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A reliable stress analysis of a cask for radioactive materials under dynamic load conditions requires a qualified numerical model. For this purpose, the cask is typically discretized using a mesh of finite elements. Certain parts of the mesh usually require a refinement to accurately determine the stresses and strains. Other parts of the mesh may not be of interest with respect to stresses and strains. In such parts, a coarse mesh is sufficient. The mesh density can vary considerably within a cask model. Transitions between regions with different mesh densities can be achieved either by gradually changing the element size or by using tie contact conditions. Such mesh transitions can sometimes lead to complications. In general, a finer mesh can transmit higher-frequency signals than a coarser mesh. The propagation of stress waves through the model may be influenced by the transition zone or by any artificially introduced interface. Stress waves arising within the fine mesh can be partially confined by the surrounding coarse mesh. Poor mesh transitions can therefore cause stress waves to be partially reflected or to change their shape. A thin rod is examined to demonstrate the effects. It is modeled with a varying number of elements or varying size of elements respectively. A stress pulse is applied to one end of the rod, while the opposite end remains free. The generated stress wave is observed at various locations along the rod, and its shape and amplitude are analyzed in relation to the mesh density. Inappropriate meshing can lead to incorrect simulation results without the finite element code issuing warnings or error messages. Such problems are often not obvious. As a result, when using finite element meshing, the maximum size of the finite elements required to model the expected stress wave propagation should not be exceeded. In other words, the correct modeling of stress wave propagation determines the minimum number of finite elements required to mesh a cask component. This study illustrates the ASME Guidance Document “Use of Explicit Finite Element Analysis for the Evaluation of Radioactive Material Transport Packages and Storage Casks in Energy-Limited Impact Events”.
A reliable stress analysis of a cask for radioactive materials under dynamic load conditions requires a qualified numerical model. For this purpose, the cask is typically discretized using a mesh of finite elements. Certain parts of the mesh usually require a refinement to accurately determine the stresses and strains. Other parts of the mesh may not be of interest with respect to stresses and strains. In such parts, a coarse mesh is sufficient. The mesh density can vary considerably within a cask model. Transitions between regions with different mesh densities can be achieved either by gradually changing the element size or by using tie contact conditions. Such mesh transitions can sometimes lead to complications. In general, a finer mesh can transmit higher-frequency signals than a coarser mesh. The propagation of stress waves through the model may be influenced by the transition zone or by any artificially introduced interface. Stress waves arising within the fine mesh can be partially confined by the surrounding coarse mesh. Poor mesh transitions can therefore cause stress waves to be partially reflected or to change their shape. A thin rod is examined to demonstrate the effects. It is modeled with a varying number of elements or varying size of elements respectively. A stress pulse is applied to one end of the rod, while the opposite end remains free. The generated stress wave is observed at various locations along the rod, and its shape and amplitude are analyzed in relation to the mesh density. Inappropriate meshing can lead to incorrect simulation results without the finite element code issuing warnings or error messages. Such problems are often not obvious. As a result, when using finite element meshing, the maximum size of the finite elements required to model the expected stress wave propagation should not be exceeded. In other words, the correct modeling of stress wave propagation determines the minimum number of finite elements required to mesh a cask component. This study illustrates the ASME Guidance Document “Use of Explicit Finite Element Analysis for the Evaluation of Radioactive Material Transport Packages and Storage Casks in Energy-Limited Impact Events”.
Accident-Induced Battery Fires: Challenges for the Safe Transport of Packages with Dangerous Goods
(2026)
The global transition toward alternative propulsion technologies is leading to a rapid increase in battery-electric transport vehicles, including their use in the carriage of dangerous goods. This development introduces new accident scenarios whose thermal characteristics may challenge existing safety assumptions embedded in international transport regulations for radioactive materials. In particular, the International Atomic Energy Agency SSR-6 regulations define standardized mechanical and thermal accident tests that were developed decades ago, based largely on fires involving fossil-fuel-powered vehicles.
Recent research demonstrates that fires involving high-voltage lithium-ion batteries and other types can exhibit high heat release rates, extended fire durations, toxic emissions, and re-ignition phenomena, all of which differ substantially from conventional vehicle fires. However, the interaction between battery-electric transport vehicle fires and packages for dangerous goods has not yet been systematically investigated, representing a significant research gap.
This paper reviews the historical development of the IAEA thermal test requirements, summarizes the current state of knowledge on battery fire behavior, and presents the experimental concept of large-scale fire tests conducted at the German Federal Institute for Materials Research and Testing (BAM). These experiments aim to generate realistic and conservative thermal boundary conditions to support future regulatory assessments of transport with dangerous goods under emerging vehicle technologies.
The safety assessment of packages for the transport of radioactive material is a highly regulated and knowledge-intensive process. Regulatory authorities must evaluate complex safety reports that integrate mechanical, thermal, shielding, criticality, and operational analyses, supported by extensive heterogeneous documentation such as drawings, certificates, test results, and inspection records. Although these documents are increasingly available in digital form, they remain largely unstructured and weakly interconnected, requiring manual cross-checking of dependencies and assumptions.
This paper explores the potential of AI-driven documentation analysis to support regulatory safety assessments in the context of IAEA-regulated transport of radioactive materials. It examines the limitations of conventional digital approaches and introduces a multi-layered architecture based on Retrieval-Augmented Generation (RAG), multimodal document processing, and structured knowledge representations. In particular, the paper argues that standard RAG systems are insufficient to capture the deep interdependencies across safety documentation and proposes the integration of Knowledge Graphs and Graph-RAG techniques to enable traceable, multi-step reasoning.
Beyond technical feasibility, the paper emphasizes the importance of human-centered design, explainability, and trustworthiness in safety-critical and regulated domains. Concepts such as Explainable AI and Human-in-the-Loop operation are discussed as essential prerequisites for regulatory acceptance and long-term resilience. Finally, implementation challenges and future developments are outlined, including machine-readable standards and continuous compliance validation. The study demonstrates that AI-supported documentation analysis can significantly enhance efficiency, transparency, and robustness of safety assessments, provided that technical innovation is carefully aligned with regulatory, organizational, and human factors.
Packages for the transport of high-level radioactive material are designed to withstand severe accident conditions. To obtain regulatory approval, such transport packages must comply with the specification-based requirements defined in the IAEA SSR-6 [1]. Demonstrating compliance could require the performance of specific mechanical and thermal tests, depending on the package type. Typically, IAEA SSR-6 [1] mandates a sequence of cumulative tests consisting of mechanical tests followed by a thermal fire test.
For approval of the fire test, the Bundesanstalt für Materialforschung und -prüfung (BAM, engl. Federal Institute for Materials Research and Testing) employs a reference package that reproduces the outer geometry of the original package to characterize the fire conditions and their effects on the package. This approach serves two purposes: first, it enables precise adjustment of the experimental parameters for the package design under approval; second, it provides input data for thermomechanical simulations (cf. [2]). Using this methodology to characterize the package boundary conditions, temperature evolutions within the fire reference package can be analyzed using finite element analysis. This allows direct comparison between experimental results and numerical simulations for the fire reference package and simultaneously supports preliminary simulations of the package design to be approved.
The thermal test of the SSR-6 [1] includes a fully engulfing 800 °C pool fire with a duration of 30 minutes, or an equally severe fire scenario, such as a propane gas fire. The fire reference test is conducted prior to the regulatory fire test of the package design under approval. In the case described here, the fire reference package is a closed cylindrical shell made of stainless steel, with a wall thickness of 10 mm, a length of 4,860 mm, and a diameter of 2,024 mm. The package was instrumented with thermocouples and filled with heat-resistant insulating material. On the lid side of the cylindrical body, a similarly designed metal sheet–encapsulated structure with insulation was used to replicate the external dimensions of the original impact limiter. Its diameter is 3,200 mm and its height is 1,680 mm.
Accident-Induced Battery Fires: Challenges for the Safe Transport of Packages with Dangerous Goods
(2026)
The global transition toward alternative propulsion technologies is leading to a rapid increase in battery-electric transport vehicles, including their use in the carriage of dangerous goods. This development introduces new accident scenarios whose thermal characteristics may challenge existing safety assumptions embedded in international transport regulations for radioactive materials. In particular, the International Atomic Energy Agency SSR-6 regulations define standardized mechanical and thermal accident tests that were developed decades ago, based largely on fires involving fossil-fuel-powered vehicles.
Recent research demonstrates that fires involving high-voltage lithium-ion batteries and other types can exhibit high heat release rates, extended fire durations, toxic emissions, and re-ignition phenomena, all of which differ substantially from conventional vehicle fires. However, the interaction between battery-electric transport vehicle fires and packages for dangerous goods has not yet been systematically investigated, representing a significant research gap.
This paper reviews the historical development of the IAEA thermal test requirements, summarizes the current state of knowledge on battery fire behavior, and presents the experimental concept of large-scale fire tests conducted at the German Federal Institute for Materials Research and Testing (BAM). These experiments aim to generate realistic and conservative thermal boundary conditions to support future regulatory assessments of transport with dangerous goods under emerging vehicle technologies.
Packages for the transport of spent nuclear fuel and high-level radioactive waste must demonstrate their integrity under severe accident conditions to comply with the international transport regulations defined in International Atomic Energy Agency SSR-6. A key component of the approval procedure is the thermal fire test, which requires a fully engulfing 800 °C fire over a duration of 30 minutes. At the Federal Institute of Materials Research and Testing (BAM), such tests are currently conducted using propane gas fires. However, in the context of climate policy objectives, resource availability, and rising costs of fossil fuels, alternative and more sustainable energy sources for fire testing are being investigated.
Hydrogen represents a promising candidate due to its carbon-free combustion and alignment with BAM’s hydrogen strategy. Nevertheless, hydrogen flames exhibit fundamentally different physical and thermal characteristics compared to hydrocarbon flames, most notably a significantly lower radiative emissivity caused by the absence of soot formation. This reduced radiative heat transfer poses a challenge for replicating the boundary conditions required by SSR-6. One potential mitigation strategy is the use of hydrogen–methane blends, where methane serves as a carbon source to enhance flame emissivity while maintaining the possibility of a sustainable fuel pathway.
This paper presents an experimental investigation of hydrogen–methane jet flames with respect to their suitability for thermal fire testing of radioactive material transport packages. A modular experimental test rig was developed and installed at the BAM Test Site for Technical Safety, enabling controlled variation of burner geometry, thermal power, and fuel composition. A Design of Experiments approach based on a Central Composite Design was applied to systematically explore the three-dimensional parameter space. Flame geometry, radiative heat flux, and characteristic flame temperatures were evaluated using thermographic imaging, Gardon gauges, and thermocouples.
The results demonstrate that increasing the methane fraction significantly enhances flame radiation and geometry, while pure hydrogen flames exhibit higher average temperatures but substantially lower radiative heat flux. Quadratic response surface models reveal clear dependencies of flame characteristics on power, nozzle cross section, and methane ratio. Overall, the study confirms that hydrogen–methane blends are a viable option for tailoring flame properties toward the requirements of regulatory fire testing and provides a foundation for the design of future fully engulfing hydrogen-based fire test setups.
The global transition toward alternative propulsion technologies is leading to a rapid increase in battery-electric transport vehicles, including their use in the carriage of dangerous goods. This development introduces new accident scenarios whose thermal characteristics may challenge existing safety assumptions embedded in international transport regulations for radioactive materials. In particular, the International Atomic Energy Agency SSR-6 regulations define standardized mechanical and thermal accident tests that were developed decades ago, based largely on fires involving fossil-fuel-powered vehicles.
Recent research demonstrates that fires involving high-voltage lithium-ion batteries and other types can exhibit high heat release rates, extended fire durations, toxic emissions, and re-ignition phenomena, all of which differ substantially from conventional vehicle fires. However, the interaction between battery-electric transport vehicle fires and packages for dangerous goods has not yet been systematically investigated, representing a significant research gap.
This paper reviews the historical development of the IAEA thermal test requirements, summarizes the current state of knowledge on battery fire behavior, and presents the experimental concept of large-scale fire tests conducted at the German Federal Institute for Materials Research and Testing (BAM). These experiments aim to generate realistic and conservative thermal boundary conditions to support future regulatory assessments of transport with dangerous goods under emerging vehicle technologies.
Packages for the transport of high-level radioactive waste are designed to withstand severe accident conditions. Regulations from the International Atomic Energy Agency (IAEA) are internationally established and define the specific requirements for packages used in the transport of radioactive material. To ensure compliance, a transport package must withstand a sequence of mechanical tests followed by a thermal test, as prescribed in the IAEA regulations. To withstand the mechanical test series, these heavyweight packages are equipped with impact limiters, also referred to as shock absorbers, which are commonly constructed from porous materials such as densely packed wood reinforced with steel sheet structures.
These components absorb the kinetic energy during the regulatory 9m drop test where it impacts on an unyielding target. These impact limiters 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 pre-damaged impact limiters, endure a thermal test defined as a 30-min, fully engulfing 800 °C fire and a following time under ambient conditions where any combustion of materials of the specimen shall be permitted to proceed naturally. A large wood filled impact limiter can continue to release thermal energy during an ongoing combustion process for days, thus defining temperatures relevant for the safety of the package. The actual heat flux from a potentially burning impact limiter to the package is important for the safety evaluation of transport packages.
3 different wood combustion capsules representing an impact limiter and encapsulating different volumes of spruce wood were designed. A test stand was set-up to maintain stable and adjustable boundary conditions where the different wood combustion capsules were ignited, and the wood combusted naturally in the following. The heat flux was investigated and the combustion behaviour of porous materials encapsulated in pre-damaged cylindrical metal enclosures under various conditions was examined. 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.
The transport of dangerous goods, like radioactive material requires, a safety evaluation to fulfill the regulatory requirements. The package design safety assessment shall be conducted in compliance with the international regulations and documented in a comprehensive package design safety report. This 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 analyzing 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.