TY - CONF A1 - Rolle, Annette A1 - Wille, Frank ED - Czarwinski, R. T1 - Radioaktive Stoffe in besonderer Form-wichtige Aspekte im Zulassungsverfahren N2 - Für die Beförderung von umschlossenen radioaktiven Stoffen (Strahler) können Transporterleichterungen gelten, wenn das Strahlerdesign nachweislich unfallsicher ausgelegt ist und eine Zulassung als radioaktiver Stoff in besonderer Form vorliegt. Die in Deutschland zuständige Behörde für die Prüfung und Zulassung radioaktiver Stoffe in besonderer Form ist die Bundesanstalt für Materialforschung und –prüfung (BAM). Eine oft langfristige Nutzung der Strahler kann eine alterungsbedingte Schwächung der Umschließung des radioaktiven Stoffes zur Folge haben. Jeder Strahler einer zugelassenen Bauart muss jedoch im Beförderungsfall zu jeder Zeit, auch nach längerer Nutzung, den vorgeschriebenen Prüfanforderungen genügen. Die Alterungsbewertung auf der Grundlage einer vom Antragsteller zu spezifizierenden Nutzungsdauer des radioaktiven Stoffes in besonderer Form ist seit langer Zeit Bestandteil des Zulassungsverfahrens in Deutschland. Ein von Deutschland eingebrachter Vorschlag im Rahmen der anstehenden Revision der IAEA Empfehlungen für die sichere Beförderung von radioaktiven Stoffen (SSR-6) soll die Lesbarkeit des Regelwerkes bezüglich der Alterungsbewertung verbessern, Klarheit über die damit verbundenen Anforderungen erzeugen und damit zu einer Harmonisierung der Zulassungsverfahren auf internationaler Ebene beitragen. In diesem Beitrag sollen wichtige Einflussfaktoren auf das Alterungsverhalten von radioaktiven Stoffen in besonderer Form aufgezeigt und die Notwendigkeit für die Spezifikation einer Nutzungsdauer als Grundlage für die Alterungsbewertung begründet werden. Der deutsche Vorschlag für die Revision des IAEA Regelwerks zum sicheren Transport radioaktiver Stoffe (SSR-6) wird vorgestellt und erläutert. T2 - Jahrestagung des FS 2022 CY - Konstanz, Germany DA - 26.09.2022 KW - Strahlenschutz KW - Radioaktive Stoffe KW - Beförderung KW - Zulassung PY - 2022 SN - 1013-4506 SP - 15 EP - 20 PB - Fachverband für Strahlenschutz e.V. CY - Berlin AN - OPUS4-56134 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rolle, Annette T1 - Radioaktive Stoffe in besonderer Form - wichtige Aspekte im Zulassungsverfahren N2 - Für die Beförderung von umschlossenen radioaktiven Stoffen (Strahler) können Transporterleichterungen gelten, wenn das Strahlerdesign nachweislich unfallsicher ausgelegt ist und eine Zulassung als radioaktiver Stoff in besonderer Form vorliegt. Die in Deutschland zuständige Behörde für die Prüfung und Zulassung radioaktiver Stoffe in besonderer Form ist die Bundesanstalt für Materialforschung und –prüfung (BAM). Eine oft langfristige Nutzung der Strahler kann eine alterungsbedingte Schwächung der Umschließung des radioaktiven Stoffes zur Folge haben. Jeder Strahler einer zugelassenen Bauart muss jedoch im Beförderungsfall zu jeder Zeit, auch nach längerer Nutzung, den vorgeschriebenen Prüfanforderungen genügen. Die Alterungsbewertung auf der Grundlage einer vom Antragsteller zu spezifizierenden Nutzungsdauer des radioaktiven Stoffes in besonderer Form ist seit langer Zeit Bestandteil des Zulassungsverfahrens in Deutschland. Ein von Deutschland eingebrachter Vorschlag im Rahmen der anstehenden Revision der IAEA Empfehlungen für die sichere Beförderung von radioaktiven Stoffen (SSR-6) soll die Lesbarkeit des Regelwerkes bezüglich der Alterungsbewertung verbessern, Klarheit über die damit verbundenen Anforderungen erzeugen und damit zu einer Harmonisierung der Zulassungsverfahren auf internationaler Ebene beitragen. In diesem Beitrag sollen wichtige Einflussfaktoren auf das Alterungsverhalten von radioaktiven Stoffen in besonderer Form aufgezeigt und die Notwendigkeit für die Spezifikation einer Nutzungsdauer als Grundlage für die Alterungsbewertung begründet werden. Der deutsche Vorschlag für die Revision des IAEA Regelwerks zum sicheren Transport radioaktiver Stoffe (SSR-6) wird vorgestellt und erläutert. T2 - Jahrestagung des FS 2022 CY - Konstanz, Germany DA - 26.09.2022 KW - Strahlenschutz KW - Radioaktive Stoffe KW - Beförderung KW - Alterung KW - Zulassung PY - 2022 AN - OPUS4-56137 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rolle, Annette T1 - Safety assessment of aged metal seals N2 - With our experiments we want to simulate a load situation which can result from a cask vertical drop test. The lid can lift a little for a very short moment and that can perhaps result in a little movement of the seal, a little rotation or a little lateral movement, so that the contact section can change. The aim of the project is to learn more about the sealing efficiency after the seal is compressed again. What we know from former component tests with non-aged seals is, that the leakage rate measured after one or more decompression /compression cycles with seal movement becomes significant higher. And this result is considered for specification of design leakage rates for release calculation in safety cases. In the recent years we all have learned more about the significant influence of temperature and time on seal behavior and so the plan was to do similar experiments with aged seals, just to get an idea about seal behavior and achievable leakage rates. What we did in detail is: We compressed Helicoflex-seals of both design types, with Aluminum and Silver outer jackets, in testflanges and aged them in an oven at a temperature of 125°C for 3 months to produce seal properties comparable with properties after several years use at more typical operating temperatures between 90 and 100°C. After this ageing procedure we opened the flanges completely, moved the seal a little to vary the contact area and compressed the flanges again. What we measured during all compression and decompression cycles was the load, the deformation and -as long as possible- the leakage rates. T2 - Workshop IRSN/BAM CY - Cadarache, France DA - 12.10.2022 KW - Transport KW - Radioactive KW - Seal behavior KW - Ageing PY - 2022 AN - OPUS4-56141 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Hong, H. A1 - Part, Florian A1 - Nowack, B. T1 - Prospective dynamic and probabilistic material flow analysis of graphene-based materials in Europe from 2004 to 2030 N2 - As industrial demand for graphene-based materials (GBMs) grows, more attention falls on potential environmental risks. The present article describes a first assessment of the environmental releases of GBMs using dynamic probabilistic material flow analysis. The model considered all current or expected uses of GBMs from 2004 to 2030, during which time there have already been significant changes in how the graphene mass produced is distributed to different product categories. Although the volume of GBM production is expected to grow exponentially in the coming years, outflow from the consumption of products containing GBMs shows only a slightly positive trend due to their long lifetimes and the large in-use stock of some applications (e.g., GBM composites used in wind turbine blades). From consumption and end-of-life phase GBM mass flows in 2030, estimates suggest that more than 50% will be incinerated and oxidized in waste plants, 16% will be landfilled, 12% will be exported out of Europe, and 1.4% of the annual production will flow to the environment. Predicted release concentrations for 2030 are 1.4 ng/L in surface water and 20 μg/kg in sludge-treated soil. This study’s results could be used for prospective environmental risk assessments and as input for environmental fate models. KW - Graphene KW - Graphene-based material (GBM) KW - Material flow analysis KW - Exposure modeling PY - 2022 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-568843 DO - https://doi.org/10.1021/acs.est.2c04002 SN - 0013-936X SN - 1520-5851 VL - 56 SP - 13798 EP - 13809 PB - American Chemical Society CY - Columbus, Ohio AN - OPUS4-56884 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - RPRT A1 - Zencker, Uwe A1 - Simbruner, Kai A1 - Völzke, Holger T1 - Entwicklung eines bruchmechanischen Berechnungsansatzes zur Beschreibung des Festigkeitsverhaltens von Brennstabhüllrohren bei längerfristiger Zwischenlagerung (BRUZL) N2 - Es werden Methoden zur sicherheitstechnischen Bewertung des mechanischen Verhaltens von Brennstabhüllrohren entwickelt, um sprödes Versagen in Belastungsszenarien nach längerfristiger trockener Zwischenlagerung zu verhindern. Unbestrahlte Brennstabhüllrohrsegmente aus der Zirkoniumlegierung ZIRLO® wurden hydriert und thermomechanischen Behandlungen unterzogen, um Hüllrohrmaterial durch Ausscheidung radialer Hydride zu verspröden. Die Proben mit radialen Hydriden wurden im Ring Compression Test (RCT) bei Raumtemperatur untersucht. Bereits bei kleinen Probenverformungen wurden abrupte Kraftabfälle mit instabiler Rissausbreitung durch das Netzwerk radialer Hydride beobachtet. Die Risslängen erreichten in einigen Fällen bis zu 90 % der Wanddicke. Der mikromechanische Versagensmechanismus ist Quasi-Spaltbruch in den Hydriden und Porenbildung, -wachstum und -vereinigung in der Zirkoniummatrix an den duktilen Brücken zwischen benachbarten Hydriden. Es wurde ein Finite-Elemente-Modell des Ring Compression Tests erstellt, um das Versagensverhalten zirkoniumbasierter Legierungen mit radialen Hydriden im RCT zu analysieren. Die Fließkurve für das elastisch-plastische Materialmodell des Matrixmaterials wurde durch eine inverse Finite-Elemente-Analyse ermittelt. Kohäsivzonenmodelle wurden benutzt, um die plötzlichen Kraftabfälle zu reproduzieren. Es wurde ein mikromechanisches Modell mit statistisch generierten Matrix-Hydrid-Verteilungen entwickelt, das zwischen sprödem Versagen entlang der Hydride und duktilem Versagen der Zirkoniummatrix in der Kohäsivzone unterscheidet. Für das jeweilige Materialverhalten wird ein lokales zweiparametriges Versagenskriterium auf Grundlage der Kohäsionsfestigkeit und der Separationsenergie bei einer festgelegten Form des Kohäsivgesetzes vorgeschlagen. Geeignete Kohäsivparameter lassen sich mit einer inversen Finite-Elemente-Analyse des Versagensverhaltens von hydrierten Proben im Ring Compression Test bestimmen. In den Simulationen lag der Schwerpunkt auf dem ersten Kraftabfall. Die Berechnungsergebnisse stimmen gut mit den RCT-Ergebnissen überein. Es konnte gezeigt werden, dass die Rissinitiierung und -ausbreitung stark von der speziellen Anordnung der radialen Hydride und Matrixbrücken in der Bruchzone abhängt. Die numerische Modellbildung wurde an Versuchen mit bestrahlten Proben aus der Zirkoniumlegierung M5® validiert. KW - Zwischenlagerung KW - Brennstabhüllrohr KW - Versagensmechanismus KW - Kohäsivzonenmodell KW - Ring Compression Test PY - 2022 SP - 1 EP - 106 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin AN - OPUS4-56853 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Werner, Jan T1 - Anforderungen an Ladeabteile für EX/III-Fahrzeuge N2 - Durchführung experimenteller Untersuchungen bezüglich der technischen und betrieblichen Anforderungen an Ladeabteile von EX/III-Fahrzeugen (9.3.4.2 ADR) Die derzeitigen Explosivstoffschutz-Anforderungen des Regelwerks ADR basieren auf einem überholten Stand der Technik. Die Unklarheiten führen bei den Ausrüstern und Betreibern der Gefahrgutfahrzeuge zu Unsicherheiten mit existenziellen Risiken und Kosten. 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. Hierzu werden auf Grundlage der heutigen Vorschriften bestehende konstruktive Lösungen untersucht und deren Wirksamkeit gegenüber einer typischen Wärmebelastung von außen festgestellt. Erforderlich dafür ist zunächst die Charakterisierung der Wärmeeinträge durch Kalorimeterversuche mit typischen Unfallbelastungen. Daraus abzuleiten sind 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. T2 - IAA Transportation CY - Hannover, Germany DA - 19.09.2024 KW - EX/III KW - Gefahrgut KW - ADR KW - Transport KW - Brand PY - 2024 AN - OPUS4-61632 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Werner, Jan T1 - Anforderungen an Ladeabteile für EX/III-Fahrzeuge N2 - Die derzeitigen Explosivstoffschutz-Anforderungen des Regelwerks ADR basieren auf einem überholten Stand der Technik. Die Unklarheiten führen bei den Ausrüstern und Betreibern der Gefahrgutfahrzeuge zu Unsicherheiten mit existenziellen Risiken und Kosten. 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. Hierzu werden auf Grundlage der heutigen Vorschriften bestehende konstruktive Lösungen untersucht und deren Wirksamkeit gegenüber einer typischen Wärmebelastung von außen festgestellt. Erforderlich dafür ist zunächst die Charakterisierung der Wärmeeinträge durch Kalorimeterversuche mit typischen Unfallbelastungen. Daraus abzuleiten sind 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. T2 - Gefahrgutkongress IHK Rostock CY - Rostock, Germany DA - 14.11.2024 KW - EX/III KW - Gefahrgut KW - ADR KW - Transport KW - Brand PY - 2024 AN - OPUS4-61639 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Werner, Jan T1 - Requirements for loading compartments for EX/III vehicles N2 - The current explosives protection requirements of the ADR regulations are based on an outdated state of the art. The lack of clarity leads to uncertainties with existential risks and costs for equipment suppliers and operators of dangerous goods vehicles. In order to promote a revision of the supplementary regulations for EX/III vehicles for the transportation of explosive substances and articles of Class 1 in packages, it is therefore necessary to examine the hazards to which explosive substances and articles are exposed during transportation. To this end, existing design solutions will be examined on the basis of current regulations and their effectiveness against a typical external heat load will be determined. The first step is to characterize the heat input by means of calorimeter tests with typical accident loads. Idealized load scenarios are then to be derived from this, which are to be regarded as a prerequisite for standardization work. In the final step, a draft text for the renewal of the existing ADR regulations is to be drawn up and then coordinated internationally. T2 - UNECE Working Party on Transport of Dangerous Goods By Road WP.15 CY - Geneva, Switzerland DA - 05.11.2024 KW - EX/III KW - Dangerous Goods KW - ADR KW - Transport KW - Fire PY - 2024 AN - OPUS4-61640 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Lengas, Nikolaos A1 - Müller, Karsten A1 - Schlick‐Hasper, Eva A1 - Neitsch, Marcel A1 - Johann, Sergej A1 - Zehn, Manfred W. T1 - Drop Test Simulation of Packaging for Dangerous Goods: An Investigation of Appropriate Drop Height Adjustment in Case of Deviating Packaging Gross Mass N2 - In the approval process of dangerous goods packagings, drop tests onto a flat, essentially unyielding surface are used to assess resistance against mechanical damage. International adopted regulations like ADR and RID define filling good dependent drop heights and filling degrees whilst the user needs to define the maximum gross mass to be tested and approved. Maximum packaging gross mass is defined conservatively and not reached in practice. To meet the defined gross mass in testing, using additives is permitted. However, in some cases, additives are not desirable due to packaging design or filling substance properties. This leads to deviations from the initial gross mass definition. Hence, a certain drop height adjustment is necessary to achieve the required impact loading. Laboratories frequently adjust drop height assuming a perfectly elastic collision that is inaccurate. Appropriate adjustment is not trivial due to energy conversion processes, for example, plastic deformation. In this work, a test stand KW - Corrugated fibreboard box KW - Dangerous goods packagings KW - Drop test KW - Impact target KW - Mechanical response KW - Structural dynamics PY - 2024 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-614138 DO - https://doi.org/10.1002/pts.2858 SP - 1 EP - 18 PB - Wiley AN - OPUS4-61413 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank T1 - Tightness Verification Procedures of welded Lids for Encapsulations for Damaged Spent Nuclear Fuel in the Design Approval Process of Dual-Purpose Cask N2 - Damaged spent nuclear fuel (DSNF) can be loaded in Germany in dual-purpose casks (DPC) for transport and interim storage. Therefore, special encapsulations are needed to guarantee a safe handling and a reliable tight closure. These encapsulations must be durable and leak-tight for a possible long interim storage term and the transport thereafter. Because components inside the package containment like these special encapsulations are not accessible within periodical inspections of the DPC. Due to the general design of DPCs for standard fuel assemblies, specific requirements needed to be considered for the design of the special encapsulations for DSNF to ensure the loading in existing package designs. Especially the content of the encapsulations with damaged spent nuclear fuel must be avoided to enter in the inner space of the DPC, due to the possible higher amount of corrosive and radioactive material as well as greater quantities of water, which can be trapped in defect fuel rods. The main difference of the e T2 - ASME PVP 2024 CY - Bellevue, WA, USA DA - 28.07.2024 KW - Tightness verification KW - Weld seams KW - Drop tests KW - Encapsulations for damaged spent nuclear fuel KW - Helium leak tests PY - 2024 AN - OPUS4-61353 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 - Enhancement of the BAM Fire Test Stand for Testing a Large Transport Package for Radioactive Materials N2 - Packages for the transport of spent nuclear fuel are designed to endure severe accidents. To obtain approval, these transport packages must adhere to the specification-based criteria of the international transport regulations SSR-6 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, SSR-6 prescribes a mechanical test followed by a thermal fire test as part of different testing scenarios. To approve the latter test of the sequence, BAM performs calorimeter tests in advance with so-called fire reference packages for characterizing the actual fire and its impact on the package to be tested. Packages are designed with different geometry sizes depending on their purpose. For previous tests, the implemented test setups in the fire test stand were sufficiently dimensioned and could cover all requirements in this respect. However, to cover additional testing needs in the future, BAM is expanding the test setup for the purpose of testing significantly larger packages. In previous test setups one ring burner for propane surrounding the test specimen was sufficient. The limiting size in this configuration was the design height of the transport package to be tested. According to the thermal test of the IAEA-Regulations [1], a 30-minute fully engulfing 800°C pool fire or an equally severe fire, e.g., propane gas fire, must be applied to the transport package. Possible adjustments such as nozzle cross-section and propane mass flow can be adjusted to a certain extent. Further modifications, to cover significantly higher and larger packages all-around with a fully engulfing fire, must be accomplished with an additional, second burner ring. Both burner rings had the same dimensions and were mounted on top of each other at different heights to create a significantly larger volume of fire that completely engulfs the package including its impact limiter. To meet the IAEA regulatory boundary conditions, the enhanced fire test stand with the second burner ring is tested with a large fire reference package and will then be used for real-size transport packages after all parameters are successfully met. This fire reference package represents the external geometry of a generic transport cask for radioactive material and is equipped with numerous temperature sensors to record temperature curves at the interior wall surfaces. T2 - RAMTrans 2024 CY - London, United Kingdom DA - 14.05.2024 KW - Fire testing KW - Full-scale KW - Transport package PY - 2024 SP - 1 EP - 7 AN - OPUS4-60253 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Quercetti, Thomas T1 - Enhancement of the bam fire test stand for testing a large transport package for radioactive materials N2 - Packages for the transport of spent nuclear fuel are designed to endure severe accidents. To obtain approval, these transport packages must adhere to the specification-based criteria of the international transport regulations SSR-6 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, SSR-6 prescribes a mechanical test followed by a thermal fire test as part of different testing scenarios. To approve the latter test of the sequence, BAM performs calorimeter tests in advance with so-called fire reference packages for characterizing the actual fire and its impact on the package to be tested. Packages are designed with different geometry sizes depending on their purpose. For previous tests, the implemented test setups in the fire test stand were sufficiently dimensioned and could cover all requirements in this respect. However, to cover additional testing needs in the future, BAM is expanding the test setup for the purpose of testing significantly larger packages. In previous test setups one ring burner for propane surrounding the test specimen was sufficient. The limiting size in this configuration was the design height of the transport package to be tested. According to the thermal test of the IAEA-Regulations [1], a 30-minute fully engulfing 800°C pool fire or an equally severe fire, e.g., propane gas fire, must be applied to the transport package. Possible adjustments such as nozzle cross-section and propane mass flow can be adjusted to a certain extent. Further modifications, to cover significantly higher and larger packages all-around with a fully engulfing fire, must be accomplished with an additional, second burner ring. Both burner rings had the same dimensions and were mounted on top of each other at different heights to create a significantly larger volume of fire that completely engulfs the package including its impact limiter. To meet the IAEA regulatory boundary conditions, the enhanced fire test stand with the second burner ring is tested with a large fire reference package and will then be used for real-size transport packages after all parameters are successfully met. This fire reference package represents the external geometry of a generic transport cask for radioactive material and is equipped with numerous temperature sensors to record temperature curves at the interior wall surfaces. T2 - RAMTrans 2024 CY - London, United Kingdom DA - 14.05.2024 KW - Fire testing KW - Full-scale KW - Transport package PY - 2024 AN - OPUS4-60255 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Weber, Mike T1 - Consequences of an Imperfectly Mounted Reinforcement Cage in a Cylindrical Concrete Container During Mechanical Specimen Tests N2 - In 2007 the license for the German Konrad repository for low and intermediate level radioactive waste was finally confirmed. Since then, the site is improved, prepared and equipped for the currently planned start of waste package emplacement in 2029. Bundesanstalt fuer Materialforschung und -pruefung is regularly contracted by the Bundesgesellschaft für Endlagerung as the responsible authority for waste product control, waste container design testing, and waste package acceptance. In this context BAM is mainly responsible for design testing of various container types including the evaluation of quality assurance measures for container manufacturing. In addition to general requirements concerning container design, the casks have to withstand specific mechanical load scenarios. Drop tests from different heights under consideration of the most damaging drop orientation and a stacking test are two examples for necessary safety demonstrations. If the containers are made from concrete the reinforcement has the function to absorb tensile forces the concrete is not able to withstand by its own. Because of manufacturing imperfections of cylindrical concrete containers manufactured already decades ago, the reinforcement cages are not always exactly, asymmetrically positioned when they were poured. This inspired BAM to perform various ABAQUS® finite-element (FE) simulations by using the example of a simplified cylindrical container design with generic dimensions. On the basis of the calculated tensile and compressive stress distributions suggestions are derived on how a cylindrical concrete container with an imperfectly placed reinforcement cage has to be oriented for a drop or stacking test to ensure the most damaging test scenario. T2 - RAMTRANS 2024 CY - London, United Kingdom DA - 14.05.2024 KW - Finite-element-analysis KW - Container design testing procedure KW - Reinforced concrete containers KW - Drop test KW - Stacking test KW - Imperfectly mounted reinforcement cage PY - 2024 AN - OPUS4-60120 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias A1 - Feldkamp, Martin A1 - Quercetti, Thomas A1 - Musolff, André A1 - Werner, Jan A1 - Wille, Frank 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 en-dure severe accidents. Packages for the transportation of radioactive material must demonstrate that the package can withstand certain prescribed tests from the IAEA Regulations [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 signifi-cantly 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 nozzles 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 corresponding 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 igni-tion of the wood filled impact limiters within the prescribed 30 minutes of the IAEA Regulations [1]. From a series of experiments, two experiments are pre-sented 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 temperature data, other data such as wind speed and wind direction are also recorded to explain subsequent effects in the measurement data in a comprehen-sible manner. T2 - Wood & Fire Safety 2024 CY - Strbske Pleso, Slowakei DA - 13.05.2024 KW - IAEA Regu-lations KW - Fire Test Stand KW - Accident Scenario KW - Fire Qualification PY - 2024 UR - https://link.springer.com/book/9783031591761 SN - 978-3-031-59176-1 SN - 978-3-031-59179-2 SN - 978-3-031-59177-8 DO - https://doi.org/10.1007/978-3-031-59177-8_22 VL - 1 SP - 189 EP - 197 PB - Springer Cham AN - OPUS4-60101 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 en-dure severe accidents. Packages for the transportation of radioactive material must demonstrate that the package can withstand certain prescribed tests from the IAEA Regulations [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 signifi-cantly 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 nozzles 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 corresponding 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 igni-tion of the wood filled impact limiters within the prescribed 30 minutes of the IAEA Regulations [1]. From a series of experiments, two experiments are pre-sented 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 temperature data, other data such as wind speed and wind direction are also recorded to explain subsequent effects in the measurement data in a comprehen-sible manner. T2 - Wood & Fire Safety 2024 CY - Štrbské Pleso, Slovakia DA - 13.05.2024 KW - Fire Test Stand KW - Accident Scenario KW - Fire Qualification KW - IAEA Regu-lations PY - 2024 UR - https://link.springer.com/book/9783031591761 AN - OPUS4-60104 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rolle, Annette A1 - Neumeyer, Tino A1 - Ballheimer, Viktor A1 - Wille, Frank T1 - Investigations of Aged Metal Seals for Transport Package Safety Assessment N2 - Acceptable limits for activity release from transport casks for high-level radioactive material specified in the IAEA regulations must be kept by the integrity of cask body and the cask sealing system. BAM as the German competent authority for mechanical, thermal and containment assessment of packages liable for approval verifies the activity release compliance with the regulatory limits. The specification of conservative package design leakage rates is one of the most important aspects in assessment. Metal seals of the Helicoflex® Type are usually used to ensure the required package tightness for both, storage, and transport of the cask before and after storage. Due to the long-term use the seal behavior is influenced by temperature and time. The mechanical and thermal loadings associated with the routine, normal and accident conditions of transport specified in the regulations can have a significant effect on the leak tightness of the sealing system. Whereas the safety for application of new, non- aged Helicoflex® seals is verified sufficiently, there are still technical data gaps concerning the efficiency of aged Helicoflex® seals. BAM performed experiments to learn more about the sealing efficiency of aged Helicoflex® seals with Aluminum and Silver outer jackets. The seals were compressed in test-flanges and for artificial ageing the complete flange systems were stored in an oven for several month at a high temperature. After this ageing procedure the flanges were opened completely, the seals were moved a little to vary the contact area, and the flanges were compressed again. During the compression and decompression tests after the aging, load-deformation characteristics of the seals, and leakage rates were measured. With these tests a load situation was simulated, which can occur in the regulatory drop test of the cask: Under high impact loads the bolted lid can lift a little for a short moment, allowing a little movement of the seal, so that the contact area can change before compressing again. Details about test conditions and first results will be presented in the poster. T2 - RAMTrans 2024, 12th Internatiopnal Conference on the Transport , Storage and Disposal of Radioactive Materials CY - London, UK DA - 15.05.2024 KW - Seals KW - Ageing KW - Radioaktiv PY - 2024 AN - OPUS4-60112 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 - Combustion Chamber Design for Encapsulated Wood-Component Testing N2 - Heavy-weight packages for the safe transport of radioactive material are equippedwith impact limiters often built ofwood-filled steel sheet structures to fulfil the requirements of the International Atomic Energy Agency (IAEA) regulations. The requirements definemechanical tests followed by a thermal test, including criteria ensuring the package design’s ability to withstand severe accidents and provide a high level of technical safety. Impact limiters are a package component mainly designed for the packages to withstand severe mechanical accident scenarios. In drop tests the impact limiters absorb the kinetic energy during impact of the package. The package must then - with its pre-damaged impact limiters - endure a thermal test defined precisely in the IAEA regulations as a 30-min fully engulfing 800 °C-fire. After the fire, a wood-filled impact limiter may continue to release thermal energy from an ongoing combustion process, defining relevant package temperatures. The energy flow from a possible burning impact limiter to the package is important for the safety evaluation of transport packages. To investigate the combustion behaviour of densely packed layers of spruce wood, encapsulated in pre-damaged cylindrical metal enclosures, a test set-up has been realised. The set-up consists of a combustion chamber to perform these tests under defined boundary conditions. The temperature development of the test specimens will be observed fromoutside with a thermographic imager, with HD-Cameras, and the mass loss will be measured during the entire test. Airflow conditions in the combustion chamber are analysed using Computational Fluid Dynamics (CFD) calculations in OpenFOAM. The planned combustion test setup is described. T2 - Wood & Fire Safety 2024 CY - Štrbské Pleso, Slovakia DA - 12.05.2024 KW - Fire KW - Combustion KW - Smouldering PY - 2024 SN - 978-3-031-59176-1 SN - 978-3-031-59179-2 SN - 978-3-031-59177-8 DO - https://doi.org/10.1007/978-3-031-59177-8 SP - 215 EP - 222 PB - Springer Nature Switzerland AG CY - Gewerbestrasse 11, 6330 Cham, Switzerland AN - OPUS4-60226 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin T1 - Combustion Chamber Design for Encapsulated Wood-Component Testing N2 - eavy-weight packages for the safe transport of radioactive material are equippedwith impact limiters often built ofwood-filled steel sheet structures to fulfil the requirements of the International Atomic Energy Agency (IAEA) regulations. The requirements definemechanical tests followed by a thermal test, including criteria ensuring the package design’s ability to withstand severe accidents and provide a high level of technical safety. Impact limiters are a package component mainly designed for the packages to withstand severe mechanical accident scenarios. In drop tests the impact limiters absorb the kinetic energy during impact of the package. The package must then - with its pre-damaged impact limiters - endure a thermal test defined precisely in the IAEA regulations as a 30-min fully engulfing 800 °C-fire. After the fire, a wood-filled impact limiter may continue to release thermal energy from an ongoing combustion process, defining relevant package temperatures. The energy flow from a possible burning impact limiter to the package is important for the safety evaluation of transport packages. To investigate the combustion behaviour of densely packed layers of spruce wood, encapsulated in pre-damaged cylindrical metal enclosures, a test set-up has been realised. The set-up consists of a combustion chamber to perform these tests under defined boundary conditions. The temperature development of the test specimens will be observed fromoutside with a thermographic imager, with HD-Cameras, and the mass loss will be measured during the entire test. Airflow conditions in the combustion chamber are analysed using Computational Fluid Dynamics (CFD) calculations in OpenFOAM. The planned combustion test setup is described. T2 - Wood & Fire Safety 2024 CY - Štrbské Pleso, Slovakia DA - 12.05.2024 KW - IAEA KW - Combustion Chamber KW - Smouldering KW - Wood PY - 2024 AN - OPUS4-60227 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Völzke, Holger T1 - Brittle Failure Limits of Spent Fuel Claddings Subjected to Long-Term Dry Interim Storage Conditions N2 - The mechanical properties of spent fuel claddings can be adversely affected under the conditions of long-term dry interim storage, so that the failure limits may be reached in case of mechanical loads during handling or transport after storage. Pre-storage drying and the early stage of interim storage can expose the cladding to higher temperatures and higher tensile hoop stresses than those associated with in-reactor operation and pool storage. During slow cooling of a cladding tube under internal pressure, radial hydrides may precipitate in zirconium-based cladding alloys. This can lead to embrittlement of the material and sudden failure of the cladding integrity under mechanical stress. In order to prevent brittle failure, numerical methods are being developed to predict the mechanical behaviour and identify limiting conditions. Experimental investigations, numerical analyses and evaluation methods are discussed. An established experimental method for characterising cladding materials is the Ring Compression Test (RCT). Some test results on irradiated cladding tubes after operation in pressure water reactors are publicly available. However, it is helpful to carry out studies on unirradiated surrogate claddings with similar material properties to reduce the effort associated with irradiated samples in hot cells and to perform material tests with a wider range of parameters. On the basis of such experimental data, load-displacement curves have been numerically analysed for a selection of cladding materials. Radial hydrides can cause a sample to break suddenly due to fracture even at low deformation. Noticeable load drops in the RCT are caused by unstable crack propagation through the radial hydride network. The failure mechanism is quasi-cleavage in the hydrides and micro-void nucleation, growth, and coalescence in the zirconium matrix, with ductile tearing patches connecting adjacent hydrides. The cohesive zone approach was used to simulate the failure process taking into account the radial hydride morphology. The developed method can adequately describe both the deformation and failure behaviour of irradiated as well as unirradiated claddings of zirconium-based alloys with radial hydrides under RCT conditions. Limiting conditions can be expressed in terms of fracture energy and cohesive strength. T2 - IAEA International Conference on the Management of Spent Fuel from Nuclear Power Plants - Meeting the Moment CY - Vienna, Austria DA - 10.06.2024 KW - Ageing Management KW - Cladding Embrittlement KW - Extended Storage KW - Ring Compression Test KW - Spent Nuclear Fuel PY - 2024 SP - 1 EP - 10 AN - OPUS4-60323 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe T1 - Brittle Failure Limits of Spent Fuel Claddings Subjected to Long-Term Dry Interim Storage Conditions N2 - The mechanical properties of spent fuel claddings can be adversely affected under the conditions of long-term dry interim storage, so that the failure limits may be reached in case of mechanical loads during handling or transport after storage. Pre-storage drying and the early stage of interim storage can expose the cladding to higher temperatures and higher tensile hoop stresses than those associated with in-reactor operation and pool storage. During slow cooling of a cladding tube under internal pressure, radial hydrides may precipitate in zirconium-based cladding alloys. This can lead to embrittlement of the material and sudden failure of the cladding integrity under mechanical stress. In order to prevent brittle failure, numerical methods are being developed to predict the mechanical behaviour and identify limiting conditions. Experimental investigations, numerical analyses and evaluation methods are discussed. An established experimental method for characterising cladding materials is the Ring Compression Test (RCT). Some test results on irradiated cladding tubes after operation in pressure water reactors are publicly available. However, it is helpful to carry out studies on unirradiated surrogate claddings with similar material properties to reduce the effort associated with irradiated samples in hot cells and to perform material tests with a wider range of parameters. On the basis of such experimental data, load-displacement curves have been numerically analysed for a selection of cladding materials. Radial hydrides can cause a sample to break suddenly due to fracture even at low deformation. Noticeable load drops in the RCT are caused by unstable crack propagation through the radial hydride network. The failure mechanism is quasi-cleavage in the hydrides and micro-void nucleation, growth, and coalescence in the zirconium matrix, with ductile tearing patches connecting adjacent hydrides. The cohesive zone approach was used to simulate the failure process taking into account the radial hydride morphology. The developed method can adequately describe both the deformation and failure behaviour of irradiated as well as unirradiated claddings of zirconium-based alloys with radial hydrides under RCT conditions. Limiting conditions can be expressed in terms of fracture energy and cohesive strength. T2 - IAEA International Conference on the Management of Spent Fuel from Nuclear Power Plants - Meeting the Moment CY - Vienna, Austria DA - 10.06.2024 KW - Ageing Management KW - Cladding Embrittlement KW - Extended Storage KW - Ring Compression Test KW - Spent Nuclear Fuel PY - 2024 AN - OPUS4-60324 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 - Introduction and Necessity of the Investigation 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 concept paper will briefly present the reasons for detailed investigations as bases for a coordinated research project under the roof of the IAEA. T2 - Technical Exchange IRSN – BAM Transport & Storage of Packages for Radioactive Material CY - Berlin, Germany DA - 04.06.2024 KW - Fire KW - Battery KW - Hydrogen KW - IAEA Regulations PY - 2024 AN - OPUS4-60338 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Naster, Maximilian T1 - Hydrogen Fire Testing N2 - In this presentation we present a new 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 will be capable of combusting hydrogen for a wide range of different burner geometries, mass flows and if necessary hydrogen blends. 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 calculations must be carried out in order to develop a viable concept for hydrogen fires. In the first step of the feasibility study, the temperature, structure, and radiation of various hydrogen flames are surveyed. In future works, the results will make it possible to design burner frames that are suitable for fire reference tests in order to make comparisons with pool and propane fires used in assessment procedures today. In parallel comparative numerical simulations are conducted to model the thermal behaviour of hydrogen flames using the software package Ansys®. On the one hand, the numerical simulations support the experiments by providing an overview of numerous parameters and the measuring range; on the other hand, they will help with the design of the burner frame in future work. This paper gives an overview in the design and capabilities of the test rig. Furthermore, the results of the parameter studies show that burner geometry and mass flow provide a significant design margin for the thermal shape of the hydrogen flames. In addition, the results of the initial numerical calculations will be used to determine the necessary sensors, the positions, and their operating range. Only the optimal interaction allows a controlled system that permits user-defined hydrogen fires. T2 - Technical Exchange IRSN – BAM Transport & Storage of Packages for Radioactive Material CY - Berlin, Germany DA - 04.06.2024 KW - Hydrogen PY - 2024 AN - OPUS4-60341 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe T1 - Fracture Mechanics Analysis of Spent Fuel Claddings during Long-Term Dry Interim Storage N2 - The European Joint Programme on Radioactive Waste Management (EURAD) is working on Spent Fuel Characterization (SFC) in its work package (WP) 8. Inspired by the EURAD activities, the International Atomic Energy Agency (IAEA) established an international Coordinated Research Project (CRP) on SFC. The EURAD WP SFC participants are collaborating as a team on the IAEA CRP on SFC. The EURAD WP SFC project consists of four tasks. Task 3 investigates the behaviour of nuclear fuel and cladding after discharge. The aim of these activities is to understand and describe the evolution of the cladding-pellet system and its ageing under conditions of extended interim storage, transportation and emplacement in a final disposal system. At the Third Research Coordination Meeting on Spent Fuel Characterization, BAM as contributor to Task 3 reported on the activities and status of its research work. T2 - IAEA 3rd Research Coordination Meeting of the Coordinated Research Project on Spent Fuel Characterization CY - Cockermouth, UK DA - 01.07.2024 KW - Nuclear fuel KW - Cladding KW - Discharge PY - 2024 AN - OPUS4-60668 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Gaddampally, Mohan Reddy A1 - Völzke, Holger T1 - Failure Analysis on Irradiated Claddings Subjected to Long-Term Dry Interim Storage N2 - Long-term dry interim storage may adversely affect the mechanical properties of spent fuel rods, possibly resulting in a reduced resilience during handling or transport after storage. The cladding is the first barrier for the spent fuel pellets. An established method for characterising the cladding material is the ring compression test (RCT), in which a small, cylindrical sample of the cladding tube is subjected to a compressive load. Radial hydrides may precipitate in zirconium-based alloys (Zircaloy) under pre-storage drying and during slow cooling, which result in embrittlement of the cladding material and eventually a possible sudden failure of cladding integrity under additional mechanical loads. The focus of the presented research is on the development of appropriate nu-merical methods for predicting the mechanical behaviour and identification of limiting conditions to prevent brittle fracture of Zircaloy claddings. A modelling approach based on cohesive zones is ex-plained which is able to reproduce the propagation of cracks initiated at radial hydrides in the zir-conium matrix. The developed methods are applied to defueled samples of cladding alloy ZIRLO®, which were subjected to a thermo-mechanical treatment to reorient existing circumferential hy-drides to radial hydrides. A selected sample showing sudden load drops during a quasi-static ring compression test is analysed by means of fracture mechanics for illustrative purposes. Based on the developed fracture mechanics approach, not only the deformation behaviour but also the fail-ure behaviour of irradiated as well as unirradiated Zircaloy claddings with radial hydrides under RCT loading conditions can be adequately described. T2 - 27th International Conference on Structural Mechanics in Reactor Technology - SMiRT 27 CY - Yokohama, Japan DA - 03.03.2024 KW - Cladding Embrittlement KW - Cohesive Zone Modelling KW - Ring Compression Test KW - Spent Nuclear Fuel PY - 2024 SP - 1 EP - 8 AN - OPUS4-60671 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe T1 - Failure Analysis on Irradiated Claddings Subjected to Long-Term Dry Interim Storage N2 - Long-term dry interim storage may adversely affect the mechanical properties of spent fuel rods, possibly resulting in a reduced resilience during handling or transport after storage. The cladding is the first barrier for the spent fuel pellets. An established method for characterising the cladding material is the ring compression test (RCT), in which a small, cylindrical sample of the cladding tube is subjected to a compressive load. Radial hydrides may precipitate in zirconium-based alloys (Zircaloy) under pre-storage drying and during slow cooling, which result in embrittlement of the cladding material and eventually a possible sudden failure of cladding integrity under additional mechanical loads. The focus of the presented research is on the development of appropriate nu-merical methods for predicting the mechanical behaviour and identification of limiting conditions to prevent brittle fracture of Zircaloy claddings. A modelling approach based on cohesive zones is ex-plained which is able to reproduce the propagation of cracks initiated at radial hydrides in the zir-conium matrix. The developed methods are applied to defueled samples of cladding alloy ZIRLO®, which were subjected to a thermo-mechanical treatment to reorient existing circumferential hy-drides to radial hydrides. A selected sample showing sudden load drops during a quasi-static ring compression test is analysed by means of fracture mechanics for illustrative purposes. Based on the developed fracture mechanics approach, not only the deformation behaviour but also the fail-ure behaviour of irradiated as well as unirradiated Zircaloy claddings with radial hydrides under RCT loading conditions can be adequately described. T2 - 27th International Conference on Structural Mechanics in Reactor Technology - SMiRT 27 CY - Yokohama, Japan DA - 03.03.2024 KW - Cladding Embrittlement KW - Cohesive Zone Modelling KW - Ring Compression Test KW - Spent Nuclear Fuel PY - 2024 AN - OPUS4-60672 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank T1 - KI-unterstützte Begutachtung der Behältersicherheit N2 - Die BAM führt sicherheitswissenschaftliche Begutachtungen von Gefahrgutbehältern durch, die mechanische, thermische, abschirmende und transportbezogene Analysen sowie Materialbewertungen und experimentelle Prüfungen umfassen. Diese Begutachtungen basieren auf umfassenden Sicherheitsberichten und Betriebsdokumentationen, die zahlreiche verknüpfte Dokumente und Daten enthalten. Änderungen an Komponenten oder regulatorischen Vorgaben können große Auswirkungen auf den Prüfumfang haben. Das Projekt sieht vor, die Datenanalyse und -bereitstellung mittels KI-Ansätzen zu verbessern. Es sollen Methoden zur automatischen Analyse und Verknüpfung komplexer Dokumentationen entwickelt werden. Ziel ist es, die Effizienz und Sicherheit der Datenanalyse und späteren Sicherheitsbewertung zu steigern, menschliche Fehler zu minimieren und die Qualität der Sicherheitsbewertungen zu verbessern. Die Qualität der Datenbereitstellung aus Zeichnungen, Tabellen, Texten und Berechnungen ist entscheidend für die Verarbeitung digitaler Formate der Behälterdokumentation. Ein neuro-symbolischer KI-Ansatz kombiniert neuronale Netze und symbolische KI, um die komplexen Inhalte zu analysieren und zu verknüpfen, was für die spätere Sicherheitsbewertung der Gefahrgutbehälter entscheidend ist. In vortrainierten Large Language Models (LLMs) fehlen für diesen Anwendungsfall spezifische fachliche Daten zur Behältersicherheit was zu fehlerhaften Ergebnissen führen kann. Für die Datenbereitstellung und Analyse im Zuge einer Sicherheitsbewertung gilt es dieses auszuschließen. Hierzu soll die RAG-Architektur (Retrieval-Augmented Generation) im Zusammenspiel mit LLMs angewendet werden. Dieser neue Ansatz der natürlichen Sprachverarbeitung und generativen KI soll die Stärken vortrainierter Sprachmodelle mit Fachwissen und Informationen aus Datenbanken und Dokumentensammlungen kombinieren. Die generierten Ergebnisse sollen dabei zusammen mit den verwendeten Quellen bereitgestellt werden, um eine fundierte und nachvollziehbare Basis für die Sicherheitsbewertung bilden. T2 - Informationsaustausch zur verkehrsrechtlichen Aufsicht bei der Beförderung radioaktiver Stoffe CY - Bonn, Germany DA - 04.02.2025 KW - KI KW - RAG KW - LLM PY - 2025 AN - OPUS4-62538 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Weber, Mike T1 - Consequences of an imperfectly mounted reinforcement cage in a generical cylindrical concrete container during mechanical specimen tests N2 - By highest court decision in 2007 the issued license for the Konrad repository (a former iron ore mine) for low and intermediate level radioactive waste was finally confirmed. Since then, the site is improved, prepared and equipped for the currently planned start of waste package emplacement by 2029. The Bundesanstalt fuer Materialforschung und -pruefung (BAM, Federal Institute for Materials Research and Testing) is regularly contracted by the Bundesgesellschaft für Endlagerung (BGE, Federal Company for Radioactive Waste Disposal) as the responsible authority for waste product control, waste container design testing, and waste package acceptance. In this context BAM is mainly responsible for design testing of various container types including the evaluation quality assurance measures for container manufacturing. In the written Konrad disposal requirements [1] [2], all acceptance criteria for potential final disposal containers are defined. In addition to general requirements concerning container design, materials, dimensions and others, specific mechanical load scenarios the casks have to withstand are derived from an analysis of the on-site handling and emplacement procedures. Drop tests from different heights under consideration of the most damaging drop orientation and a stacking test are two examples for safety demonstrations that have to be performed during the container design testing procedure to qualify the respective container type. The containers, whether cubic or cylindrical containers, can be made from different materials like ductile cast iron, reinforced concrete or as welded construction from steel plates and profiles. In case of concrete containers the reinforcement has the function to absorb tensile forces the concrete is not able to withstand by its own. Because of manufacturing imperfections of cylindrical concrete waste containers manufactured already decades ago, the reinforcement cages are not always exactly, axisymmetrically positioned when they were poured. This inspired BAM to perform various ABAQUS finite-element (FE) simulations [3] by using the example of a simplified cylindrical container design with generic dimensions and pure elastic material properties. As outcome the stress conditions in the container during the drop test impact under different drop positions and during the stacking test were investigated and are explained and illustrated in this contribution. Different reinforcement cage positions were calculated and compared. On the basis of the calculated tensile and compressive stress distributions suggestions are derived on how a cylindrical concrete container with an imperfectly placed reinforcement cage has to be oriented for a drop or stacking test to ensure the most damaging test scenario. T2 - ASME 2024 Pressure Vessels & Piping Conference CY - Bellevue, Washington, USA DA - 28.07.2024 KW - Container design testing procedure KW - Reinforced concrete containers KW - Drop test KW - Stacking test KW - Imperfectly mounted reinforcement cage KW - Finite-element-analysis PY - 2024 AN - OPUS4-62560 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schwarz, Irina A1 - Rieck, Arielle T1 - Valorization of carbon dioxide by electrocatalytic reduction coupled to acetogens via multiple electron carriers (Ecat-acetogens) N2 - To alleviate CO2 emissions and their impact on climate change, converting carbon dioxide into valuable products such as multi-carbon organic chemicals is of great importance. CO2 can be converted via different pathways such as electrochemical, photo-electrochemical and biological etc. Each approach offers distinct merits but also certain challenges in terms of process efficiency, product selectivity and implementation at scale etc. Therefore, developing coupled CO2 conversion systems, for instance bioelectrochemical reactors, can potentially address some of those challenges.[1] In this work, the focus is on developing cost-efficient, biocompatible, and high activity porous M-N-C catalysts with M = Ni and Co that are atomically dispersed as NiN4 and CoN4 active sites in porous carbon matrix. Ni- and Co-N-Cs are prepared by active-site imprinting approach using Mg as an imprinter.[2][3] Pyrolysis of Mg-N-C is carried out in a salt-melt at high temperatures (≥ 800 oC) and followed by an exchange with Ni or Co at low temperatures. N2-sorption of the materials reveal a micro-mesoporous structure with high surface areas (> 1000 m2 g-1) and a mass-transport enabling pore system. Extended X-ray absorption fine structure (EXAFS) reveal the existence of atomically dispersed single atom active sites with defined active site structure. A variety of Ni-N-Cs and Co-N-Cs were tested for CO2R activity in a rotating disc electrode (RDE) setup, showing high activity and selectivity towards CO2R versus the competing HER. Subsequently, these catalysts were implemented in a home-made bio-electrocatalytical system (BES) consisting of a bioreactor coupled to a CO2 electrolysis cell. Here, CO2 is first electrochemically converted to CO in the electrolysis cell which is then directly fed to bacteria (Clostridium ragsdalei) in bioreactor who further metabolize it to valuable carbon compounds such as acetate. In the BES, partial pressures of CO reached a maximum of 5.7 mbar and that of hydrogen was 2.7 mbar after 30 h. A specific exponential bacterial growth rate of 0.16 h-1 was observed with acetate formation rate of 1.8 mg L-1 h-1 and an acetate concentration of 0.103 g L-1 corresponding to acetate formation rate of 0.73 mmol d-1. As will be discussed in greater details in this talk, we have successfully demonstrated the validity of a coupled bio-electrocatalytical system concept operating with Co- and Ni-N-C catalysts for CO2 conversion. T2 - Joint SPP Conference CY - Jena, Germany DA - 06.11.2024 KW - CO2 Reduktion KW - Bioelectrocatalytical system PY - 2024 AN - OPUS4-61993 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schwarz, Irina A1 - Rieck, Arielle T1 - Valorization of carbon dioxide by electrocatalytic reduction coupled to acetogens via multiple electron carriers (Ecat-acetogens) N2 - For the realization of a sustainable energy economy, it is of great importance to develop CO2 -neutral methods producing multi-carbon organic chemicals used as feedstock as well as carbon-neutral fuels by CO2 capture and conversion. In this work, a bio-electrocatalytical system (BES) consisting of a bioreactor coupled to a CO2 electrolysis cell is established. CO2 is first electrochemically converted to CO in electrolysis cell which is then directly fed to bacteria (acetogens) to further metabolize it to valuable carbon compounds such as acetate. The objective of this study is to develop cost-efficient, biocompatible and high activity electrocatalysts that can selectively convert CO2 to CO. Porous nitrogen-doped carbons containing atomically dispersed Ni and Co (Ni or Co-N-Cs) are prepared by active-site imprinting approach. First, synthesis of Mg- or Zn-N-C was carried out through pyrolysis of precursors in a salt melt followed by exchange with Ni or Co. N2-sorption porosimetry of the materials reveal a micro-mesoporous structure with high surface areas (> 1000 m2 g-1) and a mass-transport enabling pore system. Extended X-ray absorption fine structure (EXAFS) reveal the existence of single atom sites with no formation of nanoparticles. A variety of Ni-N-Cs and Co-N-Cs were tested for CO2R activity in a rotating disc electrode (RDE) setup, showing high activity (Tafel slopes range from 77 – 130 mV/decade) and selectivity towards CO2R versus the competing HER. Before operation in the BES, first tests were performed in a single cell. Significantly increased current was detected in the CO2R test in CO2-saturated electrolyte vs. in N2 -saturated electrolyte indirectly proving formation of carbon monoxide (CO). Transfer of the electrolysis cell operation into the BES proved to be successful. For biotic operation, the BES was inoculated with Clostridium ragsdalei. Partial pressures pCO reached a maximum of 5.7 mbar and pH2 was 2.7 mbar after 30h. The reduction of partial pressures is interpreted as the consumption of the gases by C.ragsdalei. We report a specific exponential growth rate of 0.16 h-1, acetate formation rate of 1.8 mg L-1 h-1 and an acetate concetration of 0.103 g L-1 corresponding to acetate formation rate of 0.73 mmol d-1.In this work we successfully demonstrated an integrated bio-electrocatalytic system (BES) to convert CO2 into value-added chemicals. The usage of a Co- and Ni-N-Cs as the reduction catalyst within the BES allowed production of CO and H2 with relative selectivity for CO resulting in the growth of Clostridium ragsdalei and acetate production. T2 - Joint SPP Conference CY - Jena, Germany DA - 06.11.2023 KW - Bioelectrocatalytical system PY - 2023 AN - OPUS4-61995 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schwarz, Irina A1 - Rieck, Arielle T1 - Valorization of carbon dioxide by electrocatalytic reduction coupled to acetogens via multiple electron carriers (Ecat-acetogens) N2 - To alleviate CO2 emissions and their impact on climate change, converting carbon dioxide into valuable products such as multi-carbon organic chemicals is of great importance. CO2 can be converted via different pathways such as electrochemical, photo-electrochemical and biological etc. Each approach offers distinct merits but also certain challenges in terms of process efficiency, product selectivity and implementation at scale etc. Therefore, developing coupled CO2 conversion systems, for instance bioelectrochemical reactors, can potentially address some of those challenges.[1] In this work, the focus is on developing cost-efficient, biocompatible, and high activity porous M-N-C catalysts with M = Ni and Co that are atomically dispersed as NiN4 and CoN4 active sites in porous carbon matrix. Ni- and Co-N-Cs are prepared by active-site imprinting approach using Mg as an imprinter.[2][3] Pyrolysis of Mg-N-C is carried out in a salt-melt at high temperatures (≥ 800 oC) and followed by an exchange with Ni or Co at low temperatures. N2-sorption of the materials reveal a micro-mesoporous structure with high surface areas (> 1000 m2 g-1) and a mass-transport enabling pore system. Extended X-ray absorption fine structure (EXAFS) reveal the existence of atomically dispersed single atom active sites with defined active site structure. A variety of Ni-N-Cs and Co-N-Cs were tested for CO2R activity in a rotating disc electrode (RDE) setup, showing high activity and selectivity towards CO2R versus the competing HER. Subsequently, these catalysts were implemented in a home-made bio-electrocatalytical system (BES) consisting of a bioreactor coupled to a CO2 electrolysis cell. Here, CO2 is first electrochemically converted to CO in the electrolysis cell which is then directly fed to bacteria (Clostridium ragsdalei) in bioreactor who further metabolize it to valuable carbon compounds such as acetate. In the BES, partial pressures of CO reached a maximum of 5.7 mbar and that of hydrogen was 2.7 mbar after 30 h. A specific exponential bacterial growth rate of 0.16 h-1 was observed with acetate formation rate of 1.8 mg L-1 h-1 and an acetate concentration of 0.103 g L-1 corresponding to acetate formation rate of 0.73 mmol d-1. As will be discussed in greater details in this talk, we have successfully demonstrated the validity of a coupled bio-electrocatalytical system concept operating with Co- and Ni-N-C catalysts for CO2 conversion. T2 - eBiotech Workshop Week + Status Seminar CY - Jena, Germany DA - 19.03.2023 KW - Bioelectrocatalytical system PY - 2023 AN - OPUS4-61997 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Simbruner, Kai A1 - Billone, Michael C. A1 - Zencker, Uwe A1 - Liu, Yung Y. A1 - Völzke, Holger T1 - Brittle failure analysis and modeling of high-burnup PWR fuel cladding alloys N2 - The aim of this research is the development of methods for predicting mechanical behavior and identification of limiting conditions to prevent brittle failure of high-burnup (HBU) pressure water reactor (PWR) fuel cladding alloys. A finite element (FE) model of the ring compression test (RCT) was created to analyze the failure behavior of zirconium-based alloys with radial hydrides during the RCT. An elastic-plastic material model describes the zirconium alloy. The stress-strain curve needed for the elastic-plastic material model was derived by inverse finite element analyses. Cohesive zone modeling is used to reproduce sudden load drops during RCT loading. Based on the failure mechanism in non-irradiated ZIRLO® claddings, a micro-mechanical model was developed that distinguishes between brittle failure along hydrides and ductile failure of the zirconium matrix. Two different cohesive laws representing these types of failure are present in the same cohesive interface. The key differences between these constitutive laws are the cohesive strength, the stress at which damage initiates, and the cohesive energy, which is the damage energy dissipated by the cohesive zone. Statistically generated matrix-hydride distributions were mapped onto the cohesive elements and simulations with focus on the first load drop were performed. Computational results are in good agreement with the RCT results conducted on high-burnup M5® samples. It could be shown that crack initiation and propagation strongly depend on the specific configuration of hydrides and matrix material in the fracture area. KW - Cladding KW - Radial hydrides KW - Ring compression test KW - Cohesive zone model PY - 2024 DO - https://doi.org/10.1515/kern-2024-0109 SN - 2195-8580 SP - 1 EP - 9 PB - Walter de Gruyter GmbH AN - OPUS4-62409 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Nagel, Thomas A1 - Rühaak, Wolfram A1 - Amann, Florian A1 - Bracke, Guido A1 - Buske, Stefan A1 - Kowalski, Julia A1 - Reiche, Sönke A1 - Schäfer, Thorsten A1 - Scheytt, Traugott A1 - Stumpf, Thorsten A1 - Völzke, Holger A1 - Wellmann, Florian A1 - Kolditz, Olaf T1 - Deep geological disposal - Editorial to the topical collection N2 - The subsurface geological environment, historically a key source of fossil and mineral resources, has seen a significant broadening of its potential applications in recent years, with increasing emphasis on its use for energy production and storage. A critical factor in utilizing subsurface space is ensuring the sustainability of management practices, with particular attention to the potential environmental impacts that may result. The current Topical Collection on Deep Geological Disposal places greater emphasis on the geotechnical aspects of geological disposal, with a particular focus on the safe isolation of hazardous materials, including radioactive waste. The Topical Collection on Deep Geological Disposal covers both experimental (laboratory and in-situ) and theoretical studies of various geotechnical applications, such as geological disposal of radioactive or other materials, e.g. coal-based solid waste, carbon dioxide sequestration in fractured reservoirs, and brine solutions, but also aspects of uranium mining. The articles in the Topical Collections are arranged under the following headings: – Fundamental studies – Experimental studies – Numerical studies KW - Disposal KW - Radioactive Waste KW - Geology PY - 2025 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-624955 DO - https://doi.org/10.1007/s12665-024-12075-2 SN - 1866-6299 VL - 84 IS - 3 SP - 1 EP - 6 PB - Springer Nature AN - OPUS4-62495 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias A1 - Feldkamp, Martin A1 - Quercetti, Thomas A1 - Wille, Frank T1 - Experimental and Numerical Analyses for the Evaluation of Heat Fluxes of a Fire Reference Test N2 - Packages for the transport of high-level radioactive material are designed to endure severe accidents. To obtain approval, these transport packages must adhere to the specification-based criteria of the IAEA SSR-6. To ensure compliance with these requirements, specific mechanical and thermal tests need to be appointed with respect to the package type. Typically, IAEA SSR-6 prescribes mechanical tests followed by a thermal fire test as part of a cumulative test sequence. To approve the fire test, BAM uses a reference package representing the original package in its outer geometry for characterizing the actual fire and its impact on the package. This serves a dual purpose: it allows the precise adjustment of experimental parameters for the package design to be approved, and it provides input parameters for thermomechanical simulations, cf. With the help of this methodology for characterizing boundary conditions of the package, temperature evolutions within the reference package can be studied in a Finite-Element Analyses (FEA). This helps to compare the experiments with the numerical simulations on the case of the reference package, but also serves at the same time for preliminary simulations with the package design to be approved. The thermal test consists of a 30-minute fully engulfing 800°C pool fire or an equally severe fire, e.g. a propane gas fire. The fire reference test is performed prior to the regulatory fire test with the package design to be approved. The fire reference package in the described case is a closed sheet 316L steel cylinder with a wall thickness of 10 mm, a length of 182 mm, and a diameter of 102 mm. The package was instrumented with thermocouples and filled with heat resistant insulating material. T2 - ASME PVP 2024 CY - Bellevue, WA, USA DA - 28.07.2024 KW - Reference Test KW - Experimental KW - Numerical KW - Heat Flux PY - 2024 SN - 978-0-7918-8851-3 SP - 1 EP - 8 AN - OPUS4-60848 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 for the Evaluation of Hydrogen as an Energy Source for Thermal Testing of Transport Packages of Radioactive Material N2 - In this paper we present a new 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 will be capable of combusting hydrogen for a wide range of different burner geometries, mass flows and if necessary hydrogen blends. 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 calculations must be carried out in order to develop a viable concept for hydrogen fires. In the first step of the feasibility study, the temperature, structure, and radiation of various hydrogen flames are surveyed. In future works, the results will make it possible to design burner frames that are suitable for fire reference tests in order to make comparisons with pool and propane fires used in assessment procedures today. In parallel comparative numerical simulations are conducted to model the thermal behaviour of hydrogen flames using the software package Ansys®. On the one hand, the numerical simulations support the experiments by providing an overview of numerous parameters and the measuring range; on the other hand, they will help with the design of the burner frame in future work. This paper gives an overview in the design and capabilities of the test rig. Furthermore, the results of the parameter studies show that burner geometry and mass flow provide a significant design margin for the thermal shape of the hydrogen flames. In addition, the results of the initial numerical calculations will be used to determine the necessary sensors, the positions, and their operating range. Only the optimal interaction allows a controlled system that permits user-defined hydrogen fires. T2 - PVP2024, Pressure Vessels & Piping Conference CY - Bellevue, Washington USA DA - 29.07.2024 KW - Hydrogen KW - Fire KW - Computational Fluid Dynamics (CFD) KW - IAEA fire test KW - Burner PY - 2024 SN - 978-0-7918-8851-3 SP - 1 EP - 9 AN - OPUS4-60852 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Müller, Lars A1 - Scheidemann, Robert A1 - Neumeyer, Tino A1 - Komann, Steffen A1 - Wille, Frank T1 - Tightness Verification Procedures of Welded Lids for Encapsulations for Damaged Spent Nuclear Fuel in the Design Approval Process of Dual-Purpose Cask (DPC) N2 - Damaged spent nuclear fuel (DSNF) can be loaded in Germany in dual-purpose casks (DPC) for transport and interim storage. Therefore, special encapsulations are needed to guarantee a safe handling and a reliable tight closure. These encapsulations must be durable and leak-tight for a possible long interim storage term and the transport thereafter. Because components inside the package containment like these special encapsulations are not accessible within periodical inspections of the DPC. Due to the general design of DPCs for standard fuel assemblies, specific requirements needed to be considered for the design of the special encapsulations for DSNF to ensure the loading in existing package designs. Especially the content of the encapsulations with damaged spent nuclear fuel must be avoided to enter in the inner space of the DPC, due to the possible higher amount of corrosive and radioactive material as well as greater quantities of water, which can be trapped in defect fuel rods. The main difference of the encapsulations for damaged spent nuclear fuel is that they have no replaceable sealing as tightness barrier. They have a specific welded lid. Therefor the tightness needs to be shown in the design approval process for all transport conditions especially for accident conditions, where high internal impact loads can occur. As German competent authority, BAM is responsible for the safety assessment of the mechanical and thermal design, the release of radioactive material and the quality assurance aspects of manufacturing and operation. Concerning the mechanical package design BAM carried out a comprehensive safety assessment for the specific encapsulations during the package design approval process of the commonly used DPC. For the proof of tightness of the welded lid no representative standards are available. For minor loads the German KTA standards can verify the tightness of a weld seam but only for low stresses. For higher impact loads physical tests are required. These tests were performed with representative drop tests and highly sensitive leak tests. The present paper gives an overview of the applied assessments by BAM and points out the main findings of the mechanical design for the welded sealing. 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 drop tests based on complex numerical pre-calculations by the applicant which result in optimized dimensions and properties of the test specimens and representative drop heights for the drop tests. The horizontal drop orientation with a plane-parallel impact on the unyielding basement was most challenging and led to specific adaptations during preparation and conduction of the drop tests performed by BAM. With leak tests and the corresponding test evaluation, it could be finally approved that the specific welded sealing of an encapsulations for DSNF is tight for all transport conditions. T2 - ASME PVP 2024 CY - Bellevue, WA, USA DA - 28.07.2024 KW - Tightness verification KW - Weld seams KW - Drop tests KW - Encapsulations for damaged spent nuclear fuel KW - Helium leak tests PY - 2024 SN - 978-0-7918-8851-3 SP - 1 EP - 10 CY - New York AN - OPUS4-61351 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Wille, Frank A1 - Linnemann, Konrad A1 - Ramsay, Jeff A1 - Reiche, Ingo T1 - Transport of large nuclear power plant components – new SCO-III regulations and mechanical design assessment N2 - The decommissioning or refurbishment of nuclear facilities necessitates either the storage or disposal of large radioactive components such as steam generators, pressurizers, reactor pressure vessels and heads, and coolant pumps, to list the major contributors. These components or objects are large in size and mass, measuring up to approximately 6 meters in diameter, up to 20 meters in length, and weighing over 400 000 kg. In many situations, the components are transported off-site to a storage, disposal or recycling/treatment facility. Previously, many large objects had to be transported under special arrangement. The latest 2018 edition of the International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive Material, No. SSR-6, incorporates regulations for the shipment of contaminated, but not activated large objects as a new category of surface contaminated object, SCO-III, based on the IAEA “performance package” concept. This paper provides background and practical guidance on these regulations. Additionally, first experiences with SCO-III in the approval process are presented. For SCO-III components a mechanical assessment regarding the tests specified in the transport regulations SSR-6 for demonstrating ability to withstand normal conditions of transport is required - a free drop of the package onto an unyielding target and a penetration test have to be investigated. Large components are unique objects; therefore, it is not possible to choose experimental testing as assessment method. The application of a complex numerical analysis for mechanical proof is necessary. The assessment of the loads takes place based on local stress distributions. The large nuclear components have typically been transported in an unpackaged manner, so that the external shell of the component provides the containment wall. The paper will represent the methods, which are used for the evaluation of the mechanical integrity of the object for transport approval. T2 - PVP2024, Pressure Vessels & Piping Conference CY - Bellevue, Washington USA DA - 29.07.2024 KW - Transport KW - Radioaktive Stoffe KW - Rückbau kerntechnischer Anlagen KW - Gefahrgut PY - 2024 SN - 978-0-7918-8851-3 SP - 1 EP - 4 AN - OPUS4-60829 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR T1 - Amts- und Mitteilungsblatt, Band 50, Heft 2 & 3 T3 - Amts- und Mitteilungsblatt der BAM - 2/2020 & 3/2020 KW - Anerkennungen KW - Zulassungen KW - Gefahrgutregeln KW - Festlegungen KW - Richtlinien PY - 2020 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-512342 SN - 0340-7551 VL - 50 IS - 2 & 3 SP - 1 EP - 151 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin AN - OPUS4-51234 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR T1 - Amts- und Mitteilungsblatt, Band 50, Heft 4 T3 - Amts- und Mitteilungsblatt der BAM - 4/2020 KW - Gefahrgutregeln KW - Anerkennungen KW - Zulassungen KW - Richtlinien KW - Festlegungen PY - 2020 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-527351 SN - 0340-7551 VL - 50 IS - 4 SP - 451 EP - 474 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin AN - OPUS4-52735 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR T1 - Amts- und Mitteilungsblatt, Band 51, Heft 2 T3 - Amts- und Mitteilungsblatt der BAM - 2/2021 KW - Anerkennungen KW - Zulassungen KW - Gefahrgutregeln KW - Festlegungen KW - Richtlinien KW - Gebührenverordnung KW - Preis- Leistungsverzeichnis PY - 2021 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-529061 SN - 0340-7551 VL - 51 IS - 2 SP - 71 EP - 110 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin AN - OPUS4-52906 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Weber, Mike A1 - Völzke, Holger A1 - Nieslony, Gregor T1 - Consequences of an imperfectly mounted reinforcement cage in a generical cylindrical concrete container during mechanical specimen tests N2 - By highest court decision in 2007 the issued license for the Konrad repository (a former iron ore mine) for low and intermediate level radioactive waste was finally confirmed. Since then, the site is improved, prepared and equipped for the currently planned start of waste package emplacement by 2029. The Bundesanstalt fuer Materialforschung und -pruefung (BAM, Federal Institute for Materials Research and Testing) is regularly contracted by the Bundesgesellschaft für Endlagerung (BGE, Federal Company for Radioactive Waste Disposal) as the responsible authority for waste product control, waste container design testing, and waste package acceptance. In this context BAM is mainly responsible for design testing of various container types including the evaluation quality assurance measures for container manufacturing. In the written Konrad disposal requirements all acceptance criteria for potential final disposal containers are defined. In addition to general requirements concerning container design, materials, dimensions and others, specific mechanical load scenarios the casks have to withstand are derived from an analysis of the on-site handling and emplacement procedures. Drop tests from different heights under consideration of the most damaging drop orientation and a stacking test are two examples for safety demonstrations that have to be performed during the container design testing procedure to qualify the respective container type. The containers, whether cubic or cylindrical containers, can be made from different materials like ductile cast iron, reinforced concrete or as welded construction from steel plates and profiles. In case of concrete containers the reinforcement has the function to absorb tensile forces the concrete is not able to withstand by its own. Because of manufacturing imperfections of cylindrical concrete waste containers manufactured already decades ago, the reinforcement cages are not always exactly, axisymmetrically positioned when they were poured. This inspired BAM to perform various ABAQUS finite-element (FE) simulations by using the example of a simplified cylindrical container design with generic dimensions and pure elastic material properties. As outcome the stress conditions in the container during the drop test impact under different drop positions and during the stacking test were investigated and are explained and illustrated in this contribution. Different reinforcement cage positions were calculated and compared. On the basis of the calculated tensile and compressive stress distributions suggestions are derived on how a cylindrical concrete container with an imperfectly placed reinforcement cage has to be oriented for a drop or stacking test to ensure the most damaging test scenario. T2 - ASME 2024 Pressure Vessels & Piping Conference CY - Bellevue, Washington, USA DA - 28.07.2024 KW - Container design testing procedure KW - Reinforced concrete containers KW - Drop test KW - Stacking test KW - Imperfectly mounted reinforcement cage KW - Finite-element-analysis PY - 2024 SN - 978-0-7918-8851-3 DO - https://doi.org/10.1115/PVP2024-123797 VL - 5 SP - 1 EP - 8 PB - ASME CY - New York City, USA AN - OPUS4-62558 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR T1 - Amts- und Mitteilungsblatt, Band 52, Heft 1 T3 - Amts- und Mitteilungsblatt der BAM - 1/2022 PY - 2022 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-545287 SN - 0340-7551 VL - 52 IS - 1 SP - 1 EP - 54 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin AN - OPUS4-54528 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR T1 - Amts- und Mitteilungsblatt, Band 52, Heft 2 T3 - Amts- und Mitteilungsblatt der BAM - 2/2022 KW - Festlegungen KW - Zulassungen KW - Richtlinien KW - Anerkennungen PY - 2022 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-550917 SN - 0340-7551 VL - 52 IS - 2 SP - 55 EP - 158 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin AN - OPUS4-55091 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR T1 - Amts- und Mitteilungsblatt, Band 51, Heft 4 T3 - Amts- und Mitteilungsblatt der BAM - 4/2021 PY - 2021 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-541902 SN - 0340-7551 VL - 51 IS - 4 SP - 135 EP - 158 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin AN - OPUS4-54190 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Qiao, Linan A1 - Nagelschmidt, Sven A1 - Herbrich, Uwe A1 - Keller, Christian T1 - Introduction of a Power Law Time-Temperature Equivalent Formulation for the Description of Thermorheologically Simple and Complex Behavior N2 - Abstract: In this work, a conceptual framework is suggested for analyzing thermorheologically simple and complex behavior by using just one approach. Therefore, the linear relation between master time and real time which is required in terms of the time-temperature superposition principle was enhanced to a nonlinear equivalent relation. Furthermore, we evaluate whether there is any relation among well-known existing time-temperature equivalent formulations which makes it possible to generalize different existing formulations. For this purpose, as an example, the power law formulation was used for the definition of the master time. The method introduced here also contributes a further framework for a unification of established time-temperature equivalent formulations, for example the time-temperature superposition principle and time-temperature parameter models. Results show, with additional normalization conditions, most of the developed time-temperature parameter models can be treated as special cases of the new formulation. In the aspect of the arrow of time, the new defined master time is a bended arrow of time, which can help to understand the corresponding physical meaning of the suggested method. KW - bended arrow of time KW - time-temperature superposition principle KW - time-temperature equivalent formulation PY - 2022 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-543800 DO - https://doi.org/10.3390/ma15030726 VL - 15 IS - 3 SP - 1 EP - 11 PB - MDPI AN - OPUS4-54380 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR T1 - Amts- und Mitteilungsblatt, Band 52, Heft 3 T3 - Amts- und Mitteilungsblatt der BAM - 3/2022 KW - Anerkennungen KW - Zulassungen KW - Richtlinien PY - 2022 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-558323 SN - 0340-7551 VL - 52 IS - 3 SP - 159 EP - 404 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin AN - OPUS4-55832 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR T1 - Amts- und Mitteilungsblatt, Band 53, Heft 1 T3 - Amts- und Mitteilungsblatt der BAM - 1/2023 KW - Anerkennungen KW - Zulassungen KW - Richtlinien PY - 2023 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-574038 SN - 0340-7551 VL - 53 IS - 1 SP - 1 EP - 340 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin AN - OPUS4-57403 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR T1 - Amts- und Mitteilungsblatt, Band 53, Heft 3 T3 - Amts- und Mitteilungsblatt der BAM - 3/2023 KW - Anerkennungen KW - Zulassungen KW - Richtlinien PY - 2023 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-585302 SN - 0340-7551 VL - 53 IS - 3 SP - 463 EP - 516 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin AN - OPUS4-58530 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR T1 - Amts- und Mitteilungsblatt, Band 53, Heft 4 T3 - Amts- und Mitteilungsblatt der BAM - 4/2023 KW - Anerkennungen KW - Zulassungen PY - 2023 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-592823 SN - 0340-7551 VL - 53 IS - 4 SP - 517 EP - 540 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin AN - OPUS4-59282 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Baeßler, Matthias A1 - Herrmann, Ralf A1 - Hille, Falk A1 - Wille, Frank T1 - Dynamisches Verhalten und Überwachung des Großen Fallturms der BAM in Horstwalde N2 - Falltürme sind Bauwerke, die als Versuchsanlagen sehr speziellen, impulsartigen Belastungen ausgesetzt sind. Am Fallturm auf dem Testgelände Technische Sicherheit (TTS) der BAM wurde bei Routineinspektionen eine Abnahme der strukturellen Integrität in Form von Vorspannungsverlusten in den Bolzen der Stahlverbindungen festgestellt. Um ein Verständnis für die zugrundeliegenden Trag- und Schädigungsmechanismen zu erlangen, wurde ein umfassendes Structural Health Monitoring (SHM) System geplant und am Bauwerk installiert unter Nutzung von digitalen Bauwerksmodellen. Für die Auslegung des Überwachungssystems, insbesondere aber zur Unterstützung der Untersuchung des Schädigungsprozesses, wurden Finite-Elemente-Modelle erstellt. Um sicherzustellen, dass die FE-Modelle das reale Tragwerksverhalten mit ausreichender Genauigkeit abbilden, mussten sie jedoch in Bezug auf die gemessenen Antworten des Tragwerks kalibriert werden. Der vorliegende Beitrag beschreibt experimentelle und numerische Untersuchungen zur Identifizierung des strukturellen Systems des Stahlrohrgitterturms in Vorbereitung einer Überwachungskampagne. Die Auswertung von gemessenen Schwingungen unter ambienter Anregung ermöglichte die Identifizierung der Eigenfrequenzen mehrerer globaler Schwingungsmoden des Fallturms. Zur Modellvalidierung wurde zunächst eine Sensitivitätsanalyse durchgeführt, um die Parameter mit dem größten Einfluss zu ermitteln. Anschließend wurde ein evolutionärer Algorithmus (EA) zur Optimierung nach dem Prinzip der Minimierung der Differenzen zwischen gemessenen und simulierten charakteristischen Antworten eingesetzt. Das aktualisierte Modell wurde schließlich an der dynamischen Reaktion der Turmstruktur infolge einer realen Falltest-induzierten Stoßbelastung validiert. Die Ergebnisse zeigten eine gute Übereinstimmung zwischen numerischen und experimentellen Ergebnissen. N2 - Drop test towers are structures subjected to very specific dynamic loadings. At the drop test tower at the Test Site Technical Safety (TTS) of BAM routine inspections revealed a decline of structural integrity in form of loss of pretension in bolts of structural steel connections. To get an understanding about the underlying damage mechanisms as well as to assure the structural safety in operation, a multifaceted Structural Health Monitoring (SHM) system was planned and installed at the structure with the help of digital models. For planning the monitoring system but especially for supporting the investigation of the damaging process finite element models are deployed. Though, to ensure the capability of the FE model to reproduce the real structural behavior in sufficient accuracy, it needs to be calibrated in respect to measured responses of the structure. The present contribution describes experimental and numerical investigations to identify the structural system of the steel tube lattice tower in preparation of the monitoring campaign. An ambient vibration test allowed the identification of the natural frequencies of several global vibrational modes of the drop test tower. For model updating first a sensitivity analysis is applied to identify the most influencing parameter. In succession a genetic algorithm was applied for optimization in the sense of minimization of the difference between measured and simulated characteristic responses. The updated model is finally validated on the dynamic response of the tower structure to a real drop test induced impact loading. The results showed a good agreement between numerical and experimental results though the robustness of the simulation should be improved by more sophisticated numerical modelling. T2 - 7. VDI-Fachtagung Baudynamik CY - Würzburg, Germany DA - 27.04.2022 KW - Großer Fallturm Horstwalde KW - Structural Health Monitoring KW - Belastungsversuch KW - Modalanalyse KW - Schwingungsdynamik KW - Finite Elemente Simulation PY - 2022 SN - 978-3-18-092379-6 SN - 978-3-18-102379-2 DO - https://doi.org/10.51202/9783181023792-265 SN - 0083-5560 VL - 2379 SP - 265 EP - 284 PB - VDI-Verlag CY - Düsseldorf AN - OPUS4-55472 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - THES A1 - Nagelschmidt, Sven T1 - Ein Beitrag zur Zusammenführung von Zeit-Temperatur-Äquivalenz-Methoden: Entwicklung und Anwendung am Beispiel ausgewählter Materialverhalten für Zeit-Temperatur-Parameter und Zeit-Temperatur-Superpositionsprinzip N2 - In der Wissenschaft und Technik gibt es verschiedene Gründe, um auf Basis geeigneter Modelle in die Zukunft schauen zu wollen, beispielsweise um zu bewerten, ob ein Bauteil auch noch deutlich länger verwendet werden kann als eigentlich einmal vorgesehen. Eine Methode dieses zu tun, basiert auf dem Zeit-Temperatur-Äquivalenz-Prinzip, welches besagt, dass ein Zustand oder eine Materialeigenschaft gleichwertig bei verschiedenen Zeit-Temperatur-Kombinationen auftritt oder erreicht werden kann. Höhere Temperaturen verkürzen in der Regel die Dauer und umgekehrt. In den letzten Jahrzehnten hat sich ein umfangreiches Methodenspektrum für unterschiedliche Werkstoffe und Anwendungsgebiete entwickelt, sodass die Identifikation einer geeigneten Methode für einen konkreten Anwendungsfall oder neue Materialien eine Herausforderung darstellt. These: „Fortschrittlich wäre, existierende Methoden zusammenzuführen, methodenspezifische Vorteile zu kombinieren, um mit geringerem Aufwand ein geeignetes Prognosemodell zu entwickeln.“ Für metallische Werkstoffe und Polymere verläuft die Entwicklung von Prognosemodellen mit Zeit-Temperatur-Korrelation seit ca. 1940 parallel und unabhängig voneinander. In diesem Zusammenhang bekannte Methoden sind das Zeit-Temperatur-Superpositionsprinzip und Zeit-Temperatur-Parameter, wie der LARSON-MILLER-Parameter. Die jeweiligen methodischen Ansätze sind in der Regel anwendungs- und materialspezifisch und nur einzelnen Fachartikeln zu entnehmen. Eine zusammenführende thematische Übersicht und Untersuchung existierender Methoden wurden bislang nicht publiziert. Diese Forschungsarbeit verfolgt dahingehend einen neuartigen methodischen Ansatz und zeigt untersuchte Gemeinsamkeiten und Unterschiede als auch Analogien für das Zeit-Temperatur-Superpositionsprinzip und Zeit-Temperatur-Parameter anhand bestimmter Merkmale auf. Dafür wurden verschiedene analytische und grafische Ansätze verwendet. Ferner wird eine zusammenführende Untersuchung anhand eines rheologischen Materialmodells sowie anhand eines praktischen Anwendungsbeispiels gezeigt. Hergeleitet wurde u. a., dass das Prinzip der Zeit-Temperatur-Superposition für sogenanntes thermorheologisch einfaches und komplexes Verhalten konkreten Zeit-Temperatur-Parametern zugeordnet werden können. Und dadurch Verschiebefunktionen nicht nur in Abhängigkeit der Temperatur, sondern auch abhängig vom Zustand untersucht und definiert werden können. Ferner ermöglicht eine Skalierung der Zeit-Temperatur-Parameter auf eine Referenztemperatur physikalisch anschaulichere Auswertungen analog zum Zeit-Temperatur-Superpositionsprinzip. Untersuchungen zeigen, dass sich für einen konkreten Anwendungsfall die geeignetste Zeit-Temperatur-Äquivalenz-Methode aus einer gegenseitigen Abhängigkeit bzw. Kompatibilität einzelner Elemente, wie zugrunde gelegte Daten, Koordinatenachsenskalierung, ermittelte Zeit-Temperatur-Äquivalenz, Masterfunktionsansatz und der geforderten Interpolationsgüte herleitet. Der gewählte Forschungsansatz und die erzielten Ergebnisse bieten eine Plattform für die weitere Entwicklung von Prognosemodellen auf Basis des Zeit-Temperatur-Äquivalenz-Prinzips, insbesondere im Hinblick auf eine Zusammenführung und Kombination existierender Methoden. KW - Zeit-Temperatur-Äquivalenz KW - Zeit-Temperatur-Korrelation KW - Zeit-Temperatur-Superposition KW - Extrapolation PY - 2024 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-601530 DO - https://doi.org/10.14279/depositonce-20439 SP - 1 EP - 145 CY - TU Bibliothek online AN - OPUS4-60153 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - THES A1 - Keller, Christian T1 - Beitrag zur numerischen Beanspruchungsanalyse an dünnwandigen Stahlblechcontainern im Fallversuch - Schädigungsmechanische Materialmodellierung duktiler Werkstoffe unter Berücksichtigung der Dehnratenabhängigkeit der plastischen Instabilität N2 - Gegenstand der vorliegenden Arbeit ist die Bereitstellung expliziter numerischer Simulationen von Fallversuchen mit dünnwandigen Stahlblechcontainern, die als Endlagerbehälter für radioaktive Abfälle mit vernachlässigbarer Wärmeentwicklung, d. h. schwach- und mittelradioaktive Abfälle, für die Verbringung in das Endlager Konrad vorgesehen sind. Die Betrachtung von potentiellen Absturzszenarien ist ein grundlegender und zentraler Bestandteil der Sicherheitsnachweise zur Auslegung der verschiedenen endlagergängigen Behälter- und Containertypen gegen mechanische Störfallbelastungen. Für dünnwandige Stahlblechcontainer existierten bislang keine sicherheitstechnischen Untersuchungen, die auf numerischen Bewertungsmethoden basieren und eine Bewertung der vorhandenen Sicherheitsreserven hinsichtlich der mechanischen Integrität ermöglichen. Daraus resultierte die Motivation, ein verifiziertes Finite-Elemente-Modell eines repräsentativen Referenzcontainers zu entwickeln, das das dynamische Verformungs- sowie duktile Schädigungs- und Versagensverhalten in numerischen Simulationen von dynamischen Lastfällen physikalisch mit der erforderlichen Güte beschreibt. Duktile Schädigungs- und Versagensvorgänge metallischer Werkstoffe gehen grundsätzlich mit großen plastischen Dehnungen einher und führen somit unweigerlich zu der Notwendigkeit der Diskussion von plastischer Instabilität und damit verknüpften Lokalisierungseffekten, die einen wesentlichen Einfluss auf die Entwicklung des lokalen Beanspruchungszustands haben. Für die schädigungsmechanische Materialmodellierung folgt hieraus das grundsätzliche Erfordernis der korrekten Berücksichtigung des Instabilitätsbeginns, der in der Regel dehnratenunabhängig angenommen wird. Für dynamische Randbedingungen ist der werkstoffspezifische Einfluss der Dehnrate auf das Einsetzen der Lokalisierung jedoch nicht uneingeschränkt vernachlässigbar, so dass im Rahmen dieser Arbeit ein theoretischer Ansatz ausgearbeitet wird, der die plastische Instabilität dehnratenabhängiger Werkstoffe anhand des zeit- und ortsabhängigen Dehnungsgradienten im einachsigen Zugversuch diskutiert. Darüber hinaus ist für eine hinreichend genaue Materialmodellierung neben der korrekten Prognose des Instabilitätsbeginns auch die korrekte Beschreibung des Verformungsverhaltens jenseits der Gleichmaßdehnung notwendig. Zu diesem Zweck wird in dieser Arbeit eine konstitutive Beziehung entwickelt, die sowohl unter Berücksichtigung der plastischen Instabilität als auch unter der Beachtung von ver- sowie entfestigenden Einflussfaktoren der dynamischen Plastizität formuliert werden kann. Insgesamt wird eine praxistaugliche Bewertungsmethode der mechanischen Integrität dünnwandiger Stahlblechcontainer unter Störfallbedingungen auf Basis expliziter dynamischer Simulationen erarbeitet, die die komplexen duktilen Schädigungs- und Versagensmechanismen dehnratenabhängiger Werkstoffe berücksichtigt. Mit der zur Simulation von Fallversuchen entwickelten numerischen Modellbildung und den zur Verifizierung entsprechend mit Testcontainern im Originalmaßstab durchgeführten Fallversuchen wird nachgewiesen, dass anhand des Finite-Elemente-Modells eines repräsentativen Referenzcontainers zum einen eine quantitativ belegte Bestimmung ungünstiger Fallorientierungen hinsichtlich maximaler Verformungen und zum anderen eine realistische Abbildung des duktilen Versagensverhaltens ermöglicht wird. Damit können tatsächlich vorhandene Sicherheitsreserven bei potentiell zu unterstellenden Behälterabstürzen quantitativ aufgezeigt und zukünftig eine verbesserte sicherheitstechnische Beurteilung von Stahlblechcontainern im Fallversuch bereitgestellt werden. Damit leistet die vorliegende Arbeit einen wichtigen Beitrag für die Bewertung von Sicherheitsnachweisen von Endlagerbehältern für radioaktive Abfälle und trägt dazu bei, den langfristigen Schutz von Mensch und Umwelt vor Schäden durch radioaktive Stoffe zu gewährleisten. N2 - The subject of the present work is the provision of explicit numerical simulations of drop tests with thin-walled sheet steel containers, which are intended as repository containers for radioactive waste with negligible heat generation, i.e. low and intermediate level waste, for shipment to the Konrad repository. The consideration of potential crash scenarios is a fundamental and central component of the safety analyses for the design of the various types of casks and containers suitable for final disposal against mechanical accident loads. For thin-walled sheet steel containers, no safety investigations based on numerical assessment methods existed so far that would allow an evaluation of the existing safety reserves with regard to mechanical integrity. This resulted in the motivation to develop a verified finite element model of a representative reference container that physically describes the dynamic deformation and ductile damage and failure behaviour in numerical simulations of dynamic load cases with the required quality. Ductile damage and failure processes of metallic materials are fundamentally accompanied by large plastic strains and thus inevitably lead to the need to discuss plastic instability and associated localisation effects, which have a significant influence on the development of the local stress state. For damage-mechanical material modelling this results in the fundamental requirement of correctly considering the onset of instability, which is usually assumed to be strain-rate independent. For dynamic boundary conditions, however, the material-specific influence of the strain rate on the onset of localisation cannot be neglected without restriction, so that a theoretical approach is elaborated within the scope of this work that discusses the plastic instability of strain-rate-dependent materials on the basis of the time- and location-dependent strain gradient in the uniaxial tensile test. Furthermore, for a sufficiently accurate material modelling, besides the correct prediction of the onset of instability, the correct description of the deformation behaviour in the postcritical region, i.e., beyond the uniform strain, is necessary. For this purpose, a constitutive relationship is developed in this work, which can be formulated both under consideration of the plastic instability as well as under consideration of hardening as well as softening influencing factors of the dynamic plasticity. Overall, a practical assessment method of the mechanical integrity of thin-walled sheet steel containers under accident conditions is developed based on explicit dynamic simulations, which takes into account the complex ductile damage and failure mechanisms of strain rate-dependent materials. With the numerical modelling developed for the simulation of drop tests and the drop tests carried out accordingly with full-scale test containers for verification, it is demonstrated that, on the basis of the finite element model of a representative reference container, on the one hand a quantitatively proven determination of unfavourable drop orientations with regard to maximum deformations and, on the other hand, a realistic representation of the ductile failure behaviour is made possible. This allows it to quantitatively demonstrate actually existing safety reserves in case of potential container crashes and to provide an improved safety assessment of sheet steel containers in drop tests in the future. This work thus makes an important contribution to the evaluation of safety verifications of final storage containers for radioactive waste and helps to ensure the long-term protection of humans and the environment from damage caused by radioactive substances. KW - FEM KW - Dynamische Plastizität KW - Plastische Instabilität KW - Duktile Schädigung KW - Endlager Konrad PY - 2024 DO - https://doi.org/10.14279/depositonce-21874 SP - 1 EP - 188 PB - DepositOnce CY - Berlin AN - OPUS4-61581 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Rolle, Annette A1 - Neumeyer, Tino T1 - Prüfung und Zulassung von radioaktiven Stoffen in besonderer Form N2 - Radioaktive Stoffe in besonderer Form (SFRM) sind nicht dispergierbare feste radioaktive Stoffe oder dichte Kapseln, die radioaktive Stoffe enthalten /1/. SFRM sind eine Kategorie innerhalb der verkehrsrechtlichen Vorschriften. Für die Beförderung zu Anwendern in der Industrie, Medizin und Forschung werden umschlossene radioaktive Stoffe (Strahler) gemäß ihrem aktivitätsabhängigen Gefahrenpotenzial verpackt. Strahler mit einer hohen Aktivität (> A2) erfordern entsprechend der verkehrsrechtlichen Vorschriften eine Beförderung in Typ B (U) Versandstücken, die als unfallsicher gelten. Alternativ besteht bis zu einer Aktivität < A1 die Möglichkeit der Beförderung in nicht unfallsicheren Typ A Versandstücken, wenn die Strahler nachweislich unfallsicher ausgelegt sind und eine Zulassung als SFRM vorliegt. Die Bundesanstalt für Materialforschung und –prüfung (BAM) ist gemäß GGVSEB §8 (2) /2/ in Deutschland die zuständige Behörde für die Prüfung und Zulassung radioaktiver Stoffe in besonderer Form. KW - Zulassung KW - Radioaktiv KW - Beförderung KW - Strahlenschutz PY - 2020 SN - 0947-434 X IS - 1 SP - 14 EP - 16 PB - TÜV Media CY - Köln AN - OPUS4-50763 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Herrmann, Ralf A1 - Hille, Falk A1 - Said, Samir A1 - Sterthaus, Jens A1 - Müller, Karsten A1 - Quercetti, Thomas A1 - Wille, Frank A1 - Paffenholz, J.-A. A1 - Baeßler, Matthias ED - Papadrakakis, M. ED - Fragiadakis, M. ED - Papadimitriou, C. T1 - Implementing a Structural Health Monitoring system using digital models of the BAM large drop test facility in Horstwalde N2 - At the Bundesanstalt für Materialforschung und -prüfung (BAM) full scale specimens for nuclear transport and storage containers (casks) are tested for their structural integrity in a series of drop tests on the Test Site Technical Safety in Horstwalde, 50 km south of Berlin. These drop tests cause a major stress not only on the casks, but also on the steel tower structure of the test facility, itself. The load pattern makes the structure very interesting for detailed investigation. The focus of the monitoring lies on the bolted joints of the flange connections that are a typical connection for cylindrical elements if welding is technical or economical unfavorable. The definition of the monitoring takes was done by investigating the existing documents and inspection results accompanied by building an initial digital representation of the structure, consisting of two finite element (FE) models and a geometrical 3D point cloud representation. As a first step the structures behavior during static and dynamic loading was analyzed using measurement data and an updated numerical FE Model. The idea behind is to use models for a digital planning and operation/evaluation of the structural health monitoring. A static FE simulation and a dynamic FE simulation are generated, to investigate how the structure behaves under the load conditions. T2 - XI International Conference on Structural Dynamics (EuroDyn 2020) CY - Online meeting DA - 23.11.2020 KW - Structural Health Monitoring KW - Drop Tests KW - System Identification KW - Digital Models KW - BIM PY - 2020 UR - https://generalconferencefiles.s3-eu-west-1.amazonaws.com/eurodyn_2020_ebook_procedings_vol1.pdf SN - 978-618-85072-0-3 VL - 1 SP - 1293 EP - 1304 PB - Institute of Structural Analysis and Antiseismic Research CY - Athen AN - OPUS4-51592 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Hille, Falk A1 - Herrmann, Ralf T1 - Structural Health Monitoring am Großen Fallturm der BAM N2 - In diesem Beitrag wird die Structural Health Monitoring Kampagne am Großen Fallturm der BAM vorgestellt. T2 - Seminar "Zerstörungsfreie Prüfung" CY - Online meeting DA - 13.01.2022 KW - Belastungsversuch KW - Großer Fallturm Horstwalde KW - Schwingungsdynamik KW - Modalanalyse PY - 2022 AN - OPUS4-55478 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Hille, Falk T1 - Structural Health Monitoring am Großen Fallturm der BAM N2 - Am Fallturm auf dem Testgelände Technische Sicherheit (TTS) der BAM wurden bei Inspektionen Vorspannungsverluste in den Bolzen der Stahlverbindungen festgestellt. Um ein Verständnis für die zugrundeliegenden Trag- und Schädigungsmechanismen zu erlangen und um den Zustand der vorgespannten Schraubverbindungen langzeitlich zu überwachen, wurde am Fallturm ein Structural Health Monitoring (SHM) System installiert. Für die Auslegung des Monitoringsystems sowie zur Unterstützung der Untersuchung des Schädigungsprozesses wurde ein numerisches Modell erstellt und in Bezug auf die gemessenen Antworten des Tragwerks kalibriert. Im Vortrag werden die experimentellen und numerischen Untersuchungen zur Systemidentifikation des Stahlrohrgitterturms als auch die Überwachungskampagne mit dem eingesetzten Monitoringsystem sowie die Messergebnisse und deren Bewertung vorgestellt. T2 - Seminar "Zerstörungsfreie Prüfung" am Lehrstuhl für Zerstörungsfreie Prüfung ,Technische Universität München CY - Online meeting DA - 13.01.2022 KW - Structural Health Monitoring KW - Schadensüberwachung KW - Schwingungsmonitoring PY - 2022 AN - OPUS4-56667 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias T1 - Fracture Mechanical Investigations on a Welding Seam of a Thick-Walled Transport Package N2 - Untersuchung einer Schweißnaht mit verschiedenen Codes. Vergleiche von experimentellen und numerischen Ergebnissen T2 - Technical Exchange IRSN – BAM: Transport & Storage of Packages for Radioactive Material CY - Cadarache, France DA - 13.10.2022 KW - Drop test KW - Fracture initiation KW - Transport package PY - 2022 AN - OPUS4-56055 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 - Quercetti, Thomas A1 - Wille, Frank A1 - Neumann, Martin A1 - Linnemann, Konrad 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 materials transport PY - 2023 SP - 1 EP - 10 AN - OPUS4-57732 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Neumann, Martin A1 - Gleim, Tobias A1 - Gradt, Thomas T1 - Friction coefficients for wood-wood and wood-steel high pressure contact under temperatures between -40 °C and 90 °C 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 offen applied in layers of altemating direction. The friction at the interfaces between these layers is of crucial importance for the impact and energy absorption e.g., at an accidental impact of a cask against a hard component. In order to get detailed Information for corresponding numerical calculations, in this study the friction coefficient for the combinations wood-wood and wood-steel was measured in the temperature ränge between -40 °C and 90 °C according to the relevant stress conditions for such casks. Results show decreasing friction with increasing temperature, ranging from 0.43 at -40 °C to 0.22 for 90 °C for wood-steel combinations and from 0.3 at -40 °C to 0.24 at 90 °C to for a wood-wood combination. KW - Wood KW - Friction KW - Transport cask KW - Radioactive material PY - 2023 DO - https://doi.org/10.24053/TuS-2023-0007 SN - 0724-3472 VL - 70 IS - 2 SP - 5 EP - 12 PB - expert verlag AN - OPUS4-57787 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schubert, Sven A1 - Reichardt, Adrian A1 - Müller, Lars A1 - Neumann, Martin A1 - Komann, Steffen A1 - Wille, Frank T1 - Introduction of the German ageing management guide for packages for transport of radioactive materials N2 - The consideration of ageing mechanisms is with integration of the new para 613A into IAEA SSR-6 (Rev. 1) now obligatory for the design of transport packages. In addition, para 809(f) requires for packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance. Para 503(e) requires that all packaging components and radioactive contents have been maintained during storage in a manner that all requirements specified in IAEA SSR-6 (Rev.1) and in the applicable certificates of approval have been fulfilled. The evaluation of ageing mechanisms and their effects including monitoring are part of BAM’s authority assessment tasks related to the mechanical and thermal package design and quality assurance aspects. BAM has compiled a guideline for the implementation of ageing assessment and of the measures for ageing management of the approval procedure based on requirements of IAEA SSR-6 (Rev.1). The guideline is applicable only for packages requiring a competent authority approval. The paper aims to describe the structure of the guideline and the general approach for ageing management requirements. The type and amount of measures for ageing management depend mainly on the use of the package and on the ageing effects for the component, which result from relevant ageing mechanisms during package operation time. The implementation of measures for ageing management is divided into three levels – systemic measures, package design related measures and documentation. The systemic measures are attributed to the general management system and define the whole activities for organization of ageing management like structure, responsibilities, documentation, reports and evaluation. The package design related measures are defined in an ageing management plan (AMP). These measures shall ensure that the anticipated changes of the package design under consideration of ageing effects still complies with the design approval specification. Therefore, an ageing surveillance program (ASP) and, if necessary, a gap analysis program shall be developed. The ageing management documentation (AMD) ensures the continuous documentation of the compliance of a specific package to the approved package design, comprising mainly records resulting from operation and surveillance. T2 - PATRAM22 - 20th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Juan-les-Pins, France DA - 11.06.2023 KW - Guide KW - Ageing KW - Mechanism KW - Package KW - Management PY - 2023 SP - 1 EP - 10 PB - World Nuclear Transport Institute (WNTI) CY - London AN - OPUS4-57770 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin A1 - Quercetti, Thomas A1 - Wille, Frank A1 - Gröke, Carsten A1 - Neumeyer, Tino 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 regulations – packages of the classification excepted, Industrial packages Type 1, 2 and 3 and Type A packages. Currently an upsurge in number and variation of these package designs can be seen in Germany, resulting from the phase out of nuclear energy in Germany as well as e. g. increased use of radioactive material for medical purposes. A design assessment regarding the package safety is required in the international IAEA SSR-6 regulations. BAM operates facilities for the performance of all regulatory tests required such as drop towers for a wide range of package masses and dimensions, fire test, leak tightness measurements and pressure test facilities. Experiences with several package types are shown. Additionally, IAEA SSR-6 requires the establishment of a management system for design, manufacture, maintenance, and repair of the packaging as well as for the preparation, consigning, loading, carriage, unloading and receipt of the package. Relevant for Germany, BAM has published guidance material on the process of management system acceptance in the technical guide BAM-GGR 016. The requirements encompass quality management plans for the manufacturing of packages including independent manufacturing surveillance and specific instructions for operation, maintenance, and repair of packagings. Examples for management system specifics and requirements are given. Since the latest edition of the IAEA SSR-6 regulations an ageing evaluation including systematic ageing management measures are required for all kind of package types. BAM is going to update the guidance material BAM-GGR 016 to support the stakeholders with relevant information to fulfil the ageing aspect for packages not requiring competent authority approval. The paper explains how the ageing aspect may be included in the safety evaluation process and the management system measures and will give an outlook for the future guidance material. T2 - 20th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 22) CY - Juan-Les-Pins, Antibes, France DA - 11.06.2023 KW - Typ KW - Radioactive material KW - Non-approved PY - 2023 SP - 1 EP - 8 AN - OPUS4-57703 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schubert, Sven T1 - Introduction of the German Ageing Management Guide for Packages for Transport of Radioactive Materials – BAM-GGR 023 N2 - BAM-GGR 023 was published in June 2022 BAM-GGR 023 gives guidance to applicants regarding ageing management for competent authority approved package designs Ageing management with evaluation of ageing mechanisms according to para 613A of IAEA SSR-6 (Rev. 1) and their effects are part of the general management system. Essential items are: AMS (systemic-related), AMP (package design-related) and AMD (package-related) There are different requirements for organization and extent of ageing management depending on type of use There are also different requirements for ageing evaluation depending on type of use for packaging/package, classification of components and their accessibility and replaceability T2 - PATRAM22 CY - Juan-les-Pins, France DA - 11.06.2023 KW - Package KW - Ageing KW - Mechanism KW - Management KW - Guide PY - 2023 AN - OPUS4-57821 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Karapanagiotis, Christos T1 - Towards predictive maintenance of hydrogen pressure vessels based on multi-sensor data fusion and digital twin modeling N2 - Hydrogen pressure vessels are among the most essential components for reliable hydrogen technology. Under current regulations, a mostly conservative strategy is employed, restricting the usage time of hydrogen pressure vessels without providing information on the real remaining lifetime. During the service life, pressure vessels are inspected periodically. However, no established method that can provide continuous monitoring or information on the remaining safe service life of the vessel. In this paper, we propose a sensor network for Structural Health Monitoring (SHM) of hydrogen pressure vessels where data from all sensors are collected and centrally evaluated. Specifically, we integrate three different SHM sensing technologies namely Guided Wave ultrasonics (GW), Acoustic Emission testing (AT), and distributed Fiber Optic Sensing (FOS). This integrated approach offers significantly more information and could therefore enable a transition from costly and time-consuming periodic inspections to more efficient and modern predictive maintenance strategies, including Artificial Intelligence (AI)-based evaluation. This does not only have a positive effect on the operational costs but enhances safety through early identification of critical conditions in the overall system in real-time. We demonstrate an experimental set-up of a lifetime test where a Type IV Composite Overwrapped Pressure Vessel (COPV) is investigated under cyclic loading instrumented with AT, FOS, and GW methods. We acquired data from the sensor network until the pressure vessel failed due to material degradation. The data collected using the three different SHM sensor technologies is planned to be evaluated individually, using data fusion, and AI. In the future, we aim to integrate the measurement setup into a hydrogen refueling station with the data stream implemented into a digital signal processing chain and a digital twin. T2 - 11th European Workshop on Structural Health Monitoring CY - Potsdam, Germany DA - 10.06.2024 KW - Hydrogen KW - Ultrasonic guided waves KW - Fiber optic sensors KW - Acoustic emission KW - Machine learning KW - Pressure vessels KW - Structural health monitoring PY - 2024 AN - OPUS4-60277 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Karapanagiotis, Christos T1 - Structural health monitoring of hydrogen pressure vessels using distributed fiber optic sensing N2 - We report on distributed fiber optic sensing-based monitoring of hydrogen composite overwrapped pressure vessels (COPV) to simultaneously increase the operational lifespan and mitigate maintenance costs. Our approach represents, to the best of our knowledge, the first application of distributed fiber optic sensing for COPV Type IV monitoring, where the sensing fibers are attached to the surface, rather than integrated into the composite material. Specifically, we attach an optical fiber of 50 m to the pressure vessel's surface, covering both the cylindrical and dome sections. We note that our fiber optic sensing technique relies on swept wavelength interferometry providing strain information along the entire length of the optical fiber with high spatial resolution even at the millimeter scale. When the vessel is pressurized, the sensing optical fiber shows a linear strain response to pressure at every position along the fiber. After thousands of load cycles, the vessel finally fails with the optical fiber detecting and precisely localizing the damage in the vessel’s blind dome area. Furthermore, we discuss the potential of state-of-the-art signal processing methods and machine learning for advancing predictive maintenance. This could reduce the number of regular inspections, mitigate premature maintenance costs, and simultaneously increase the vessel’s remaining safe service life. We believe that the structural health monitoring of hydrogen pressure vessels with fiber optic sensors can enhance trust in hydrogen technology contributing to the energy transition in the future. T2 - 11th European Workshop on Structural Health Monitoring CY - Potsdam, Germany DA - 10.06.2024 KW - Hydrogen KW - Composites KW - Pressure vessels KW - Fiber optic sensors KW - Machine learning KW - Structural health monitoring PY - 2024 AN - OPUS4-60275 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wosniok, Aleksander T1 - Distributed fiber optic strain sensing for structural health monitoring of 70 MPa hydrogen vessels N2 - We report on the development and testing of 70 MPa hydrogen pressure vessels with integrated fiber optic sensing fibers for automotive use. The paper deals with the condition monitoring of such composite pressure vessels (CPVs) using the optical backscatter reflectometry (OBR) applied for a distributed fiber optic strain sensing along fully integrated polyimide-coated single-mode glass optical fiber (SM-GOF). The sensing fibers were embedded into the vessel structure by wrapping them over the polymer liner during the manufacturing process of the carbon fiber reinforced polymer (CFRP). Detecting local strain events by the integrated fiber optic sensors can be an opportunity for monitoring the material degradation of CPVs under static and cyclic loading. T2 - 11th European Workshop on Structural Health Monitoring CY - Potsdam, Germany DA - 10.06.2024 KW - Fiber optic sensor KW - Distributed strain sensing KW - Composite pressure vessel KW - Structural health monitoring KW - Fiber-reinforced plastics PY - 2024 AN - OPUS4-60307 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Heimann, Jan A1 - Yilmaz, Bengisu A1 - Charmi, Amir A1 - Duffner, Eric A1 - Schukar, Marcus A1 - Prager, Jens T1 - Structural Health Monitoring (SHM) for continuous monitoring of hydrogen pressure vessels N2 - While hydrogen is one of the most promising energy carriers, the safety of hydrogen storage technology remains one of the most important factors for technological and societal approval. While the engineering safety factors of the pressure vessels are kept high, the periodic inspection and the limited lifetime are making the application very costly considering manpower, time, money, and material waste. The development of an integrated structural health monitoring system can allow an easy transition from the current situation to cost-effective predictive maintenance. Hence, we propose to integrate three different SHM systems into hydrogen pressure vessels, namely guided wave ultrasonics, acoustic emission, and fibre optic sensing, to continuously monitor the condition and integrity. In this work, we evaluated the condition of a Type IV composite overwrapped pressure vessel using ultrasonic guided wave propagation. We mounted fifteen piezo-electric wafers on the composite cylinder by shaping three rings containing five sensors each. We acquired data from the sensor network following different boundary conditions with artificial damages on the selected locations. The data were evaluated with guided wave tomography techniques using ultrasonic features (amplitude, frequency, etc.) as well as artificial intelligence (AI). The results suggest that both traditional guided wave fusion techniques and AI-based characterization methods can detect artificial damages. In future work, it is planned to integrate acoustic emission and fibre optic sensing. Moreover, the measurement and the test results will be implemented into a digital twin to derive trends and make predictions on the damage propagation as well as the remaining useful lifetime. This work has received funding from German Ministry of Economic Affairs and Climate Actions within the QI-Digital initiative (www.qi-digital.de). T2 - SCHALL 23 CY - Wetzlar, Germany DA - 21.03.2023 KW - Structural Health Monitoring KW - Ultrasonic Guided Waves KW - Composite Overwrapped Pressure Vessel KW - Hydrogen PY - 2023 AN - OPUS4-58026 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Popiela, Bartosz T1 - PhD Topic 5: Summer School Update. Influence of manufacturing process related residual stresses in wound composite material on the operational safety of H2 pressure vessels N2 - The presentation is an update on the progress of the PhD Project. It focuses on the residual stress induction during the winding process of type 4 composite pressure vessels. Moreover, an overview of the experimental study is given, with focus on the manufacturing of composite pressure vessels. T2 - Summer School 2023 - BTU-BAM Graduate School "Trustworthy Hydrogen" CY - Berlin, Germany DA - 04.09.2023 KW - Residual stress KW - Composite KW - Pressure vessel KW - Hydrogen PY - 2023 AN - OPUS4-58239 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Popiela, Bartosz T1 - Non-Destructive Testing of Type 4 Composite Pressure Vessels N2 - Non-Destructive Testing (NDT) of type 4 composite pressure vessels can be seen as key to better understanding the behaviour of the composite structure and the impact of the manufacturing process on its quality. In this presentation, NDT methods used in the “Trustworthy Hydrogen” project are introduced. A brief discussion of the observed phenomena is provided. T2 - Visit of a delegation from Korea Fire Institute (KFI) CY - Berlin, Germany DA - 24.06.2024 KW - Composite KW - Pressure vessel KW - Non-destructive testing PY - 2024 AN - OPUS4-60401 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Bernardy, Christopher A1 - Konert, Florian A1 - Popiela, Bartosz A1 - Sarif, Raduan T1 - H2Safety@BAM: Competence Center for safe hydrogen technologies N2 - Presentation of the competence center H2Safety@BAM at the European PhD Hydrogen Conference 2024 in Ghent, Belgium. T2 - European PhD Hydrogen Conference 2024 (EPHyC2024) CY - Ghent, Belgium DA - 20.03.2024 KW - H2safety KW - Hydrogen KW - Safety KW - Competence center PY - 2024 AN - OPUS4-59756 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Ghaznavi, Ali T1 - Damage monitoring of hydrogen composite pressure vessels using acoustic emission technique and machine learning N2 - A good understanding of the structural stability of hydrogen composite overwrapped pressure vessels (COPV) is important for the cost-effective design and safe operation of hydrogen storage systems. Acoustic emission (AE) monitoring is a non-destructive method sensitive to microstructural damages such as e.g. fiber breakage, and matrix cracking in COPVs. This study proposes a novel approach for damage monitoring by integrating acoustic emission techniques with machine learning (ML) algorithms to classify and predict damage types in COPVs. However, training accurate classification models requires extensive labeled datasets, which are very challenging to generate due to the nature of AE signal data and the lack of in-situ observations of microscopic failures in COPVs. Our research overcomes this limitation by automating the labeling process of AE signal data for different COPVs using unsupervised ML methods. The most representative features were extracted and then selected from recorded AE signals. Different unsupervised clustering algorithms were utilized based on various extracted feature combinations. The most stable clustering result was achieved and later used as appropriate labels for training classification algorithms. A deep neural network-based deep learning (DL) architecture was used to train discriminative models on AE data, identify patterns, and classify damage types into different classes with improved accuracy and speed for each COPV. Results demonstrate the potential of the proposed combined deep learning approach to train predictive models in identifying failure patterns. The trained models based on individual COPVs show high training, validation, and test accuracy for unseen datasets and offer enhanced predictive capabilities by following advanced DL techniques compared to traditional monitoring methods. The proposed method highlights its potential to improve the efficiency and safety of hydrogen storage systems. T2 - SCHALL 25 CY - Dresden, Germany DA - 26.03.2025 KW - Acoustic Emission KW - Composite Overwrapped Pressure Vessels, KW - Damage monitoring KW - Machine Learning KW - Deep Learning KW - Deep Neural Network KW - Sequential Neural Network PY - 2025 AN - OPUS4-62915 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Mair, Georg W. T1 - Hydrogen as Energy carrier – Contributions to safety assessement of storage systems N2 - The introduction reflects the political background in Germany and worldwide concerning hydrogen as energy carrier. This leads to available hydrogen strategies and the reaction of BAM by launching the competence centre H2Safety@BAM. Fokus is set on the competence area TestCert, the special role of the division “Safety of Gas Storage Systems” there and its increasing success in research activities. The main part explains the needs for a risk-controlled market ramp-up concerning hydrogen products and appropriate measures being under development in division 3.5: risk control, tools for consequence estimation and limitation, probabilistic assessment of end of safe life, the efficiency assessment and optimization of current regulations, the structural health monitoring (SHM) with necessary improvement of measures for quality management in the digital world of safety assessment. Last but not least, the wide range of full-scale testing and simulation of worst-case scenarios is explained. T2 - Colloquium zu Antrittsvortrag Leitung Sicherheit von Gasspeichern CY - Online meeting DA - 20.08.2021 KW - H2Safety@BAM KW - Markthochlauf KW - Lebensdauervorhersage KW - statistische Bewertung KW - Risikosteuerung PY - 2021 AN - OPUS4-54617 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Mair, Georg W. T1 - Salvage pressure receptacles - Technical background N2 - The presentation reflects the questions that have been raised by member states and NGOs. As background information details on the question how to choose a suitable salvage pressure receptacle (SPR) are provided. This leads to the need for deleting the volume limitation for SPRs and to the discussions in 2014 and 2016 on this issue. As an adequate substitution for deleting the volume limit for SPRs it is proposed to limit the pressure receptacles to be stored in by a maximum pressure-volume-value of 1.5 Mio bar-litres. After some explanations to standardisation projects currently also tackling this pV-limit, some risk-based safety criteria for a limitation are mentioned with the focus of the consequence level and the general avoidance of catastrophic worst case scenarios. T2 - 57th session of TDG Sub-Committee CY - Online meeting DA - 30.11.2020 KW - Salvage pressure receptacle KW - Consequence KW - Catastrophe KW - Compressed gas PY - 2020 AN - OPUS4-53161 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Mair, Georg W. A1 - Günzel, Stephan T1 - Der systematische Einsatz der Monte-Carlo-Simulation in der Normung N2 - Im Rahmen der Energiewende erfahren viele Produkte einen umfassenden Markthochlauf. Hierzu müssen neue Technologien entwickelt oder bestehende in kurzer Zeit angepasst werden. Das macht sie besonders anfällig für Zwischenfälle und nachfolgenden Akzeptanzverlust. Zu vermeidende Zwischenfälle hängen oft von den deterministischen Mindestanforderungen in Norm und Recht ab, die erfahrungsbasiert entwickelt wurden. Hier ist die Monte-Carlo-Simulation eine wertvolle Hilfe. Sie erlaubt, auf der Basis von wenigen ermittelten Daten zu bewerten, welche statistische Wirkung aus einer Mindestanforderung resultiert und was angepasst werden muss, um die im Zuge eines Markthochlaufes relevanten Zielgrößen zu erreichen. Ein Verfahren, das im Rahmen der Normung erlaubt, die Wirkung einer Mindestanforderung auf die Ausfallwahrscheinlichkeit zu bewerten, wird zurzeit im Rahmen des Projektes DIN/TS 19472 unter dem NA 016-00-03 AA ausgearbeitet und hier vorgestellt. KW - Wasserstoffspeicher KW - Wirtschaftlichkeit KW - Markthochlauf KW - Zufallsgenerator KW - Normalverteilung KW - Sicherheit PY - 2025 SN - 0722-2912 VL - 2025 IS - 4 SP - 72 EP - 75 CY - Berlin AN - OPUS4-63807 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Mair, Georg W. T1 - Blasting Splinter Protection Tower and Focus Points in Research and RCS N2 - Firstly, the modular fragmentation protection components are presented and the concept of the currently realised, cube-shaped tower is shown. This temporary tower was exposed to various explosive loads up to the level of 10 kg TNT. The orthogonality of the pressure effect is clearly recognisable. The pressure peak is reduced by 15% in the direction of the openings and the wind effect is reduced by around 40%. Both effects are greater in the direction of the diagonals. Another important point is risk management during the H2 market ramp-up. The aspects of specifically controlled reliability, consequence control and also new technologies, e.g. for the insulation of cryogenic storage facilities, are explained. Another aspect is analysing the effect of minimum requirements in standards according to risk-based criteria. Monte Carlo simulation is used for this purpose. Efficient, random sample-based recurring tests and optimised and consistent data availability are further aspects. Conclusions:  Usage of hydrogen needs careful safety precautions and reliable equipment  Worst case scenarios must get prevented but possible consequences should be taken into account, also.  For the market rump-up new approaches are necessary for keeping the system running and for ensuring an adequate safety level: - probabilistic evaluation of components - improvement of NDT-methods - digital tools for data administration and sharing - simulation of effectiveness of minimum requirements in RCS - new storage concepts e.g. for LH2 T2 - 5th Germany-Korea Hydrogen Conference CY - Halle (Saale), Germany DA - 22.10.2024 KW - Risk control KW - Hydrogen transport KW - DCC KW - DCoC KW - DPP KW - TNT PY - 2024 AN - OPUS4-61440 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Mair, Georg W. T1 - Das Potenzial des SHM an Gasspeichern- Zulassung & Betrieb N2 - Der Vortrag beginnt mit dem Ziel einer Prognose der Ausfallwahrscheinlichkeit einer Population oder eines Individuums, die laufend auf der Basis von SHM (Zustandsüberwachung von Strukturen) aktualisiert wird. Zunächst wird die Rolle des Rechts und der Rechtsrahmen für die Prüfung von Gasspeichern nach Norm dargestellt. Der Bedarf an technologischen Fortschritten wird mit Bezug zur Prüfpraxis und dem zugehörigen Ressourcenbedarf, wie auch den Defiziten der vorgeschriebenen Prüfungen im Kontext des Markthochlaufes Wasserstoff erläutert. Der Lösungsansatz ist zweistufig und basiert auf dem systematischen Ersatz der Wasserdruckprüfung in Begleitung von SHM (insbesondere AT/SEA) und im zweiten Schritt auf der Kombination des probabilistischen Ansatzes der BAM (GGR 021) mit einer weiterentwickelten SHM. Diese Kombination von ZfP und Probabilistik würde zum einen die Aussagekraft in der betrieblichen Überwachungsmaßnahmen erheblich erhöhten und gleichzeitig eine erheblich Aufwandsreduktion sowohl bzgl. Stillstandszeiten, Kosten und Lebensdauer bieten. ‒ In vielen Fällen sind die Prüfverfahren in Norm und Recht geregelt. ‒ Der Markthochlauf fordert neue Ansätze, um die erforderliche Quantität (mehr und größere Speicher) und Qualität (hohe Zuverlässigkeit) bieten zu können. ‒ Für stationäre und mobile Großspeicher bleibt nur eine permanente Onlineüberwachung ‒ Für Speicher in großer Stückzahl sind stichprobenbasierte Ansätze als permanenter Messung oder als wiederkehrende Prüfung möglich und sinnvoll. ‒ Die größte Aufgabe liegt aber darin, die ZfP-Methoden weiterzuentwickeln und deren Aussagekraft und –genauigkeit zu schärfen. T2 - 37. Fachausschuss Zustandsüberwachung (FA SHM) CY - Berlin, Germany DA - 15.10.2024 KW - Wasserstoffspeicher KW - Probabilistik KW - Schallemissionsanalyse KW - Wiederkehrende Prüfung KW - Lebensdauerüberwachung KW - BAM-GGR 021 PY - 2024 AN - OPUS4-61362 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Mair, Georg W. T1 - DIN TS 19472 - Das Monte-Carlo-Experiment in der Normung N2 - Der Foliensatz erläutert den Denkansatz, die Normstruktur und eine evtl. Programmstruktur für das Normungsprojekt TS 19472. Das Spannungsfeld heutiger Normung basiert auf den immer komplexer vorhersagbaren Eigenschaften Fertigungsstreuung und Bauteilalterung. Während man die Bauteilalterung mit neuen Verfahren der zerstörungsfreien Prüfung usw. betriebsbegleitend bewertet, kann der Fertigungsstreuung mit ihrem Einfluss auf die zu erwartenden Ausfälle nur mit probabilistischen Mitteln direkt begegnet werden. Ein probabilistischer Zulassungsansatz würde aber zu enorm komplexen Bewertungsprozessen führen, die wiederum in ihrer Feldanwendung komplexer zu bewerten und damit ohne langjährige Erfahrung fehleranfälliger als deterministische Verfahren sein dürften. Um diesen Konflikt aufzulösen, bietet es sich zumindest übergangsweise an, den probabilistischen Ansatz nicht unmittelbar in der Zulassung anzuwenden, sondern die in der Breite vertrauten, deterministischen Zulassungsvorschriften auf ihre Wirkung zu überprüfen und ggf. zu optimieren. Hierzu kann die systematisch numerische Wiederholung eines sog. Monte-Carlo-Experiments eingesetzt werden. Hierzu wird für verschiedene Parametersätze, die die Grenze noch akzeptierter Ausfallwahrscheinlichkeit beschreiben, das nachfolgend beschriebene, numerische Experiment wiederholt ausgeführt. Die Wiederholung erfolgt in definierten Variationsschritten über das gesamte Spektrum praktisch relevanter Streuungswerte. Jedes Experiment besteht somit aus der Generierung einer Grundgesamtheit zu dem für den jeweiligen Variationsschritt spezifischen Parametersatz. Danach wird die Grundgesamtheiten in Zufallsstichproben einer definierten Größe aufgeteilt und jede simulierte Stichprobe auf deren Akzeptanz gemäß dem betrachteten Akzeptanzkriterium in der Norm analysiert. Daraus resultiert für jede Grundgesamtheit aus dem Einzelexperiment die Wahrscheinlichkeit zur Annahme einer Stichprobe . Mit der systematischen Wiederholung des Experiments ist der Verlauf  der Akzeptanzwahrscheinlichkeit bekannt, mit der eine grenzwertige Eigenschaft nach einem deterministischen Akzeptanzkriterium noch angenommen werde würde und damit auch ein ungenügendes Baumuster aufgrund der jeweils betrachteten Eigenschaft nicht abgelehnt werden würde. T2 - Sitzung des NA 016-00-03-03 AK „Composite-Flaschen“ des DIN-Normenausschuss Druckgasanlagen (NDG) CY - Berlin, Germany DA - 13.02.2025 KW - Wasserstoffspeicher KW - Probabilistik KW - Markthochlauf KW - Zufallsgenerator KW - Sicherheit PY - 2025 AN - OPUS4-62907 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Popiela, Bartosz T1 - Performance of Type 4 Composite Pressure Vessels: Impact of Residual Stress State N2 - This presentation summarizes the results of an experimental study on slow burst tests, involving two pressure vessel designs with different residual stress states. The significant performance differences between the two designs highlight the critical role of residual stress state in filament-wound structures T2 - Composites Research Seminar at the Innovative Design and Integrated Manufacturing Lab, Seoul National University CY - Seoul, South Korea DA - 22.11.2024 KW - Composite KW - Pressure vessel KW - Residual stresses KW - Burst test KW - Filament winding PY - 2024 AN - OPUS4-61734 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Popiela, Bartosz T1 - BAM 3.5 and Trustworthy Hydrogen: Experimental Investigation of Type 4 Composite Pressure Vessels N2 - The presentation provided a brief introduction to Division 3.5 at BAM and detailed an experimental study of composite pressure vessels as part of the 'Trustworthy Hydrogen' project. It included an in-depth analysis of slow burst test evaluations. T2 - Lab Seminar of IDIM SNU CY - Seoul, South Korea DA - 26.11.2024 KW - Composite KW - Pressure vessel KW - Residual stresses KW - Burst test PY - 2024 AN - OPUS4-61779 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rolle, Annette A1 - Wille, Frank A1 - Komann, Steffen A1 - Neumann, Martin T1 - Qualification Procedure for Seal Designs for Spent Fuel Transport and Storage Cask Containments N2 - The seal is a key component of the containment and closure system of transport and storage casks for radioactive material. It is a major contributor to ensuring compliance with the acceptable limits for activity release according to IAEA regulations. The requirements for a safe seal performance are high, accordingly. Every new seal design intended for use in the containment of a transport cask for radioactive material passes a qualification process in Germany. The qualification process is supervised by BAM as German competent authority for mechanical, thermal and containment assessment of packages requiring design approval. The closure system including the seal shall be able to withstand the corrosive, mechanical and thermal loads associated with routine, normal and accident conditions of transport according to the IAEA regulations without losing the required sealing function. Metal seals of the Helicoflex® type are often used to ensure required package leak tightness for both storage and transport, including transport after long term interim storage. The poster will provide an overview of requirements during a seal qualification process on the example of a Helicoflex® type metal seal. T2 - 21st International Symposium on the Packaging and Transportation of Radioactive Materials, PATRAM 2025 CY - San Antonio, Texas , US DA - 27.07.2025 KW - Spent fuel transport KW - Seals KW - Radioactive KW - Containment PY - 2025 SP - 1 EP - 5 AN - OPUS4-63911 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rolle, Annette T1 - Qualification Procedure for Seal Designs for Spent Fuel Transport and Storage Cask Containments N2 - The seal is a key component of the containment and closure system of transport and storage casks for radioactive material. It is a major contributor to ensuring compliance with the acceptable limits for activity release according to IAEA regulations. The requirements for a safe seal performance are high, accordingly. Every new seal design intended for use in the containment of a transport cask for radioactive material passes a qualification process in Germany. The qualification process is supervised by BAM as German competent authority for mechanical, thermal and containment assessment of packages requiring design approval. The closure system including the seal shall be able to withstand the corrosive, mechanical and thermal loads associated with routine, normal and accident conditions of transport according to the IAEA regulations without losing the required sealing function. Metal seals of the Helicoflex® type are often used to ensure required package leak tightness for both storage and transport, including transport after long term interim storage. The poster will provide an overview of requirements during a seal qualification process on the example of a Helicoflex® type metal seal. T2 - 21stInternational Symposium on the Packaging and Transportation of Radioactive Materials, PATRAM 2025 CY - San Antonio, Texas , US DA - 27.07.2025 KW - Spent fuel transport KW - Seals KW - Raqdioactive KW - Containment PY - 2025 AN - OPUS4-63909 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Maiwald, Michael A1 - Soruco Aloisio, Ricardo A1 - Meyer, Klas A1 - Klaus, Christian T1 - Auf dem Weg zu einer digitalen Qualitätsinfrastruktur - Eine Labor-Testplattform für die Integration von Sensoren und Messgeräten N2 - Um die internationale Spitzenposition deutscher Unternehmen der Prozessindustrie auch in Zukunft sicher zu stellen, müssen die Unternehmen ihre Prozesse und Geschäftsabläufe digitalisieren und gemeinsam mit der Forschung innovative neue Methoden, Apparate, Anlagen, Sensoren und Automatisierungstechnik sowie Datenkonzepte entwickeln. All dies erfordert den Aufbau neuer Fähigkeiten, Investition in Talente, interdisziplinäre Kommunikation zwischen verschiedenen Personen und Abteilungen und eine Bereitschaft zur Veränderung. KW - QI-Digital KW - Wasserstofftankstelle KW - IT-OT-Testplattform KW - Prozessindustrie PY - 2023 VL - 67 IS - 9 SP - 20 EP - 23 PB - Wiley-VCH CY - Weinheim AN - OPUS4-58461 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Soruco Aloisio, Ricardo A1 - Klaus, Christian T1 - Auf dem Weg zu einer digitalen Qualitätsinfrastruktur - Use Case Wasserstofftankstelle N2 - Im Rahmen der von der BAM und anderen Partnern ins Leben gerufenen Initiative „Digitale Qualitätsinfrastruktur“ liegt der Fokus u.a. auf der Entwicklung von neuen Zertifizierungsworkflows. Dabei ist eine besondere Bedeutung dem Zusammenführen von Operational Technology (OT) und Informationstechnik (IT) beizumessen. Zur Datenintegration aus der Sensor-Feldebene einer Versuchs-wasserstofftankstelle wurde eine solche Infrastruktur zunächst in einer Laborumgebung aufgebaut. T2 - Hannover Messe 2024 - Speakers Corners CY - Hannover, Germany DA - 23.04.2024 KW - IT KW - OT KW - Infrastruktur KW - Datenintregration KW - VPN KW - Verwaltungsschale KW - Open Source KW - Software PY - 2024 AN - OPUS4-59930 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias A1 - Monavari, Mehran A1 - Bertovic, Marija A1 - Wille, Frank T1 - AI-driven Documentation Analysis for Safety Assessment of Packages with Hazardous Goods 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 SP - 1 EP - 9 PB - Kontec Gesellschaft für technische Kommunikation GmbH CY - Dresden AN - OPUS4-64154 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 - Eiben, Mario T1 - Die Aufgaben der BAM im Gefahrgutbereich - ein Überblick N2 - Die BAM ist eine der zuständigen Behörden im Gefahrgutbereich in Deutschland und nach der Gefahrgutverordnung Straße, Eisenbahn und Binnenschifffahrt (GGVSEB) und der Gefahrgutverordnung See (GGVSee) für diverse Aufgaben zuständig, wie z. B. große Teile der Klassifizierung gefährlicher Güter, die Verwendung, Prüfung, und Zulassung von Gefahrgutverpackungen oder auch die Verwendung, den Bau und die Prüfung von Gefahrguttanks. Sie berät die Bundesregierung bei der Ausrichtung der Gefahrgutpolitik durch Mitarbeit im Ständigen Ausschuss Gefahrgutbeförderung (AGGB) des Gefahrgut-Verkehrs-Beirates beim BMV und wirkt nach dem Erlass über die BAM im Einvernehmen mit dem BMWK in nationalen und internationalen Regel setzenden Gremien und Normungsgremien mit. Damit leistet sie einen wertvollen Beitrag zur Sicherheit im Gefahrgutbereich. T2 - 35. Münchner Gefahrgut-Tage CY - Munich, Germany DA - 25.05.2025 KW - Gefahrgut KW - Zuständige Behörde KW - GGVSEB KW - GGVSee KW - AGGB KW - Normung PY - 2025 AN - OPUS4-64051 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Graeber, Gustav T1 - Paste-like interlayers in alkali-metal battery anodes N2 - Giving an introduction to high-temperature batteries with molten alkali-metal anodes and solid electroyltes. Presenting the research on alkali-metal tensiometry and the study about wetting interactions between liquid alkali-metal alloys and porous carbon hosts. T2 - AG Christina Roth Seminar CY - Bayreuth, Germany DA - 16.07.2025 KW - Battery PY - 2025 AN - OPUS4-64069 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Graeber, Gustav T1 - Graeber Lab for Energy Research at Tag der Chemie in Adlershof N2 - Highlighting recent progress in the Graeber Lab for Energy Research in the areas of alkali-metal tensiometry, alkali-metal anodes in contact with solid electrolytes, sulfur cathodes and solid electrolyte synthesis. T2 - Tag der Chemie in Adlershof 2025 CY - Berlin, Germany DA - 03.07.2025 KW - Batterie PY - 2025 AN - OPUS4-64068 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Graeber, Gustav T1 - Paste-like alkali-metal anodes in contact with solid electroytes N2 - Explaining the motivation of the BMFTR ANaBatt project. Presenting recent advances in alkali metal tensiometry and characterization of alkali-metal wetting in porous carbon materials via X-ray computed tomography. T2 - Sodium Battery Symposium 6 CY - Dresden, Germany DA - 03.09.2025 KW - Battery PY - 2025 AN - OPUS4-64070 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - THES A1 - Lengas, Nikolaos T1 - Parameter study of impact targets in the drop test of packaging for dangerous goods N2 - Within the transportation chain, impact loading of dangerous goods packagings can happen. Thus, a package’s resistance against mechanical damage needs to be assessed. In the context of dangerous goods transport, drop tests are used for damage assessment as a part of packaging approval. Hence, a horizontal, flat unyielding surface must be provided to ensure maximum damage on impact and univocal test results. Leading adopted regulations like ADR/RID reference ISO 2248 to specify the requirements for the impact surface. The main requirement states that the impact surface must belong to an impact target with a mass at least 50 times higher than that of the heaviest package to be tested. However, many manufacturers in Germany, especially manufacturers of fibreboard boxes, do not have their own testing device with the required mass ratio for the drop test. Furthermore, the necessity of requirement revision has been addressed at UN level. It is unclear if mass ratio is the decisive criterion or if alternative design parameters can be defined to guarantee rigidity of the impact surface. The focus of the research reported in this thesis lays in the development and implementation of an analysis and testing concept for a comprehensive investigation of impact targets in drop testing. To this end, an experimental setup consisting of regulation compliant model impact targets is used in drop tests with two packaging types of significantly different mechanical properties. The variation of drop test parameters, such as the mass ratio, provides new insights into their respective significance in the drop test outcome. In addition, experimental findings are enhanced with numerical Finite-Element (FE) analyses to propose new improved criteria which incorporate all relevant influencing factors. In this way, firstly, critical impact target designs can be identified, and secondly, the kinetic energy of a real impact target in a drop test can be reliably approximated and compared to the respective theoretical threshold derived from a worst-case assumption. Thus, the rigid mass ratio currently specified in ISO 2248 can be regarded obsolete. The results of this work are highly beneficial for industrial application since they form the basis for introducing a standardized method for evaluating impact targets, replacing the 50 times mass ratio requirement. This would enable manufacturing and testing facilities to ensure a uniform level of safety assessment and to avoid the considerably high construction costs of impact targets with mass ratio of 1:50 in relation to packaging gross masses of several hundred kilograms. Hence, to make the results attained under laboratory conditions usable in practical application, preliminary investigations of the mechanical response of installed impact targets are conducted. For this purpose, important factors such as the interaction between impact target and ground in dynamic impact testing conditions are examined using validated FE models to establish an evaluation method. The investigations aim to create the basis for the revision of ISO 2248 and to define a standardized reference method for impact target characterization. KW - Drop test KW - Structural dynamics KW - Dangerous goods packaging KW - Mass ratio KW - Finite-element-method PY - 2025 DO - https://doi.org/10.14279/depositonce-24333 SP - 1 EP - 189 CY - Berlin AN - OPUS4-64090 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Böttcher, Nils T1 - Neue Brandlasten - neue Aufgaben für die Feuerwehr N2 - Die zunehmende Verbreitung von elektrischen Energiespeicher und Flüssiggasspeicher ermöglichen eine erfolgreiche Transition zu einer CO2 neutralen Energieversorgung. Allerdings bringen neue Energiespeicher mit hohen Energiedichten auch zusätzliche Herausforderungen für die Feuerwehr der Zukunft mit sich. Insbesondere Lithiumbatterien können bei falscher Handhabung zum thermischen Durchgehen führen. Dies kann katastrophale Auswirkungen mit sich bringen. Der Umstieg auf Wasserstoff als neuen Energieträger birgt ebenfalls zusätzliche Risiken und Unsicherheiten für die Einsatzkräfte. Daher ist die Lageeinschätzung und der möglichen Gefahren am Einsatzort für die Feuerwehrkräfte essenziell notwendig. T2 - Transfer on fire CY - Ludwigsfelde, Germany DA - 14.08.2024 KW - Lithiumbatterien KW - Sicherheit von Energieträgern KW - Gefahrguttransport PY - 2024 AN - OPUS4-61502 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Böttcher, Nils T1 - Untersuchungen für den Transport gekühlter Batterien Vorstellung des Nageltests N2 - Im Zusammenhang mit den Untersuchungen zu den Möglichkeiten von gekühlten Transporten von Lithiumbatterien werden unterschiedliche Zerstörungsmethoden vorgestellt und diskutiert. Insbesondere wird dabei das neu entwickelte Nageltool und die vorläufigen Untersuchungen für den Einfluss von Ultratiefkühlung auf unbeschädigte Lithiumbatterien vorgestellt. T2 - ERFA-Verpackungen CY - Berlin, Germany DA - 22.09.2022 KW - Lithiumbatterien KW - Thermal Runaway KW - Gefahrguttransport KW - Nageltest PY - 2022 AN - OPUS4-56759 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Böttcher, Nils T1 - Untersuchungen für den Transport gekühlter Batterien Vorstellung des Nageltests N2 - Im Zusammenhang mit den Untersuchungen zu den Möglichkeiten von gekühlten Transporten von Lithiumbatterien werden unterschiedliche Zerstörungsmethoden vorgestellt und diskutiert. Insbesondere wird dabei das neu entwickelte Nageltool vorgestellt. T2 - Fachkonferenz Lithiumbatterien CY - Goettingen, Germany DA - 28.04.2022 KW - Lithiumbatterien KW - Thermal Runaway KW - Gefahrguttransport KW - Nageltest PY - 2022 AN - OPUS4-56758 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Zhang, Wuyi A1 - Mehmood, Asad A1 - Ali, Ghulam A1 - Liu, Hui A1 - Chai, Liyuan A1 - Wu, Jun A1 - Liu, Min T1 - Nickel Nanocluster-Stabilized Unsaturated Ni–N3 Atomic Sites for Efficient CO2-to-CO Electrolysis at Industrial-Level Current N2 - Unsaturated Ni single-atom catalysts (SACs), Ni-Nx (x=1,2,3), have been investigated to break the conventional Ni-N4 structural limitation and provide more unoccupied 3d orbitals for CO2 reduction reaction (CO2RR) intermediates adsorption, but their intrinsically low structural stability has seriously hindered their applications. Here, we developed a strategy by integrating Ni nanoclusters to stabilize unsaturated Ni-N3 atomic sites for efficient CO2 electroreduction to CO at industrial-level current. Density Functional Theory (DFT) calculations revealed that the incorporation of Ni nanocluster effectively stabilizes the unsaturated Ni-N3 atomic sites and modulates their electronic structure to enhance the adsorption of the key intermediate *COOH during CO2RR. Guided by these insights, we prepared an optimal composite catalyst, Ni6@Ni-N3, which features a Ni6N6 nanocluster surrounded by six Ni-N3 single atoms sites, through low-temperature pyrolysis. The morphology and coordinative structure of Ni6@Ni-N3 were confirmed by an aberration-corrected transmission electron microscope (AC-TEM) and X-ray absorption spectroscopy (XAS). As a result, Ni6@Ni-N3 demonstrated a remarkably high CO Faradaic efficiency (FECO) of 99.7 % and a turnover frequency (TOF) of 83984.2 h−1 at 500 mA cm−2 under −1.15 VRHE, much better than those of Ni-N4 with a lower FECO of 86 % at 100 mA cm−2 and a TOF of 39309.9 h−1under identical potential. XAS analyses of Ni6@Ni-N3 before and after long-term CO2RR testing confirmed the excellent stability of its coordinative environment. This work highlights a generalizable approach for stabilizing unsaturated single-atom catalysts, paving the way for their application in high-performance CO2RR. KW - Electrochemical CO2 conversion KW - Single atom catalysts KW - CO2 electrolysis PY - 2025 DO - https://doi.org/10.1002/anie.202424552 SN - 1521-3773 VL - 64 IS - 13 SP - 1 EP - 10 PB - Wiley-VCH CY - Weinheim AN - OPUS4-62926 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Graeber, Gustav T1 - Batterieforschung an der Humboldt-Universität zu Berlin - Selbstvorstellung beim KLiB N2 - Selbstvorstellung der Batterieforschungsaktivitäten der HU Berlin in Kooperation mit lokalen Partnern wie der BAM im Rahmen eines Netzwerktreffens. Fokus auf die Forschung in der Arbeitsgruppe Graeber zu Festkörperbatterien und der Arbeitsgruppe Adelhelm zu Natrium-Ionen-Batterien. T2 - KLiB Netzwerktreffen CY - Frankfurt, Germany DA - 26.03.2025 KW - Batterie PY - 2025 AN - OPUS4-63350 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Graeber, Gustav T1 - Graeber Lab for Energy Research - Overview N2 - Vorstellung der Forschungsaktivitäten der AG Graeber an der HU Berlin und an der BAM. Diese beinhalten die Erforschung grundlegender Benetzungsphänomene von Alkalimetallen, deren Anwendung in Festkörperbatterien mit pastenartigen Alkalimetallanoden, die Erforschung von Schwefelkathoden, die Synthese von Natrium-leitenden Festelektrolyten sowie die Entwicklung von Hydrogel-basierten Batterien. T2 - BMBF BattFutur NanoMatFutur Netzwerktreffen 2025 CY - Berlin, Germany DA - 24.02.2025 KW - Batterie PY - 2025 AN - OPUS4-63361 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Qi, Naiyu A1 - Somaskandan, Rachana A1 - Graeber, Gustav T1 - High-Precision Surface Tension Measurements of Sodium, Potassium, and Their Alloys via Du Noüy Ring Tensiometry N2 - The development of post-lithium-ion batteries has sparked significant interest in alkali-metal anodes, particularly sodium (Na), potassium (K), and sodium−potassium (Na−K) alloys. Na−K alloys are promising for partially liquid anodes due to their unique low melting points. A critical factor influencing Na−K-based anode performance is wetting behavior, which governs electrical conductivity, mechanical contact, and long-term stability. At the heart of wetting lies surface tension, a fundamental property of solid−liquid− gas interactions. However, the surface tension of alkali metals and their alloys, particularly Na−K systems, remains poorly understood due to experimental and theoretical challenges. This study bridged these gaps by employing Du Noüy ring tensiometry for the first time in alkali-metal systems to measure the surface tension of Na, K, and Na−K alloys across temperatures from ambient to 180 °C. A key innovation in this work is the development of the push-in Du Noüy method, which provided significantly higher precision and reliability compared to the traditional pull-out technique, without requiring a correction factor. The measured surface tension decreased with increasing temperature for the studied Na−K alloys. For instance, for a eutectic Na−K mixture, the surface tension decreases from 121.7 mN m−1 to 112.2 mN m−1 when increasing the temperature from ambient to 180 °C. Additionally, this study presented the first use of Gibbs free energy minimization to model the surface tension of the Na−K system. The robust method significantly enhanced the predictive accuracy compared to the previous simplified model, reducing deviations from 25% to 2%. Our findings reveal that surface tension increases with sodium mole fraction in the bulk phase, yet the surface monolayer remains potassium-rich, indicating non-ideal surface behavior. This study deepens the understanding of alkali-metal wetting behavior, providing valuable insights for designing optimized interfaces in next-generation semi-solid alkali-metal batteries. KW - Sodium−potassium alloy KW - Liquid-metal anodes KW - Alkali metal KW - Batteries KW - Surface tension PY - 2025 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-630102 DO - https://doi.org/10.1021/acsami.5c02183 SN - 1944-8252 VL - 17 IS - 17 SP - 25985 EP - 25995 PB - American Chemical Society (ACS) CY - Washington, DC AN - OPUS4-63010 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Romero Navarrete, J. A. A1 - Otremba, Frank A1 - Lozano Guzmán, A. A. T1 - Experimental-theoretical modelling of the lateral sloshing in rail tankers N2 - The objective of this paper is to describe and to validate a simplified pendulum-analogy model to simulate the interaction of a liquid cargo with ist carrying vehicle. The resulting testing rig consists of a rectangular container, spring supported on a two wheelset-bogie having a scale down of 1/10 with respect to a full-size equipment. The testing rig is used to validate a simple pendulum-based, simplified three degree-of-freedom mathematical model of the response of a partially filled container to lateral accelerations. The length of the pendulum is set according to validated methodologies. The resulting mathematical scheme reveals a high correlation with the experimental output, on the order of 99%, while some other performance measures, related to the peak forces and the range of variation of the wheel-rail forces, also show good concordance with the experimental results. KW - Sloshing KW - Rail tankers KW - Pendulum analogy KW - Experimental modelling KW - Mechanical fatigue PY - 2021 DO - https://doi.org/10.1504/ijhvs.2021.117504 VL - 28 IS - 3 SP - 435 EP - 454 AN - OPUS4-53101 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Kühl, Christiane T1 - Marktüberwachung nach der ortsbeweglichen-Druckgeräte-Verordnung (ODV) N2 - Die europäische Transportable Pressure Equipment Directive (TPED) ist national mit der Ortsbeweglichen-Druckgeräte-Verordnung (ODV) umgesetzt. Sie zielt darauf ab den freien Warenverkehr in Europa inkl. Drittstaaten sowie den Abbau von Handelshemmnissen zu regeln. Gleichzeitig soll ein hohes Schutzniveau bei öffentlichen Interessen wie Gesundheit und Sicherheit sowie Verbraucher- und Umweltschutz gewährleistet werden. Ortsbewegliche Druckgeräte durchlaufen vor ihrer Bereitstellung auf dem Markt keine behördliche Zulassung, sondern werden von Prüfstellen zertifiziert. Mit der behördlichen Marktüberwachung wird stichpunktartig die Konformität dieser Druckgeräte mit den betreffenden Vorschriften geprüft. Der Vortrag erklärt, was ortsbewegliche Druckgeräte im Anwendungsbereich der ODV genau sind, wie die Marktüberwachung in Deutschland organisiert ist und wie die europäischen Meldesysteme über nicht vorschriftenkonforme Produkte informieren. Der Vortrag stellt einige Praxisfälle vor. T2 - 26. Gefahrgutkongress Mecklenburg-Vorpommern CY - Rostock, Germany DA - 03.11.2022 KW - Marktüberwachung KW - Ortsbewegliche Druckgeräte PY - 2022 AN - OPUS4-61903 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Otremba, Frank A1 - Romero Navarrete, J. A. T1 - Assesing rail damage in turns due to lateral load transfer N2 - A testing procedure is proposed and used, to estimate the rail damage potentials of variations in both, the height of the cargo´s center of gravity and the railway car suspension´s spring constant. The experimental setup consisted of a tilt table that slowly exerted an increasing lateral acceleration on a two-axle bogie-type vehicle equipped with a spring supported container. The potential damaging effect derived from the resulting lateral load transfer, was assessed on the basis of the fourth-power law. Results suggest that the cargo having a higher center of gravity could be more damaging to the outside rail when compared with the effect of the shorter center of gravity of the cargo, in arrange from0.94% to 3.17%, as a function of the spring constant of the suspension. Consequently, and comparatively, there would be a long-term damaging effect on the rail when having a cargo with a higher center of gravity, so that specific cargo, having a high center of gravity, would be more aggressive to the infrastructure. On the other hand, for the range of time rate changes of the lateral acceleration, it was not found a consistent trend regarding the effect of the value of the spring constant on the magnitude of the load transfers. T2 - ASME 2024 CY - Portland, OR, USA DA - 17.11.2024 KW - Rail demage KW - Lateral load transfer PY - 2024 AN - OPUS4-61784 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Thomas, Sebastian T1 - Improvement of Type Approval Regulations of Pressure Vessels for Hydrogen Fueled Vehicles using Probabilistic Methods N2 - Composite pressure vessels (CPVs) are becoming the state of the art for storage for compressed hydrogen (CH2) in automotive applications. There is a strong interest of car manufacturers to use lightweight and less-costly gas storage units. In order to reduce the necessary amount of expensive carbon fibre, the nominal safety margins are becoming gradually smaller, pushing the limits of the regulations for type approval. At the same time, the total volume of these vessels increases to extend the range of the vehicles, increasing the consequences for worst-case scenarios like the rupture of the CPVs in service. This presentation presents insights gained in the project “TAnk HYdrogen Automotive” (TAHYA). Its aim is to improve the safety of current regulations for type approval of pressure vessels for the use in hydrogen fueled vehicles, namely GTR No. 13 and ECE R 134. For the assessment of safety, the probabilistic approach developed by division 3.5 of BAM is used. Monte-Carlo-Simulations were conducted leading to the identification of several weak spots, mainly found in the burst test and the batch test. By changing the requirements for burst tests and the approach for batch tests, the identified weak spots can be strongly reduced. T2 - Colloquium of Department 3 CY - Online meeting DA - 19.11.2020 KW - Monte-Carlo Simulation KW - Safety Assessment KW - Pressure Vessel PY - 2020 AN - OPUS4-51696 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -