TY - CONF A1 - Völzke, Holger T1 - Container requirements for high-level radioactive waste disposal in rock salt, claystone, and crystalline rock – Outcomes of the research project KoBrA N2 - Suitable containers for receiving high-level radioactive waste are a key elements of every repository system concerning different host rocks like rock salt, claystone and crystalline rock as being considered in Germany. The disposal container design is decisive regarding boundary conditions for the transport, emplacement techniques, and the operational and long-term safety assessment. The systematic derivation of the requirements to be placed on disposal containers forms the basis for a targeted, comprehensible and transparent development of containers that meet the requirements. The presentation summarizes the outcomes of the research project KoBrA. T2 - IGD-TP Symposium CY - Zurich, Switzerland DA - 20.09.2022 KW - Disposal KW - Container KW - Radioactive waste KW - Safety PY - 2022 AN - OPUS4-57021 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank T1 - Transport nach Zwischenlagerung, Besonderheiten des letzten Transports N2 - Transportierbarkeit von Transport- und Lagerbehältern für radioaktive Stoffe, welche nach eine längerfristigen trockenen Zwischenlagerung transportiert werden müssen. Überblick über die aktuellen Regelwerke und Richtlinien sowie die Zeitpläne für das Finden eines Endlagers für hochradioaktive Stoffe und die damit verbundene verlängerte Zwischenlagerung. Des Weiteren werden das für die verlängerte Zwischenlagerung notwendige Alterungsmanagement und die noch erforderlichen Forschungstätigkeiten vorgestellt. T2 - BGZ Fachworkshop Zwischenlagerung CY - Berlin, Germany DA - 16.11.2021 KW - Transportbehälter KW - Radioaktive Stoffe KW - Transport KW - Zwischenlagerung KW - IAEA PY - 2021 AN - OPUS4-60505 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank T1 - Verkehrsrechtliche Betrachtungen Transport- und Lagerbehälter - Wo geht die Reise hin? N2 - Transportierbarkeit von Transport- und Lagerbehältern für radioaktive Stoffe, welche nach eine längerfristigen trockenen Zwischenlagerung transportiert werden müssen. Überblick über die aktuellen Regelwerke und Richtlinien sowie die Zeitpläne für das Finden eines Endlagers für hochradioaktive Stoffe und die damit verbundene verlängerte Zwischenlagerung. Des Weiteren werden das für die verlängerte Zwischenlagerung notwendige Alterungsmanagement und die noch erforderlichen Forschungstätigkeiten vorgestellt. T2 - 10. Symposium Lagerung und Transport radioaktiver Stoffe CY - Hannover, Germany DA - 05.09.2023 KW - Transportbehälter KW - Radioaktive Stoffe KW - Transport KW - Zwischenlagerung KW - IAEA PY - 2023 AN - OPUS4-60506 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias T1 - Safety Aspects for Transport Containers with regard to Ageing and Battery Accident Scenarios N2 - In Germany, the search for a final repository for highly radioactive material is currently based on the assumption that interim storage will take considerably longer than was anticipated. At that time, authorization procedures assumed that interim storage would be brief, until the containment systems could be placed in a final repository. For today's new approvals and extensions, the IAEA (International Atomic Energy Agency) regulations for the transport of radioactive material require an assessment of all components and component groups with regard to ageing. To assess the safety requirements not only over the previously envisaged periods but also over long durations, numerous individual parts and component groups must be examined and evaluated for ageing and interactions between materials. The metal seals of a double lid sealing system, for example, are critical components that must be studied with respect to ageing. In a containment system for radioactive material, metal seals must not only undergo classic ageing, but also withstand mechanical influences and radiation over extended periods. In addition to assessments by the applicants, BAM must also independently analyze and evaluate these ageing mechanisms as part of its sovereign mandate. Another challenge in both new approvals and extensions is the assessment of transport regarding changes in the state of the art, which are not synchronously assessed in the regulations. In transporting radioactive material, a classic oil fire has been assumed in a hypothetical accident scenario from the development of the regulations to the present day. Due to the rapid development of propulsion technologies in recent years, such as battery or hydrogen-powered vehicles, investigations must be conducted in the revision process of the IAEA regulations to assess the impact of these new technologies on safety assessments. It is important for the member states of the IAEA to know whether new technologies are covered by the regulations or if changes are necessary to continue issuing international licenses. By focusing on batteries from the material to the cell to the module and the application, BAM contributes to the evaluation of batteries at every step of the chain. In addition to the safety of current and new battery technologies, BAM also endeavors to address issues of compositional trace and sustainable energy materials. T2 - MSD: Leaf CY - Livermore, CA , USA DA - 07.08.2024 KW - Safety Aspects KW - Ageing KW - Accident Scenarios KW - Battery PY - 2024 AN - OPUS4-60851 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Reichardt, Adrian A1 - Komann, Steffen T1 - Experience regarding ageing management and maintenance of transport packages in Germany N2 - The presentation gives an overview about the current experiences of BAM regarding ageing management of transport packages in Germany. The concept of the BAM-GGR 023 for ageing management of transport packagings will be described. The fundamentals of BAM-GGR 023 will be shown, including the following key aspects: -the organization of an Ageing Management System (AMS), -the issue of an Ageing Management Plan (AMP), -the ageing evaluation as a part of the AMP, -the Ageing Surveillance Program (ASP) as a part of the AMP, -the Ageing Management Documentation (AMD). T2 - First Consultancy Meeting on Drafting the Safety Guide on Ageing Management and Maintenance of Radioactive Material Transport Packages CY - Vienna, Austria DA - 20.11.2023 KW - Ageing Management KW - Dual Purpose Cask KW - BAM-GGR 023 PY - 2023 AN - OPUS4-58863 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias T1 - KI-unterstützte Dokumentenanalyse für die Sicherheitsbewertung von Transportbehältern für Gefahrstoffe N2 - Transport packages for radioactive material require, dependent on type und quantity of the radioactive material, a regulatory approval. 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 physical specifications, control measures, and testing assessments. Additionally, it encompasses supporting documents such as specifications, plans 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, standards, 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 constraints, making every safety report distinct, despite following the same regulatory framework. This project aims to enhance data analysis and processing through AI-based approaches [4]. Automated methods for analysing and interlinking documentation will improve efficiency, accuracy, and consistency while reducing human error in safety assessments. A key challenge is that pre-trained Large Language Models (LLMs) lack domain-specific data on packaging safety, potentially leading to inaccurate results. To mitigate this, the project applies Retrieval-Augmented Generation (RAG) in conjunction with LLMs. This approach integrates the strengths of pre-trained models with expert knowledge from databases and document repositories, ensuring accurate, well-founded, and transparent assessments. Beyond technical challenges, human factors must be considered early. New technologies often trigger resistance, if not introduced properly. Furthermore, long-term AI-reliance may lead to loss of expertise needed to solve complex problems. User-centred approach ensures effective implementation and lasting viability. This study evaluates the feasibility of using LLMs [2] and RAG [1, 3] for regulatory compliance in radioactive material transport. By analysing current documentation workflows, we assess how AI-driven tools can interpret complex safety reports and identify critical dependencies. Furthermore, we highlight the necessity of robust data governance, confidentiality measures, and AI reliability in this highly regulated domain. T2 - KONTEC 2025 CY - Dresden, Germany DA - 17.09.2025 KW - AI-driven KW - QI-Digital KW - Retrieval-Augmented Generation KW - Large Language Model PY - 2025 AN - OPUS4-64153 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank T1 - Package safety evaluation in a rapidly changing world N2 - The presentation addressed the evolving challenges and developments in the safety evaluation of transport packages for radioactive materials, especially in light of changing technologies, regulations, and environmental conditions. A key focus was the current situation in Germany: following the final shutdown of commercial nuclear power plants in 2023, efforts are now concentrated on decommissioning, interim storage in dual-purpose casks (DPCs), and the ongoing site selection process for a repository for high-level waste. The expected duration of interim storage exceeds 100 years, demanding robust and sustainable safety strategies. One major topic was ageing management, which goes beyond technical measures to ensure transportability over long periods. It also includes preserving knowledge and expertise for future generations. The regulatory framework includes international standards such as IAEA SSR-6 and SSG-26, as well as national guidance like BAM-GGR 023. It was emphasized the growing role of Artificial Intelligence (AI) in safety evaluations. AI can enhance efficiency through automated document analysis and digital data structuring. However, final safety decisions remain the responsibility of human experts, especially given the complexity of documentation and the shortage of skilled personnel. The presentation also addressed changing transport technologies, such as the use of electric and hydrogen-powered vehicles. These vehicles behave differently in accidents, particularly in battery fires, which can reach temperatures above 1000 °C and last significantly longer than conventional fires. This raises the need to reassess existing fire test criteria. Environmental changes were another key point. With global temperatures rising by 0.26 °C per decade, local safety margin evaluations are becoming increasingly important. Existing regulatory assumptions, such as ambient temperatures of 38 °C, may no longer be sufficient. Finite Element Analysis (FEA) is increasing. AI can support model generation, but there is concern about potential skill fading among engineers. Physical testing, such as BAM’s drop towers (up to 200 tons), remains essential for public package safety acceptance. Key takeaways from the talk include: Ageing Management is also about preserving skills and knowledge. Changing technologies and environmental conditions impact package safety. AI can improve efficiency but must be used carefully to avoid skill loss. Physical testing continues to play a vital role in gaining public trust. T2 - PATRAM 2025 CY - San Antonio, Texas, USA DA - 27.07.2025 KW - Artificial Intelligence KW - Package KW - Ageing Management KW - Electric Vehicles KW - Testing PY - 2025 AN - OPUS4-63879 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Niederleithinger, Ernst T1 - Nuclear concrete, and how to live with it more easy using NDE N2 - This keynote presentation compiles the specialities of civil engineering compared to other disciplines, of NDT in civil engineering compared to other filds of NDT and the specific challenges of applications in the nuclear energy and disposal sector. T2 - NucCon 2023 CY - Espoo, Finland DA - 25.01.2023 KW - NDT KW - Concrete KW - Nuclear PY - 2023 AN - OPUS4-56912 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Jaunich, Matthias T1 - Tests of metallic seals at Bam 3.4 performed over more than 15 years N2 - The investigation of the long-term performance of sealing systems employed in containers for radioactive waste and spent nuclear fuel is one research focus area for division 3.4 “Safety of Storage Containers” at the Bundesanstalt für Materialforschung und -prüfung (BAM) in Germany. The time dependant behaviour of metallic seals, which are employed in interim storage casks for used fuel and high active waste, is of high importance for ensuring safe enclosure. Therefore, investigations on these systems were started at BAM to get a general understanding of the relevant processes. Our investigations comprise investigations on different parameters which influence the seal performance and the main part is focussed on the time and temperature dependent behaviour. In this contribution an overview of the performed tests and their respective results will be given. T2 - 5th sealing workshop by Maestral CY - Avignon, France DA - 05.11.2024 KW - Metal seal KW - Aging KW - Interim storage PY - 2024 AN - OPUS4-62048 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Griesche, Axel T1 - In situ bragg edge imaging with neutrons for crystallographic phase and temperature field mapping during tig welding N2 - In Neutron-Bragg-Edge Imaging (NBEI) experiments, we studied the phase transition during butt-welding of martensitic Low Temperature Transformation (LTT) Steel [1]. Tungsten inert gas (TIG) welding was used with a moveable torch allowing for automated weldments. The austenitization in the heat affected zone (HAZ) underneath the welding head could be clearly visualized at λ = 0.39 nm, a wavelength smaller than the Bragg edge wavelengths of both austenite and martensite. Also, the re-transformation upon cooling from austenite into martensitic phase was detected. However, we observed an unexpected additional change in transmission at λ = 0.44 nm that is a wavelength larger than the wavelength of the Bragg edges of both the martensitic and austenitic phases. We attribute this change to the Deybe-Waller-Factor that describes the temperature dependence of coherent scattering at a crystal lattice [2]. The observed two-dimensional attenuation map corresponds well with a temperature distribution modelling by software macros in ANSYS [3]. Here, the absolute temperature values could be achieved by calibrating the modelled attenuation with help of a thermocouple placed at the steel sample plate. This allows in return for a direct two-dimensional temperature reading based on the Debye-Waller-relation between neutron attenuation and sample temperature. T2 - MSE 2024 CY - Darmstadt, Germany DA - 24.09.2024 KW - In situ neutron Bragg edge imaging KW - Temperature field mapping KW - Crystallographic phase mapping KW - TIG welding PY - 2024 AN - OPUS4-61268 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zaghdoudi, Maha T1 - Analysis of heterogeneous ageing of hnbr o rings N2 - Hydrogenated nitrile butadiene rubber (HNBR) elastomer was thermo-oxidatively aged at different temperatures up to 150°C. Fourier transform infrared spectroscopy (FTIR), compression stress relaxation (CSR) and IRHD microhardness were used to characterise the chemo-mechanical changes of HNBR O-rings during thermo-oxidative ageing. FTIR shows the development of carbonyl, methyl and ester groups but the nitrile content was not affected by ageing. The effect of sample geometry during CSR was investigated. CSR data were converted through integrated kinetic laws. The conversion has proven its sensibility to detect heterogeneous ageing. This was confirmed by the IRHD measurements across the section of O-rings. Oxidation profiles were determined by applying the model of Wise et al. to the IRHD experimental results. T2 - The 2023 Postgraduate Seminar - Advanced Structured Materials CY - Barcelona, Spain DA - 20.02.2023 KW - HNBR KW - Heterogeneous ageing KW - IRHD KW - FTIR KW - CSR PY - 2023 AN - OPUS4-57057 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -