval procedure based on IAEA-requirements. The goal of the presented paper is to introduce this guideline and the general approach for ageing management requirements and to describe the application to a specific package design. The type and amount of the ageing management not only depend on the use of the packaging, but also on the accessibility of the components that are considered in the ageing assessment. The different operating phases of a packaging are considered for the ageing assessment, such as loading, interim storage or transport. The implementation of measures for ageing management is divided into three levels – systemic measures, package design related measures and documentation. The systemic measures are attributed to the general management system and define the whole activities for organization of ageing management like structure, responsibilities, documentation, reports and evaluation. The package design related measures are defined in an ageing management plan. These measures shall ensure that the anticipated changes of the package design under consideration of ageing effects still complies with the design approval specification. Therefore, an ageing surveillance program and, if necessary, a gap analysis program shall be developed. The ageing management documentation ensures the continuous documentation of the compliance of a specific package to the approved package design, comprising mainly records resulting from operation and surveillance. T2 - RAMTRANS 2024 CY - London, United Kingdom DA - 15.05.2024 KW - Radioactive Materials KW - Ageing Management KW - Transport Packages KW - Dual Purpose Casks PY - 2024 VL - 2024 SP - 1 EP - 8 PB - Nuclear Institute CY - London AN - OPUS4-60186 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Transportbehälter für Klasse 7 - Ein Überblick N2 - Die Präsentation gibt einen Überblick über die Tranportbehälter der Klasse 7. Behandelt werden neben der Versandstückklassifikation auch die Anforderungen an diese Verpackungen gemäß der gefahrgutrechtlichen Vorschriften. T2 - 30. Münchner Gefahrguttage CY - Online meeting DA - 20.07.2020 KW - Gefahrgutrecht KW - Transportbehälter KW - Radioaktives Material KW - Zulassungspflichtige Versandstücke PY - 2020 AN - OPUS4-51104 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schubert, Sven T1 - BAM-GGR 023 - Ageing Management for CA Approved RAM Transport Packages N2 - The consideration of ageing mechanisms is with integration into the IAEA-requirements now obligatory for the design of transport packages. For packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance are required. Therefore, these packages have been maintained during storage in a manner that all requirements specified in the IAEA-requirements and in the applicable certificates of approval have been fulfilled. BAM is the competent authority in Germany for evaluating the thermal and mechanical design of packages for the transport of radioactive materials. In this context, BAM also evaluates the aging mechanisms and aging effects occurring during the long-term storage period of such transport packages. BAM has developed a guideline for the implementation of ageing assessment and of the measures for ageing management into the approval procedure based on IAEA-requirements. The goal of the presented paper is to introduce this guideline and the general approach for ageing management requirements and to describe the application to a specific package design. The type and amount of the ageing management not only depend on the use of the packaging, but also on the accessibility of the components that are considered in the ageing assessment. The different operating phases of a packaging are considered for the ageing assessment, such as loading, interim storage or transport. The implementation of measures for ageing management is divided into three levels – systemic measures, package design related measures and documentation. The systemic measures are attributed to the general management system and define the whole activities for organization of ageing management like structure, responsibilities, documentation, reports and evaluation. The package design related measures are defined in an ageing management plan. These measures shall ensure that the anticipated changes of the package design under consideration of ageing effects still complies with the design approval specification. Therefore, an ageing surveillance program and, if necessary, a gap analysis program shall be developed. The ageing management documentation ensures the continuous documentation of the compliance of a specific package to the approved package design, comprising mainly records resulting from operation and surveillance. T2 - RAMTRANS 2024 CY - London, United Kingdom DA - 15.05.2024 KW - Radioactive Materials KW - Ageing Management KW - Transport Packages KW - Dual Purpose Casks PY - 2024 AN - OPUS4-60177 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GOVDOC A1 - Neumann, Martin T1 - Measures for quality and ageing management for non-competent authority approved package designs for the transport of radioactive material N2 - The BAM-GGR 016 explains the requirements of ADR, RID, ADN and IMDG for management systems for design, manufacturing, testing, documentation, use, maintenance, and inspection of packagings for package designs for the transport of radioactive material not requiring competent authority approval for all designs of exempted packages, packages type IP-1, IP-2, IP-3 and type A. KW - Not requiring competent authority approval KW - Radioactive material KW - Transport PY - 2024 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-636506 VL - BAM-GGR 016 SP - 1 EP - 25 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin ET - Revision 1 AN - OPUS4-63650 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias A1 - Komann, Steffen T1 - Fracture Mechanical Analyses of a Welding Seam of a Thick-Walled Transport Package N2 - Transport packages shall satisfy various safety criteria regarding mechanical, thermal and radiation phenomena. Typical requirements focusing mechanical aspects are usually drop tests in accordance with IAEA regulations [1]. The drop tests are usually carried out experimentally and, as an additional measure, finite element analyses (FEA) are performed. A specific part of the investigations presented is the evaluation of the welding seam connecting cask shell and cask bottom. Experimental results and FEA are presented and compared. The evaluation of the welding seam performed includes a variety of aspects. In addition to the experimental and analytical stresses determined, different standards are used to investigate a possible crack initiation. Several destructive and non-destructive tests are performed for quality assurance in the manufacturing process as well as for different input parameters. The necessary monitoring and non-destructive measurement methods to define the boundary conditions of the standards are introduced. Taking into account all required parameters, the welding seam is examined and evaluated using the failure assessment diagrams (FAD) of the respective standards. It can be shown under the given boundary conditions that considering the experimental data, the welding seam is in the context of crack initiation below the enveloping curve in the acceptable region. More critical drop tests to be conducted are proposed and need to be investigated in future work. T2 - Pressure Vessels & Piping Conference® 2022 CY - Las Vegas, NV, USA DA - 17.07.2022 KW - Drop test KW - Fracture initiation KW - Transport package PY - 2022 AN - OPUS4-55374 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin T1 - Friction coefficients for wood-wood and wood-steel contacts N2 - 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. T2 - Sandia-BAM Workshop CY - Berlin, Germany DA - 21.11.2022 KW - Wood KW - Friction KW - Transport cask PY - 2022 AN - OPUS4-56342 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias A1 - Neumann, Martin A1 - Linnemann, Konrad A1 - Wille, Frank T1 - Fracture Mechanical Analyses of a Welding Seam of a Thick-Walled Transport Package N2 - 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. T2 - PATRAM 22 - The International Symposium on the Packaging and Transportation of Radioactive Materials CY - Juan-Les-Pins, Antibes, France DA - 11.06.2023 KW - Transport Package KW - Welding KW - Fracture Mechanics PY - 2023 SP - 1 EP - 10 AN - OPUS4-57696 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias T1 - Welding Seam Safety Evaluation in a Thick-Walled Type B Transport Package N2 - 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 above-mentioned standards and taking into account the IAEA requirements with respect to defect sizes, material properties, primary and residual stress, yield strength etc. T2 - PATRAM 22 - The International Symposium on the Packaging and Transportation of Radioactive Materials CY - Juan-Les-Pins, France DA - 11.06.2023 KW - Welding KW - Fracture Mechanics KW - Transport Package PY - 2023 AN - OPUS4-57695 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin T1 - Friction coefficients for wood-wood and wood-steel interfaces in impact limiters for transport casks N2 - 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. T2 - 20th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 22) CY - Juan-les-Pins, France DA - 11.06.2023 KW - Wood KW - Friction KW - Transport cask PY - 2023 AN - OPUS4-57702 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen T1 - Ageing management measures for transport packages for radioactive materials N2 - The consideration of ageing mechanisms is with integration into the IAEA-requirements now obligatory for the design of transport packages. For packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance are required. Therefore, these packages have been maintained during storage in a manner that all requirements specified in the IAEA-requirements and in the applicable certificates of approval have been fulfilled. BAM is the competent authority in Germany for evaluating the thermal and mechanical design of packages for the transport of radioactive materials. In this context, BAM also evaluates the aging mechanisms and aging effects occurring during the long-term storage period of such transport packages. BAM has developed a guideline for the implementation of ageing assessment and of the measures for ageing management into the approval procedure based on IAEA-requirements. The goal of the presented paper is to introduce this guideline and the general approach for ageing management requirements and to describe the application to a specific package design. The type and amount of the ageing management not only depend on the use of the packaging, but also on the accessibility of the components that are considered in the ageing assessment. The different operating phases of a packaging are considered for the ageing assessment, such as loading, interim storage or transport. The implementation of measures for ageing management is divided into three levels – systemic measures, package design related measures and documentation. The systemic measures are attributed to the general management system and define the whole activities for organization of ageing management like structure, responsibilities, documentation, reports and evaluation. The package design related measures are defined in an ageing management plan (AMP). Therefore, an ageing surveillance program (ASP) and, if necessary, a gap analysis program has to be developed. The ageing management documentation (AMD) ensures the continuous documentation of the compliance of a specific package to the approved package design, comprising mainly records resulting from operation and surveillance. T2 - PVP2023-Pressure, Vessels & Piping Conference CY - Atlanta, GA, USA DA - 16.07.2023 KW - Radioaktive Stoffe KW - Transport KW - Gefahrgut PY - 2023 AN - OPUS4-58003 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin A1 - Feldkamp, Martin A1 - Linnemann, Konrad A1 - Wille, Frank T1 - Transport of HLW canisters on sea vessels N2 - Germany had been transporting spent fuel to the reprocessing plant in Sellafield and La Hague for decades until around 2005. Resulting from the obligation to take back the vitrified high-level waste from reprocessing six CASTOR® HAW28M filled with 168 canisters with radioactive waste in vitrified form were transported from Sellafield to the interim storage facility Biblis in 2020. Rail wagons were used for the transport to the port in Barrow-in-Furness, where they were loaded into a dedicated seagoing vessel, certified as INF Class 3 according to the INF Code. This was the first time that vitrified high level waste with considerable heat load was transported under a German design approval certificate. BAM was involved in the authority assessment of the conditions for the sea transport. For the first transport BAM required among others, assessment of temperature distribution during transport, logging of temperatures of cargo bays and graphical imaging of temperatures of the bay with the cask in order to ensure compliance with temperature specifications, e.g. maximal neutron absorber and gasket temperatures. Special interest was taken in the identification of possible events exceeding the specified temperatures considering the different philosophies of IMDG code and its supplement INF code regarding temperature control of hatches. Results show compliance with assumed conditions. T2 - RAMTrans 2024 CY - London, United Kingdom DA - 14.05.2024 KW - Transport KW - Spent nuclear fuel KW - Ship KW - Sea KW - High level waste PY - 2024 SP - 1 EP - 8 AN - OPUS4-60092 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Neumann, Martin A1 - Gröke, Carsten A1 - Wille, Frank T1 - BAM-GGR 016 - Auf dem aktuelle Stand N2 - Die BAM-GGR 016 zur Anerkennung und Überwachung von Managementsystemen für nicht zulassungspflichtige Verssandstücke für radioaktive Stoffe wurde kürzliche erstmals revidiert. KW - BAM-GGR 016 KW - Überwachung KW - Anerkennung KW - Radioaktive Stoffe PY - 2024 SN - 0944-6117 IS - 5 SP - 11 EP - 13 PB - Verlag Heinrich Vogel CY - München AN - OPUS4-59998 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin T1 - Transport of HLW canisters on sea vessels N2 - Germany had been transporting spent fuel to the reprocessing plant in Sellafield and La Hague for decades until around 2005. Resulting from the obligation to take back the vitrified high-level waste from reprocessing six CASTOR® HAW28M filled with 168 canisters with radioactive waste in vitrified form were transported from Sellafield to the interim storage facility Biblis in 2020. Rail wagons were used for the transport to the port in Barrow-in-Furness, where they were loaded into a dedicated seagoing vessel, certified as INF Class 3 according to the INF Code. This was the first time that vitrified high level waste with considerable heat load was transported under a German design approval certificate. BAM was involved in the authority assessment of the conditions for the sea transport. For the first transport BAM required among others, assessment of temperature distribution during transport, logging of temperatures of cargo bays and graphical imaging of temperatures of the bay with the cask in order to ensure compliance with temperature specifications, e.g. maximal neutron absorber and gasket temperatures. Special interest was taken in the identification of possible events exceeding the specified temperatures considering the different philosophies of IMDG code and its supplement INF code regarding temperature control of hatches. Results show compliance with assumed conditions. T2 - RAMTrans 2024 CY - London, GB DA - 14.05.2024 KW - Transport KW - Spent nuclear fuel KW - Ship KW - Sea KW - High level waste PY - 2024 AN - OPUS4-60091 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias T1 - AI-Based Documentation Analysis for Safety Assessment of Packages for Radioactive Material N2 - The transportation of radioactive material requires, dependent on type und quantity of the radioactive material, a regulatory approval based on the type of the package. Safety assessments shall be conducted in compliance with the IAEA regulations and documented in a comprehensive package design safety report to obtain approval from authority. This comprehensive safety report evaluates a broad range of requirements from the regulations, including mechanical, thermal, shielding, criticality and transport requirements and controls, and testing assessments. Additionally, it encompasses supporting documents such as specifications, inspections, certifications, drawings, and guidelines in a variety of complex documents. Safety and manufacturing reports contain multiple interconnected sub-reports covering various topics. Changes, such as component modifications, material property updates, or regulatory revisions, often impact multiple sections of the safety analysis reports, making even minor adjustments complex and time-consuming. Each transport package has unique requirements, making every safety report distinct, despite following the same regulatory framework. Most documentation exists in standard digital formats but is often not machine interpretable. This lack of interpretability means individuals must manually identify and address dependencies within the reports. An AI-based documentation system that visualizes these dependencies would significantly enhance the efficiency of safety assessments. By linking interpretable content directly to datasheets, tables, simulations, experimental results, standards, and regulations, such a system would automatically identify changes and interdependencies. Related conditions could be validated using AI-based tools, reducing the need for manual intervention, improving both efficiency and safety. Human error plays a significant role in drafting, reviewing, and revising safety reports, often requiring iterative review cycles and multiple reviewers before approval. A digital quality infrastructure could reduce iterations and further improve efficiency. Integrating AI into this process could optimize safety assessments and enhance their robustness by leveraging interpretability to enhance safety. This preliminary study explores the readiness and requirements for using LLMs and RAG in the context of regulatory compliance for transport of radioactive material. By analyzing current documentation workflows, we identify how LLM-based tools can interpret complex safety reports and highlight critical interdependencies. We stress the importance of robust data governance, confidentiality measures, and AI reliability in this highly regulated context. T2 - BAM – Fraunhofer Materials LLM Days CY - Würzburg, Germany DA - 03.07.2025 KW - KI KW - RAG KW - LLM PY - 2025 AN - OPUS4-63727 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Reichardt, Adrian T1 - Introduction of An Ageing Management Approach for Dual Purpose Casks N2 - With integration of the new para 613A into SSR-6 [1] the consideration of ageing mechanisms is now obligatory for the design of packages and their approval. In addition, para 809(f) of SSR-6 [1] requires consideration of the effects of storage on ageing mechanisms, safety analyses and operation and maintenance instructions. German competent authorities Bundesanstalt für Materialforschung und -prüfung (BAM) and Bundesamt für die Sicherheit der nuklearen Entsorgung (BASE) are considering the aspect of ageing in approval procedures. Ageing assessment is mainly focused on dual purpose casks (DPC) package designs which are long-term stored in interim storage facilities. T2 - BAM-IRSN Symposium 2021 CY - Online meeting DA - 08.09.2021 KW - Ageing KW - DPC KW - Interim storage KW - Ageing management PY - 2021 AN - OPUS4-53287 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin A1 - Gleim, Tobias A1 - Gradt, Thomas A1 - Wille, Frank T1 - Friction coefficients for wood-wood and wood-steel interfaces in impact limiters for transport casks N2 - 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. T2 - 20th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Juan-les-Pins, France DA - 11.06.2023 KW - Wood KW - Friction KW - Transport cask PY - 2023 SP - 1 EP - 11 AN - OPUS4-57334 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Werner, Jan T1 - Brandschutzbeschichtungen an Tanks - Prüfverfahren zur Bestimmung der Feuerwiderstandsfähigkeit von Druckbehältern mit einem Brandschutzsystem unter Standardbrandbedingungen - ISO 21843 N2 - Brandschutzbeschichtungen an Tanks können zuverlässig BLEVEs verhindern. Die ISO 21843 gibt hierzu neue Standards für Prüfverfahren vor und charakterisiert die Qualität von Unfallfeuern detaillierter als bisher. Die BAM hat auf ihren Prüfanlagen im TTS die Umsetzbarkeit dieser Anforderungen nachgewiesen. T2 - 29. Gefahrgutkongress Mecklenburg-Vorpommern CY - Rostock, Germany DA - 18.11.2025 KW - ISO 21843 KW - BLEVE KW - Brandschutz KW - Unfallfeuer KW - Wärmeübertragung PY - 2025 AN - OPUS4-64806 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Werner, Jan T1 - Verpackungen und Beförderungseinheiten im Zusammenspiel N2 - Die derzeitigen Explosivstoffschutz-Anforderungen des Regelwerks ADR basieren auf einem überholten Stand der Technik sowie Technologie der Baustoffe/Bauteile/Werkstoffe. Die Formulierung im entsprechenden Abschnitt des ADR (9.3.4.2) ist nicht eindeutig und verweist auf eine Norm, welche als kritisch angesehen wird. Diese Unklarheiten führen bei den Ausrüstern und Betreibern der Gefahrgutfahrzeuge zu Unsicherheiten mit existenziellen Risiken und Kosten. Es ist hier sowohl aus wirtschaftlicher als auch aus sicherheitstechnischer Sicht vordringlicher Klärungsbedarf erkennbar. Eine Klärung ist zudem dringlich, weil sich auch international bei den beteiligten Akteuren der ADR-Vertragsparteien Fragen zur Klärung der Technologieentwicklung und dem Stand der Technik ergeben haben. Um eine Überarbeitung der ergänzenden Vorschriften für EX/III-Fahrzeuge zur Beförderung von explosiven Stoffen und Gegenständen der Klasse 1 in Versandstücken voranzutreiben, ist deshalb eine Untersuchung der Gefahren erforderlich, denen explosive Stoffe und Gegenstände während der Beförderung ausgesetzt sind. Die beschriebenen Unschärfen der heutigen Vorschriften sollten im Rahmen eines Forschungsvorhabens des Bundesministeriums für Digitales und Verkehr (BMDV) durch eine neuerliche Untersuchung beseitigt werden. Hierzu wurden auf Grundlage der heutigen Vorschriften bestehende konstruktive Lösungen untersucht und deren Wirksamkeit gegenüber einer typischen Wärmebelastung von außen festgestellt. Erforderlich dafür war zunächst die Charakterisierung der Wärmeeinträge durch Versuche mit typischen Unfallbelastungen. Daraus abzuleiten waren dann idealisierte Belastungsszenarien, welche als Voraussetzung für eine Normungsarbeit angesehen werden sollen. Im letzten Schritt soll ein Textentwurf für die Erneuerung der bestehenden Vorschriften des ADR verfasst und im Anschluss international abgestimmt werden. Es soll ein völlig neuer Ansatz zur Auslegung und Bewertung von Bauteilen von EX/III-Fahrzeugen für den Einsatz als Schutzschild gegenüber externer Wärmebelastung gefunden werden. Dieser begründet sich auf neuen technischen Erkenntnissen, welche eine Feuerbelastung heute nicht mehr allein durch eine Einheits-Temperaturkurve (ETK), sondern differenziert nach konvektiven und strahlenden Anteilen betrachtet. Mit ähnlicher technischer Zielrichtung wurde international der neue Standard „Bestimmung der Beständigkeit von Brandschutzmaterialien und -systemen für Druckbehälter gegenüber Kohlenwasserstoffpoolbränden“ als ISO 21843 in Jahr 2018 verabschiedet. Die jeweilige Wärmeleistung bzw. Wärmestromdichte soll mittels Kalorimeterversuchen bestimmt werden. Es gilt den Wärmeeintrag ins Innere der Ladeabteile zu begrenzen. Hierbei stellt sich nicht nur die Frage nach Isolationswirkung sowie Wärmeübergängen und ob dies nur durch Wandung sowie Boden sicherzustellen ist, sondern ob weitere Maßnahmen, wie Reifenschutz, automatische Feuerlöscheinrichtungen, etc. benötigt werden. Letztlich soll durch die Präzisierung der Gefahrgutvorschriften Transparenz bei Anwendern, Zulassungs- und Kontrollbehörden geschaffen werden. T2 - Gefahrguttechniktage 2025 CY - Berlin, Germany DA - 13.11.2025 KW - Explosivstoffe KW - Unfallszenarien KW - Brandbelastungen PY - 2025 AN - OPUS4-64808 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Widjaja, Martinus Putra A1 - Moosavi, Robabeh A1 - John, Sebastian A1 - Schumacher, David A1 - Grunwald, Marcel A1 - Auster, Jürgen A1 - Szczepaniak, Marius A1 - Mair, Georg W. A1 - Waske, Anja T1 - Impact damage evaluation of hydrogen composite pressure vessels by analysing computed tomography images N2 - The objective of this work is to find a method that describes the degree of damage from an impact experiment. This experiment was performed on Composite Pressure Vessels (CPV) in order to find the correlation of impact damage to the residual burst pressure. Computed Tomography (CT) approach was used to capture the before and after impact condition of the CPVs. The Wasserstein function was used to calculate how much the after impact image has differed from the original one. In the end, a good correlation was obtained to the residual burst pressure. T2 - HyFiSyn Conference CY - Online meeting DA - 15.09.2021 KW - Hydrogen KW - Composite pressure vessel KW - Carbon fibre KW - Burst test KW - Image analysis KW - Computed tomography (CT) PY - 2021 SP - 31 EP - 32 AN - OPUS4-53494 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Widjaja, Martinus Putra T1 - Impact damage evaluation of hydrogen composite pressure vessels by analysing computed tomography images N2 - The objective of this work is to find a method that describes the degree of damage from an impact experiment. This experiment was performed on Composite Pressure Vessels (CPV) in order to find the correlation of impact damage to the residual burst pressure. Computed Tomography (CT) approach was used to capture the before and after impact condition of the CPVs. The Wasserstein function was used to calculate how much the after impact image has differed from the original one. In the end, a good correlation was obtained to the residual burst pressure. The smaller the Wasserstein distance is, the higher the residual burst pressure would be and vice versa. T2 - HyFiSyn Conference CY - Online meeting DA - 15.09.2021 KW - Hydrogen KW - Composite pressure vessel KW - Carbon fibre KW - Burst test KW - Image analysis KW - Computed tomography (CT) PY - 2021 AN - OPUS4-53496 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - John, Sebastian T1 - Current results of the DELFIN project N2 - As a contribution to the national hydrogen strategy, 3.5 years ago, the Delfin research project started with the aim of developing a cost- and material-optimized hydrogen tank design for automotive application. Under the patronage of the National Organization Hydrogen and Fuel Cell Technology (NOW), a consortium consisting of 9 research institutes, component suppliers, engineering service providers and automobile OEMs is processing a wide range of work packages. The focus of BAM research sets on impact testing and safety-related characterization of pressure vessels of different development stages. Furthermore, the implementation of nondestructive testing methods is applied. The presentation shows an overview of the BAM work packages and an extraction of the results generated so far. T2 - Wasserstoffkolloquium des Kompetenzzentrums H2Safety@BAM CY - Online meeting DA - 16.02.2022 KW - Delfin KW - Wasserstoff KW - Druckbehälter KW - Impact PY - 2022 AN - OPUS4-55348 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -