TY - CONF A1 - Kömmling, Anja A1 - Jaunich, Matthias A1 - Grelle, Tobias A1 - Simbruner, Kai A1 - Zencker, Uwe A1 - Wolff, Dietmar A1 - Orellana Pérez, Teresa A1 - Völzke, Holger T1 - Research at BAM for evaluating long term safety of container systems and components N2 - Safety of long term containment and storage of radioactive waste is an essential issue, which is increasingly gaining international attention. Extending interim storage beyond initial license periods is one of the major challenges worldwide. BAM has been involved in all kinds of radioactive waste container safety evaluation for storage and transportation including their long term performance from the very beginning. Today, all work related to the safe management of radioactive waste is linked by the activity field “Nuclear Waste Management” within the Focus Area “Energy” at BAM and in conjunction with a research strategy and agenda. Most recently, the working group “Long Term Safety of Container Systems and Components” was established to launch and perform research projects related to safety issues concerning the extended interim storage of radioactive waste. For example, within our project LaMEP, we investigate ageing effects of metal and elastomer seals as well as polymeric neutron shielding materials, which are container components that fulfil major safety functions. The results of the experiments help to understand the long term behaviour of these components. Likewise, our project BRUZL started at BAM in 2018 with the aim of developing a fracture mechanics approach to understand and describe a potential brittle failure mechanism of fuel cladding during long-term interim storage. BAM also contributes to the GRS project “Development of methods and models and international exchange for safety evaluation in the frame of interim storage of radioactive waste”. Additionally, BAM is involved in several international research programmes dealing with extended interim storage, such as the European Joint Programme on Radioactive Waste Management (EURAD), the Extended Storage Collaboration Program (ESCP) and IAEA Coordinated Research Projects. The present contribution provides a comprehensive overview of BAM research activities contributing to national and international gap analyses and to filling knowledge gaps regarding the safe long term management of radioactive waste. T2 - Annual Meeting on Nuclear Technology 2019 CY - Berlin, Germany DA - 07.05.2019 KW - Radioactive Waste KW - Container Safety KW - Metal Seals KW - Elastomer Seals KW - Fuel cladding PY - 2019 AN - OPUS4-48437 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gröke, Carsten A1 - Neumann, Martin A1 - Komann, Steffen A1 - Wille, Frank T1 - Requirements for Package Design Testing and Quality Assurance Measures for Packages not Requiring Competent Authority Design Approval N2 - Übersicht über die gefahrgutrechtlichen Anforderungen zur Bauartprüfung und dem Qualitätsmanagement für Verpackungen für nicht zulassungspflichtige Versandstücke. T2 - KONTEC 2019 CY - Dresden, Germany DA - 27.03.2019 KW - Bauartprüfung KW - Qualitätsmanagement KW - Nicht zulassungspflichtig PY - 2019 AN - OPUS4-56352 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin A1 - Wille, Frank A1 - Kuschke, Christian A1 - Schubert, Sven A1 - Schilling, Olaf A1 - Günther, Uve A1 - Darnstädt, Andreas T1 - Requirements for management systems for manufacturing of transport packages: the new revision of BAM-GGR 011 guideline N2 - In accordance with IAEA SSR-6 para 306 a management system shall be established and implemented to ensure compliance with the relevant provisions of the IAEA regulations. BAM has issued an update of the guideline: the BAM-GGR 011. The new revision describes necessary quality assurance measures for design, manufacture, testing, documentation, use, maintenance and inspection of packagings for package designs requiring competent authority approval for the transport of radioactive material. The measures can be categorised as system-related and design-related. They are independently approved and monitored by the German competent authority BAM and its authorised expert (BAM/T). The qualification of the organisation applying for the design approval certificate is reviewed in the context of the design approval procedure. The quality assurance measures for manufacture consist of three main steps. Pre-assessment of manufacturing documents such as quality plans, specifications etc., Manufacturing inspections according the pre-assessed documents and inspection before commissioning including documentation review. Periodic inspections during operation as well as relevant specifications for use and maintenance ensure that the properties specified in the approval certificate are preserved over the package life time. Special provisions for the return on experience regarding operational feedback for design, manufacture, use, maintenance and inspection are given. Special focus shall be given here to the rearranged and meanwhile established system of manufacturing inspections. This includes more transparent roles for a) the producers authorised inspection 11282 representative, b) the independent inspection expert (S), acting on behalf of the manufacturer with acceptance of BAM, and c) BAM or its authorised expert (BAM/T). Additional attention shall be drawn to the management of deviations during manufacturing and provisions for maintenance and periodic inspections. T2 - 19th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 2019 CY - New Orleans, LA, USA DA - 04.08.2019 KW - Quality assurance KW - Transport KW - Manufacturing KW - Surveillance KW - Radioactive material PY - 2019 AN - OPUS4-49056 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Mair, Georg T1 - Relevante Entwicklungen zu Speichern für Gase als Energieträger N2 - Es werden die Zusammenhänge des Druckvolumenprodukts und der Konsequenz bei Druckgasen insbesondere für Wasserstoff dargestellt. Entsprechend werden Stellungnahmen zu verschiedenen Normungsprojekten abgeleitet und perspektivische Entwicklungen mit dem resultierenden Bedarf in der Normung dargestellt. Außerdem wird am Beispiel ein Problem in der praktischen Beurteilung von Speicherpopulationen für Batteriefahrzeuge diskutiert. T2 - 26. BAM-DIN-IGV-DVFG-Gespräch 2019 CY - Berlin, Germany DA - 27.02.2019 KW - Wasserstoffspeicher KW - Konsequenzbegrenzung KW - Normung KW - Druck-Volumen-Produkt KW - Katastrophe KW - Akzeptanz PY - 2019 AN - OPUS4-53145 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schlick-Hasper, Eva A1 - Bruchno, Martin A1 - Goedecke, Thomas T1 - Release of Powdery or Granular Substances from Intact Dangerous Goods Bags During Road Transport - Analysis of the Causes and Development of a Test Concept N2 - The leaks of dangerous goods from actually intact bags detected in the years 2018 to 2020 tend to be at an almost constant high level. These releases of powdery or granular dangerous goods represent violations of the sift-proofness required in the dangerous goods regulations. This article first analyzes the causes. The components of the bags that are affected by leaks are micro-perforations, joins and closures, in particular internal sleeve valves. A distinction must be made between bags closed in conformity with or contrary to the manufacturer's instructions. The particle release is determined by a number of influencing factors of the filling substance, the packaging and other boundary conditions. Therefore, a comprehensive test concept is developed in this work, which takes all these factors into account. The application of this test concept facilitates the planning of the test setup and the experiments. On this basis, the complex mechanisms involved in the release of solid substances can be systematically investigated in the test laboratory. To prevent releases of powdery or granular substances from intact bags, it is necessary that the user has access to the closing instructions and the relevant properties of the test substance used for the design type approval. Further experimental investigations are needed to assess whether filling substances change their properties during transport and whether this enables them to escape. T2 - 30th IAPRI Member Conference 2021 CY - Online meeting DA - 15.06.2020 KW - Bags KW - Dangerous goods packagings KW - Sift-proofness KW - Particles KW - Leak PY - 2021 AN - OPUS4-52827 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Orellana Pérez, Teresa T1 - Regulations codes and standards for safe hydrogen technologies N2 - Safety in hydrogen technologies in Europe is governed by international and European regulations and standards. An overview on regulatory bodies, technical committees, regulations, directives, standards, and technical guidelines with special attention on the BAM-GGR 021 is given in this lecture. T2 - Joint European Summer School 2023, Hydrogen Safety CY - Athens, Greece DA - 17.09.2023 KW - Hydrogen KW - Safety KW - Regulations KW - Standards PY - 2023 AN - OPUS4-59300 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Moutarde, Marianne A1 - Apel, Andreas A1 - Ballheimer, Viktor A1 - Sterthaus, Jens T1 - Recent developments in standards and IAEA guidance material for package load attachment points N2 - For transport package design and operation according to IAEA regulations, the package shall be securely stowed and its retention system shall be capable to withstand load conditions of routine transport. The supporting IAEA Advisory Material SSG-26 provides information how to do that. Up to now package designers in different countries use other load factors for the design of attachment points than those specified in the IAEA guidance material. In particular the acceleration values vary between different countries and lead to difficulties during the validation of foreign approval certificates. Therefore the IAEA started a discussion process to review the existing guidance text. An international working group was constituted in 2013. Representatives came from different stakeholders, e.g. transport operators, competent authorities and modal organizations. The discussions concluded especially on the transport conditions which has to be considered for stowage design, including on the one hand the relevance of the load factors used for strength and fatigue analysis and on the other hand the criteria which have to be considered for the attachment points. Another standard with relevance to the load attachment of packages is ISO 10276. This standard deals with trunnion design, manufacturing and operational aspects. The regular standard revision phase started in 2017. An expert group discussed new state-of-the-art technology and proposed revised text for the ISO standard for international discussion. The paper describes relevant tie-down aspects, gives background argumentation, and tries to support harmonized application of the revised IAEA guidance material and future ISO 10276 standard. T2 - 11th International Conference on the Transport, Storage and Disposal of Radioactive Materials CY - London, UK DA - 15.05.2018 KW - Acceleration KW - Package design KW - ISO KW - Ladungssicherung PY - 2018 AN - OPUS4-45293 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rolle, Annette A1 - Wille, Frank 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 - Orellana Pérez, Teresa A1 - Völzke, Holger A1 - Zencker, Uwe A1 - Wolff, Dietmar T1 - R&D initiatives at BAM concerning spent nuclear fuel integrity during long term storage N2 - The presentation provides an overview about the understanding of fuel cladding failure mechanisms dominated by hydride embrittlement during long term dry storage. A currently launched research project focuses on the development of a fracture mechanics approach to describe brittle failure of fuel cladding during long term interim storage (BRUZL)“. Finally, the BAM contribution to the current European Joint Program (EJP) on radioactive waste management is illustrated. T2 - 2nd GRS Workshop on Safety of Extended Dry Storage of Spent Nuclear Fuel CY - Munich, Germany DA - 06.06.2018 KW - Spent fuel KW - Extended interim storage KW - Hydride precipitation KW - Fuel cladding integrity PY - 2018 AN - OPUS4-45329 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin A1 - Quercetti, Thomas A1 - Gleim, Tobias A1 - Nehrig, Marko A1 - Musolff, André A1 - Wille, Frank T1 - R&D Activities by BAM Related to Transport Package Fire Testing N2 - Packages for the transport of radioactive material shall meet the mechanical and thermal test requirements of the International Atomic Energy Agency (IAEA) regulations for package design approval. Besides mechanical testing, the Federal Institute for Materials Research and Testing (BAM) performs thermal tests in accordance with the IAEA regulations. The thermal test includes a 30-minute 800°C fully engulfing fire. BAM continuously performs various thermal experiments for the investigation of the thermal response of packages with respect to the IAEA fire. The purpose of this paper is to give an overview of the already performed, ongoing and future physical tests and experiments of BAM in the field of thermal investigations. These research and development works shall support our competencies for the authority package design assessment. BAM operates a propane gas fire test facility. To be able to carry out comparative investigations and validity between the propane fire and the in detail prescribed pool fire test in the regulations, BAM carries out various calorimetric tests and investigates the boundary conditions of the fire with the help of fire reference packages. At the same time, we are conducting various fire scenarios with wood-filled impact limiters. Large-scale fire tests of impact limiters are carried out on a full scale as well as on a small scale. Influencing variables are investigated in particular by means of geometric changes and the consideration of artificial damages, in particular holes. In addition to propane fire as a heat source, thermal scenarios are also investigated with hydrogen as heat source and an infrared radiator system to ignite test specimens. For these numerous test arrangements, the transferability to existing and newly developed transport package designs is essential and fruitful within the review of design approvals, especially for Dual Purpose casks with a long-lasting operation time. T2 - 20th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 22) CY - Juan-les-Pins, France DA - 11.06.2023 KW - Fire Testing KW - Wood KW - Hydrogen KW - Fire Reference Test PY - 2023 AN - OPUS4-57722 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Romero-Navarrete, José A. A1 - Otremba, Frank A1 - Sklorz, Christian A1 - Martínez Madrid, M. T1 - Quasistatic rollover threshold of atmospheric road tankers N2 - On the other hand, it was found that the quasistatic rollover threshold of a circular tank, does not depend on the fill level, namely, it is only determined by the position of the support and the diameter of the tank T2 - CONIIN 2020 CY - Online meeting DA - 28.09.2020 KW - Quasistatic KW - Atmospheric KW - Road KW - Tankers PY - 2020 AN - OPUS4-51385 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Otremba, Frank T1 - Qualitätssicherung anstatt Wasserdruckprüfung? N2 - Wasserdruckprüfung kann entfallen: Schutzziel definieren, Qualitätssichernde Maßnahmen während der Herstellung, Nachweise der vorhandenen Qualität muss stetig erfolgen mittels: Betriebsüberwachung, zfP Bewertung des Standes der Technik: Zustandsorientierte Instandhaltung/Inspektion, Reduzierung von Ausfallzeiten durch optimierten Betrieb T2 - CSE-Sicherheitstage CY - Wangerooge, Germany DA - 22.04.2018 KW - Qualitätssicherung KW - Wasserdruckprüfung PY - 2018 AN - OPUS4-44817 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Qualification of Nuclear Waste Packages - Needs and Challenges from BAM's Perspective N2 - This Presentation adresses the major needs and challenges of qualification processes for nuclear waste packages performed by BAM. Packages include those for high level radioactive waste like spent fuel as well as those for low and intermediate level waste to be disposed of in the Konrad repository. Beginning with the current German nuclear waste management policy design testing capabilities and experience at BAM is explained followed by illustrating the major strategic process to identify future challenges including specific R&D needs. T2 - 5th International Nuclear Decommissioning Summit CY - Berlin, Germany DA - 30.01.2018 KW - Radioactive KW - Container KW - Testing KW - Safety PY - 2018 AN - OPUS4-44750 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Orellana Pérez, Teresa A1 - Khorasani, Media Ghasem Zadeh A1 - Mair, Georg A1 - Kehr, Torsten A1 - Bock, Robert A1 - Tiebe, Carlo T1 - QI Digital Use Case Hydrogen Refueling Station N2 - BAM is part of the “Quality Infrastructure Digital” (QI Digital) initiative of the German Federal Ministry for Economic Affairs and Climate Action (BMWK). This initiative aims at coordinating a large cooperation project, “QI Digital” for making German and European quality management systems fit for the digital transformation. It is a fact that the digitization of new products and services is occurring much faster than quality management systems can be accordingly updated. Thus, the digital transformation of quality management is necessary to preserve the competitiveness of the German and European industries that stand for quality and safety in the global market. The Use Case “Reliable Hydrogen Refueling Station” of QI Digital aims at creating new solutions that are transferable to other technical systems and at further developing standards and technical rules as a contribution to technology transfer and innovation. T2 - 4th German-Korean Hydrogen Conference CY - Seoul, Republic of Korea DA - 31.10.2023 KW - Hydrogen refueling station KW - Digital quality infrastructure PY - 2023 AN - OPUS4-59303 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Mair, Georg T1 - Prüfung der Wirksamkeit von Normen mithilfe der Monte-Carlo-Simulation N2 - Der Vortrag gibt zunächst einen Überblick über die Disziplinen, die in der BAM bzgl. Druckgefäßpüfung verfügbar sind. Außerdem ist zusammengestellt, mit welchen Vh-Beteiligungen und daraus resultierenden Lösungsansätzen die BAM jeweils zeitnah auf Änderungen im Recht, die die Aufgabe als zuständige Behörde betrafen, reagiert hat. Danach wird in die Festigkeitskennwerte und deren Simulation mithilfe der Monte-Carlo-Simulation eingeführt und der Unterschied zwischen Überlebenswahrscheinlichkeit und Akzeptanzrate erläutert. Darauf aufbauend wird gezeigt, wie die Akzeptanzrate grenzwertig zuverlässiger Grundgesamtheiten einer Prüfvorschrift ermittelt werden kann. Zuletzt wird gezeigt, dass ein solcher Ansatz ein Optimierungspotential für Wasserstoff-Trailerflaschen eröffnet, sofern er konsequent angewendet wird. T2 - Jährlicher Austausch zwischen der BAM und DIN, IGV und DVFG CY - IGV-Sitz in Berlin-Mitte, Germany DA - 21.02.2018 KW - Wasserstoff KW - Akzeptanzrate KW - GTR 13 KW - Überlebenswahrscheinlichkeit KW - Berstfestigkeit KW - Sample Performance Chart PY - 2018 AN - OPUS4-45465 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Tiebe, Carlo A1 - Maiwald, Michael A1 - Rabe, Torsten A1 - Prager, Jens A1 - Lugovtsova, Yevgeniya A1 - Schukar, Marcus A1 - Munzke, Dorit A1 - Duffner, Eric A1 - Eisermann, René A1 - Schoppa, André A1 - Szczepaniak, Mariusz A1 - Strohhäcker, J. A1 - Mair, Georg T1 - Prüf- und Messverfahren mit verschiedenen Sensortechnologien und Ultraschallwellen N2 - Der Vortrag zum Mess- und Prüfverfahren mit verschiedenen Sensortechnologien und Ultraschallwellen beinhaltet die Themen: Metrologie zur Wasserstoffspeicherung - Euramet-Vorhaben "MefHySto", Erkennung von freigesetztem Wasserstoff sowie die Bestimmung des Wasserstoff-Luftverhälntisses mit Gassensoren, zerstörungsfreie Fehlstellenerkennung mit integriertem Zustandsüberwachungssystem basierend auf geführten Ultraschallwellen zur Lebensdauerüberwachung von Composite-Behältern (Wasserstoffspeicher) sowie faseroptische Sensorik zur Schadenfrüherkennung von Wasserstoffspeichern aufgrund erkennbarer Dehnungsänderungen an Druckbehältern. T2 - DVGW Kongress H2 Sicherheit CY - Online meeting DA - 28.09.2021 KW - Leckdetektion KW - Metrologie zur Wasserstoffspeicherung KW - Gassensorik KW - Structural Health Monitoring (SHM) KW - Geführte Ultraschallwellen KW - Faseroptische Sensorik KW - Zerstörungsfreie Prüfung PY - 2021 AN - OPUS4-54136 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Herold, Christian A1 - Völzke, Holger A1 - Orellana Pérez, Teresa T1 - Projektvorhaben "KoBrA" - AP1 N2 - Eine umfangreiche Darstellung der bisherigen Ergebnisse des ersten Arbeitspaketes im FuE-Vorhaben "KoBrA": Ziele und Anknüpfungspunkte des AP1; Ableitung von Kriterien und Kategorien; internationale Kernenergienutzung; Quellenbasis und Literaturrecherche; Selektion und Sortierung der Dokumentensammlung; Beispiele internationaler Endlagerprogramme N2 - An exhaustive presentation of the first working package of project "KoBrA" and its preliminary results: Objectives and follow-up links in- and outside the project; establishing criteria and categories; screening of international nuclear power programmes; reference basis and literature research; selecting and sorting the compiled documents; examplary international final disposal programmes T2 - Fachinformationsgespräch zum FuE-Vorhaben "KoBrA" CY - Berlin, Germany DA - 28.05.2018 KW - Endlagerbehälter KW - Kernenergienutzung KW - Dokumentensammlung KW - Hochaktive wärmeentwickelnde Abfälle KW - Länderübersicht PY - 2018 AN - OPUS4-45468 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Kehr, Torsten A1 - Günzel, Stephan A1 - Habib, Abdel Karim A1 - Mair, Georg A1 - Maiwald, Michael A1 - Prager, Jens A1 - Tiebe, Carlo T1 - Project QI-Digital - Quo vadis Use Case H2 Refueling Station? N2 - As a part of the QI-Digital cooperation project, BAM is setting up a hydrogen refuelling station research platform at the Test site for Technical Safety in Horstwalde. Based on this platform, BAM intends to develop, to test and to optimize new measurement techniques as well as data acquisition and processing methods for hydrogen refuelling stations and their periphery in close cooperation with partners from the quality infrastructure and industry. The presentation will introduce the hydrogen refuelling station use case and provide insights into the issues and research goals of the associated subprojects. T2 - H2-Colloquium of the Competence Centre „H2SAFETY@BAM” CY - Online meeting DA - 16.02.2022 KW - Hydrogen KW - Safety KW - QI-Digital PY - 2022 AN - OPUS4-54361 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Herold, Christian A1 - Völzke, Holger A1 - Orellana Pérez, Teresa A1 - Wolff, Dietmar A1 - Bollingerfehr, W. A1 - Prignitz, S. A1 - Wunderlich, A. T1 - Project KoBrA - Requirements and concepts for disposal containers for heat-generating radioactive waste and spent fuel in salt, clay and crystalline rock N2 - After restarting the site selection process for a final repository for spent nuclear fuel (SNF) and heat-generating radioactive waste, all areas with one of the three potential host rock formations considered in Germany – salt, clay and crystalline rock – are under review. The project “KoBrA“, run by BGE TECHNOLOGY and BAM, collects and reviews requirements, criteria and proposals for final disposal container concepts complying with the current safety standards, taking into consideration international experience in the field of high-level nuclear waste (HLW) management. T2 - IGD-TP Exchange Forum 8 CY - Berlin, Germany DA - 03.12.2018 KW - Final disposal container KW - Spent fuel KW - HLW KW - Concepts KW - Requirements PY - 2018 UR - https://igdtp.eu/wp-content/uploads/2018/11/EF8-P9-Herold-KoBrA_V1b2.pdf AN - OPUS4-46983 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Linnemann, Konrad A1 - Quercetti, Thomas A1 - Sterthaus, Jens A1 - Ballheimer, Viktor T1 - Prestressed bolt connections under lateral displacements N2 - The containment system of transport packages for spent nuclear fuel and high-level waste usually includes bolted lids with metal gaskets. The specified transport condition imply high loading on the lids and the bolt connections of the package. The response of the lid systems on these load conditions is generally investigated by drop tests or numerically. BAM has started a research project to get a better understanding about the behavior of prestressed bolt connection under loadings typical for drop tests. T2 - IRSN-BAM Symposium Safety of Transport and Storage Packages CY - Online meeting DA - 19.11.2020 KW - Transport packages KW - Pprestressed bolt connection KW - Experimental investigation KW - Finite element method PY - 2020 AN - OPUS4-51697 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Linnemann, Konrad A1 - Quercetti, Thomas A1 - Sterthaus, Jens A1 - Ballheimer, Viktor T1 - Prestressed bolt connections under lateral displacements N2 - The containment system of transport packages for spent nuclear fuel and high-level waste usually includes bolted lids with metal gaskets. The specified transport condition imply high loading on the lids and the bolt connections of the package. The response of the lid systems on these load conditions is generally investigated by drop tests or numerically. BAM has started a research project to get a better understanding about the behavior of prestressed bolt connection under loadings typical for drop tests. T2 - BAM-IRSN-Workshop 2021 CY - Berlin, Germany DA - 08.09.2021 KW - Transport packages KW - Bolt connections KW - Finite element analysis KW - Experimental investigation PY - 2021 AN - OPUS4-53251 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Duffner, Eric A1 - Szczepaniak, Mariusz A1 - Kriegsmann, Andreas T1 - Pressure cylinders for the transport of dangerous goods N2 - Introduction of the Department 3 and the competence and scientific focus of the working group focus area energy - gases for external visitors. T2 - Besuch einer Studentengruppe der AGH Krakau CY - BAM Berlin, Germany DA - 23.09.2019 KW - Introduction Department 3 KW - Focus area energy gases PY - 2019 AN - OPUS4-49193 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias A1 - Wille, Frank A1 - Wille, Frank 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 - Geburtig, Anja T1 - Possibilities on prediction of plastic’s fragmentation time - Digital twins for decomposing-time predictions N2 - Depending on the specific plastic’s ageing sensitivities, the durations which plastic components remain in the environment can be very long. As, in the past, the advantages in ageing resistance and durability were highly evaluated, we now face the problem of quite stable plastic waste within the environment. However, there is only little knowledge on the real timescales until macroscopic fragmentation for the different kinds of plastic under various environmental conditions. Here, weathering methods are presented, which have been used for the failure prediction in specific outdoor conditions. Issues of uncertainty, reproducibility, or validation are discussed. For the prediction of the plastic’s fragmentation, much longer time scales have to be considered. To do this within a limited project life span, various processes as well as their acceleration potential have to be evaluated separately, such as temperature increase or spectral shift. The possibilities and limitations of such controlled acceleration will be discussed. T2 - 29th IAPRI Symposium on Packaging CY - Twente, Enschede, The Netherlands DA - 11.06.2019 KW - Plastic KW - Ageing KW - Environment KW - Fragmentation KW - Digital twin PY - 2019 AN - OPUS4-49714 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias T1 - Polyurethane Foam in Impact Limiters - Experimental and Numerical Analysis N2 - Transport containers with radioactive material are usually shipped in Germany with wooden-filled impact limiters. Alternative energy-absorbing materials for this purpose can be polyurethane foam, for example. In order to perform adequate simulations with PU foam, experimental and numerical investigations must be carried out. With the help of a series of experimental test runs, a material model is developed, tested and compared in LS-Dyna. T2 - Technical Exchange IRSN – BAM: Transport & Storage of Packages for Radioactive Material CY - Berlin, Germany DA - 08.09.2021 KW - Polyurethane Foam, Impact Limiters, PU-Foam PY - 2021 AN - OPUS4-53261 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias T1 - Polyurethane Foam for Impact Limiters - Theory and Experimental Data N2 - Transport containers with radioactive material are usually shipped in Germany with wooden-filled impact limiters. Alternative energy-absorbing materials for this purpose can be polyurethane foam, for example. In order to adequately determine the characteristics for a selected PU foam, various experimental investigations must be carried out. Classically, PU foam specimens are tested under uniaxial compression, confined compression and a tensile test. Using the experimental data and selected material models from the literature, the parameters can be determined to describe and apply material models. T2 - Technical Exchange Sandia – BAM: Transport & Storage of Packages for Radioactive Material CY - Online meeting DA - 31.08.2021 KW - Polyurethane Foam KW - Impact Limiters KW - PU-Foam PY - 2021 AN - OPUS4-53262 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Keller, Christian A1 - Herbrich, Uwe T1 - Plastic Instability of Rate-Dependent Materials - Consideration of Isothermal and Adiabatic Conditions in Dynamic Tensile Tests - N2 - During dynamic processes, a certain range of strain rates is often observed along loaded structures and components. For precise numerical simulations, it is necessary to determine rate-dependent properties in dynamic tests and to describe the material behavior correctly within an appropriate domain of strain rates including adiabatic heating effects at higher strain rates, typically higher than 10 1/s. In principle, numerical simulations are compared to experimental results to verify the applied material models. For dynamic tensile tests considering ductile materials and large plastic deformation beyond uniform elongation, it is challenging to obtain comparable results due to plastic instability and necking of the specimen, e.g.. Based on the strain gradient in a general tensile specimen, a theoretical criterion was derived describing the plastic instability in rate-dependent materials under isothermal conditions in. It was applied to different multiplicative and additive constitutive relations and the analytical onset of necking was compared to results from numerical calculations of quasi-static and dynamic tensile tests. The simulations of a sheet-metal specimen with rectangular cross-section were carried out using the Finite Element Method and it was found that the numerical calculated and the theoretical predicted onset of plastic instability agree very good. The analytical criterion for instability holds even for specimens without geometrical or material imperfections and confirms that the onset of plastic instability must be considered a material characteristic. However, real dynamic problems with higher strain rates are not isothermal, the heat generated by plastic work is not dissipated to the surrounding and the temperature of the material increases significantly. Adiabatic heating and thermal softening must be considered within the constitutive relations of rate-dependent materials and the discussion of plastic instability. In this paper, an enhanced and more generalized approach for the description of the condition for stability is discussed and applied to phenomenological as well as more physical constitutive relations from the literature. This allows an individual assessment of the accuracy and verification of rate-dependent material models with respect to plastic instability. T2 - 13th World Congress on Computational Mechanics CY - New York, USA DA - 22.07.2018 KW - Plastic Instability KW - FEM KW - Rate-dependent Materials KW - Dynamic Tensile Test PY - 2018 AN - OPUS4-48923 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Beckmann, Jörg A1 - Puskar, Ljiljana A1 - Schade, U. A1 - Jaunich, Matthias A1 - Wolff, Dietmar A1 - Bär, Sylke T1 - Photolytically and Thermally Initiated Destruction on the Stability of (Ultra)High Molecular Polyethylene N2 - THz and mid IR spectroscopy of high-molecular PE (HMW) and ultra high-molecular PE (UHMW) reveals modifications of the molecular structure. Characteristic absorption bands are changed if the two materials are exposed by γ-Co60 radiation up to 600 kGy and subsequently stored at an annealing temperature of 398 K until for 729 days. UHMW-PE and HMW-PE behave differently during the ageing process because of their molecular weight and inherent structure distinctions. The spectroscopic data offer characteristic absorption bands, which have been used to describe the complete ageing process in more detail. For instance, the integral absorption in the B1u THz-region can be used to describe quantitatively the reduction of crystallinity. The formation of trans vinylene unsaturation and the decay of vinyl during ageing can be observed in detail in the mid IR range. T2 - 9th International Workshop on Terahertz Technology and Applications CY - Kaiserslautern, Germany DA - 03.03.2020 KW - Degradation KW - MID IR Spectroscopy PY - 2020 AN - OPUS4-50555 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Popiela, Bartosz A1 - Günzel, Stephan A1 - Mair, Georg A1 - Seidlitz, H. A1 - Ulke-Winter, L. 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 - Quercetti, Thomas A1 - Scheidemann, Robert A1 - Komann, Steffen A1 - Ballheimer, Viktor A1 - Wille, Frank T1 - Package testing of a dual purpose cask for SNF from german research reactors N2 - A new dual purpose cask design was developed for the safe transport and interim storage of spent fuel elements of German research reactors. In the framework of the safety assessment within the licensing procedure the Bundesanstalt für Materialforschung und –prüfung (BAM) as competent authority performed a series of drop tests according to the IAEA-Regulations. The package consists of a cylindrical thick-walled ductile cast iron cask body closed by a double lid system with metallic seals. A lid and bottom sided impact limiter consisting of a wood/steel construction limit the mechanical impact loading. The full-scale test specimen was equipped with a basket and assembled with dummy-fuel elements. The package and test specimen, respectively have a total mass of approximately 24 metric tons. The mechanical test program included three 9m free drop tests, in horizontal, vertical and oblique cask orientation onto the lid system. Additionally, a 1m-puncture drop test followed the horizontal drop test to consider an IAEA-test sequence. The horizontal and vertical drop tests were performed at a temperature of minus 40°C. During the oblique drop test the upper impact limiter was heated to +80°C. The tests were conducted onto an unyielding target, fulfilling the requirements of the IAEA regulations. The test specimen was considerably instrumented with strain gauges and accelerometers. Transient strains at selected locations of the inner and outer container walls, of the primary and secondary lid, as well as of the corresponding lid bolts were measured during the drop tests. Furthermore, decelerations in different locations at the cask body and the lids were measured. The complex geometrical deformation of the impact limiters due to the impact were determined by optical 3d- measurements using the projected fringe method in combination with multi-image photogrammetry. Before and after the drop tests the leakage rate of the lid system was determined by helium leakage testing. The experimental results contribute to the evaluation of the package response to mechanical tests, demonstrating safety under normal and accident conditions of transport. Especially to the verification of the dynamic finiteelement model of the package used in the package design safety report. The paper describes the performance of the drop tests, selected test results focusing on the lid screws and the cask body and the deformation of the impact limiters as well as impact kinematics, respectively. T2 - IHLWM 2019 CY - Knoxville, TN, USA DA - 14.04.2019 KW - Package testing KW - Drop test PY - 2019 AN - OPUS4-50620 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Quercetti, Thomas A1 - Scheidemann, Robert A1 - Komann, Steffen A1 - Ballheimer, Viktor A1 - Wille, Frank T1 - Package testing of a dual purpose cask for SNF from german research reactors N2 - A new dual purpose cask design was developed for the safe transport and interim storage of spent fuel elements of German research reactors. In the framework of the safety assessment within the licensing procedure the Bundesanstalt für Materialforschung und –prüfung (BAM) as competent authority performed a series of drop tests according to the IAEA-Regulations. The package consists of a cylindrical thick-walled ductile cast iron cask body closed by a double lid system with metallic seals. A lid and bottom sided impact limiter consisting of a wood/steel construction limit the mechanical impact loading. The full-scale test specimen was equipped with a basket and assembled with dummy-fuel elements. The package and test specimen, respectively have a total mass of approximately 24 metric tons. The mechanical test program included three 9m free drop tests, in horizontal, vertical and oblique cask orientation onto the lid system. Additionally, a 1m-puncture drop test followed the horizontal drop test to consider an IAEA-test sequence. The horizontal and vertical drop tests were performed at a temperature of minus 40°C. During the oblique drop test the upper impact limiter was heated to +80°C. The tests were conducted onto an unyielding target, fulfilling the requirements of the IAEA regulations. The test specimen was considerably instrumented with strain gauges and accelerometers. Transient strains at selected locations of the inner and outer container walls, of the primary and secondary lid, as well as of the corresponding lid bolts were measured during the drop tests. Furthermore, decelerations in different locations at the cask body and the lids were measured. The complex geometrical deformation of the impact limiters due to the impact were determined by optical 3d- measurements using the projected fringe method in combination with multi-image photogrammetry. Before and after the drop tests the leakage rate of the lid system was determined by helium leakage testing. The experimental results contribute to the evaluation of the package response to mechanical tests, demonstrating safety under normal and accident conditions of transport. Especially to the verification of the dynamic finiteelement model of the package used in the package design safety report. The paper describes the performance of the drop tests, selected test results focusing on the lid screws and the cask body and the deformation of the impact limiters as well as impact kinematics, respectively. T2 - Workshop ORNL/BAM CY - Oak Ridge National Laboratory, TN, USA DA - 11.04.2019 KW - Package testing KW - Drop test PY - 2019 AN - OPUS4-50621 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zaghdoudi, Maha A1 - Kömmling, Anja A1 - Jaunich, Matthias A1 - Wolff, Dietmar T1 - Oxidative ageing of elastomers: experiment and modelling N2 - During an extensive test programme at the Bundesanstalt für Materialforschung und prüfung, material property changes of EPDM O-rings were investigated at different ageing times and an ageing temperature of 125 °C. To exclude possible diffusion limited oxidation (DLO) effects that can distort the data, IRHD micro hardness measurements were performed over the cross-section of compressed O-rings. Continuous stress relaxation measurements were conducted on samples free of DLO effects. The additional effect of physical processes to irreversible chemical ones during a long-term thermal exposure is quantified by the analysis of compression set measurements under various test conditions. By combining the different experimental methods, characteristic times relative to the degradation processes were determined. On the basis of experimental data, a microphysically motivated model that takes into account reversible and irreversible processes was developed. The parameter identification strategy of the material model is based on our experimental investigations on homogeneously aged elastomer O-rings. The simulated results are in good agreement with the experiments. T2 - ACEX-14th International Conference on Advanced Computational Engineering and Experimenting CY - Malta DA - 04.07.2021 KW - Compression stress relaxation KW - Compression set KW - IRHD micro hardness KW - Modelling PY - 2021 AN - OPUS4-52968 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zaghdoudi, Maha A1 - Kömmling, Anja A1 - Jaunich, Matthias A1 - Wolff, Dietmar A1 - Albouy, P.-A. A1 - Häcker, Ralf A1 - Stock, Daniel T1 - Overview of ongoing research and future prospects on polyethylene neutron shielding materials at BAM N2 - The extension of the interim storage period of radioactive waste before disposal will cause additional challenges for the nuclear waste management in Germany, so that an extensive knowledge of the long-term performance of casks, including their components and inventories, will be required for future extended storage licenses. Ultra-high and high molecular weight polyethylenes ((U)HMW-PE) are used for neutron shielding purposes in casks for storage and transport of spent fuel and high-level waste due to their extremely high hydrogen content. During their service life of several decades as cask components, the PE materials are exposed to neutron and gamma radiation from the radioactive inventory of the casks, mechanical assembling stresses and temperature. All these combined effects affect the material properties of such components which in turn may be crucial for some possible accident scenarios. At the Bundesanstalt für Materialforschung und -prüfung (BAM), the effects of high temperature exposure in combination with subsequent or previous irradiation were investigated with a comprehensive aging program including thermal aging at 125 °C for different aging periods up to 5 years and irradiation with doses ranging from 50 to 600 kGy. This contribution provides an overview of the ongoing research related to the structural changes of (U)HMW-PE induced by gamma irradiation and high temperature exposure and focuses on current research perspectives at BAM with regard to the prediction of the dynamic behavior of the material during extended interim storage in case of an accident scenario. First results of the coupled effect of temperature, radiation and mechanical loading will be presented. The effect of microstructural changes induced by gamma irradiation and high temperature on the mechanical behavior of (U)HMW-PE will be assessed. T2 - PATRAM22 CY - Juan-les-Pins, France DA - 11.06.2023 KW - (U)HMWPE KW - Ageing KW - Irradiation KW - WAXD KW - SHPB PY - 2023 AN - OPUS4-57708 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zaghdoudi, Maha A1 - Kömmling, Anja A1 - Jaunich, Matthias A1 - Wolff, Dietmar T1 - Overview of ongoing long-term ageing investigations on elastomer seals N2 - At the Bundesanstalt für Materialforschung und -prüfung (BAM) in Division 3.4 Safety of Storage Containers, one of our tasks is to evaluate the safety of containers designed for disposal of low and intermediate radioactive waste. As such containers might be transported before and stored until disposal, safe enclosure of the radioactive inventory is important for this time span. Elastomer O-rings are widely used as barrier seals in these containers. Thus, as for many other applications, an understanding of the practical effects of ageing degradation on elastomer seals during long-term exposure is mandatory for predicting the lifetime of such components. According to a long-term test programme on three kinds of rubbers (EPDM and FKM (relevant for application), HNBR (for comparison)), over several years we have studied the degradation and the change of mechanical properties (e.g. hardness, strain at break) at four different ageing temperatures (75 °C, 100 °C, 125 °C and 150 °C) as well as the change of sealing properties. Continuous and intermittent compression stress relaxation (CSR) measurements were performed in order to investigate the respective contribution of crosslinking and chain scission to the observed degradation effects. Thus, the degradation kinetics and mechanisms could be resolved more clearly. For assessing the seal performance, compression set (CS) and leakage rate measurements were conducted. The experimental results showed that the O-rings remained leak-tight under purely static conditions even when CSR, CS and mechanical properties already indicated far advanced degradation. For this reason, a modified leakage test involving a small and rapid partial decompression of the seal was developed that enabled determining an end-of-lifetime criterion for O-rings with a safety margin for thermal shrinkage and vibrations. T2 - IRC CY - London, UK DA - 03.09.2019 KW - Compression set KW - Continuous compression stress relaxation KW - Intermittent compression stress relaxation KW - Leakage rate PY - 2019 AN - OPUS4-49073 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Jaunich, Matthias T1 - Overview of metal seal tests performed at BAM and implications for extended interim storage N2 - The investigation of the long-term performance of sealing systems employed in containers for radioactive waste and spent nuclear fuel is one research focus area for division 3.4 “Safety of Storage Containers” at the Bundesanstalt für Materialforschung und -prüfung. The behaviour of metallic seals, which are employed in interim storage casks for used fuel and high active waste, over time is of high importance for ensuring safe enclosure. Therefore, investigations on these systems were started at BAM to get a general understanding of the relevant processes. Our investigations comprise investigations on different parameters which influence the seal performance and the main part is focussed on the time and temperature dependent behaviour. In this contribution an overview of the performed tests and their respective results will be given. A focus will lie on a comparison between seals with large torus diameter in comparison to small diameters. Our aim is to understand the long-term behaviour of the sealing systems for evaluation of their performance during possible extended interim storage and subsequent transportation. T2 - 4th Workshop on Safety of Extended Dry Storage of Spent Nuclear Fuel CY - Online meeting DA - 03.06.2020 KW - Seal performance KW - Metal seal KW - Leakage rate PY - 2020 AN - OPUS4-50843 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin A1 - Quercetti, Thomas A1 - Wille, Frank T1 - Outcomes of Three Large-Scale Fire Reference Tests Conducted in Propane Gas Fire Test Facility N2 - Packages for the transport of high-level radioactive material are designed to withstand severe accidents. Hypothetical severe accident conditions are defined in the IAEA Regulations for the Safe Transport of Radioactive Materials. One of these accident conditions is the thermal test, mainly consisting of a 30 minute fully engulfing 800°C pool fire or an equally severe fire test. The heat fluxes into the package depend substantially on the fire characteristics and the surface temperature of the package. Fire tests can be performed at BAM on a propane gas fire test facility. In order to investigate the heat fluxes over a wide range of surface temperatures in this test facility a fire reference package was designed for multiple use. The package represented the outer geometry of a specific transport cask for radioactive waste. The fire reference package is a closed steel sheet cylinder with a wall thickness of 10 mm, a length of 1500 mm and a diameter of 1050 mm. The package was instrumented with thermocouples and filled with heat resistant insulation material. Three open-air fire tests were performed in the BAM propane gas fire test facility. The flames exposure time period varied slightly for the fire tests. The wind direction as well as the wind speed were measured and changed between and during the tests. Test stand parameters such as wind shield location and propane gas volume flow were chosen constant for the three tests. The locally measured fire reference package steel sheet temperatures were used for the calculation of heat fluxes as function of time and surface temperature. The measured temperatures allowed further calculations. In a first approach effective fire characteristics of the propane gas fire, including the flame temperature, the fire convection coefficient and a radiation exchange coefficient mathematically describing the determined average heat flux over the surface temperature were calculated. T2 - Abteilungskolloquium 3.3 CY - Online meeting DA - 03.12.2020 KW - Fire KW - Heat flux KW - Convection coefficient KW - Adiabatic surface temperature KW - IAEA PY - 2020 AN - OPUS4-51778 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin A1 - Quercetti, Thomas A1 - Wille, Frank T1 - Outcomes of three large scale fire reference tests conducted in BAM fire test facility N2 - Packages for the transport of high-level radioactive material are designed to withstand severe accidents. Hypothetical severe accident conditions are defined in the IAEA Regulations for the Safe Transport of Radioactive Materials. One of these accident conditions is the thermal test, mainly consisting of a 30 minute fully engulfing 800°C pool fire or an equally severe fire test. The heat fluxes into the package depend substantially on the fire characteristics and the Surface temperature of the package. Fire tests can be performed at BAM on a propane gas fire test facility. In order to investigate the heat fluxes over a wide range of surface temperatures in this test facility a fire reference package was designed for multiple use. The package represented the outer geometry of a specific transport cask for radioactive waste. The fire reference package is a closed steel sheet cylinder with a wall thickness of 10 mm, a length of 1500 mm and a diameter of 1050 mm. The package was instrumented with thermocouples and filled with heat resistant insulation material. Three open-air fire tests were performed in the BAM propane gas fire test facility. The flames exposure time period varied slightly for the fire tests. The wind direction as well as the wind Speed were measured and changed between and during the tests. Test stand parameters such as wind shield location and propane gas volume flow were chosen constant for the three tests. The locally measured fire reference package steel sheet temperatures were used for the calculation of heat fluxes as function of time and surface temperature. The measured temperatures allowed further calculations. In a first approach effective fire characteristics of the propane gas fire, including the flame temperature, the fire convection coefficient and a Radiation exchange coefficient mathematically describing the determined average heat flux over the surface temperature were calculated. T2 - Pressure Vessels & Piping Virtual Conference 2020 CY - Online meeting DA - 03.08.2020 KW - Fire KW - Testing KW - Convection coefficient KW - Large scale fire testing KW - Propane gas fire test facility PY - 2020 AN - OPUS4-51194 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Birk, A. M. A1 - Bradley, I. A1 - Bisby, L. A1 - Otremba, Frank A1 - Borch, Jörg T1 - Optical Access Pressure Vessel for Observing Temperature Stratification and Boiling in a Pressure Vessel Exposed to Accidental Fire N2 - We are interested in accidental fire impingement of HazMat pressure vessels. Want to develop improved models for predicting time to failure or empty (if PRV present). We are still trying to properly predict pressurization and time to first PRV activation due to liquid temperature stratification for a range of fire scenarios (Full and partial engulfing pool fire, jet fires, with roll over, with TP defects, etc.) T2 - Optical Access PV for Fire Effects Research CY - Berlin, Germany KW - Vessels KW - Observing temperatur KW - Accidential Fire PY - 2023 AN - OPUS4-57565 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Mair, Georg T1 - Open Issues of insuring Safety of CPVs by Strength testing N2 - Der Vortrag erläutert den Sicherheitsbegriff im erweiterten Sinne und führt zur Notwendigkeit eines eher risikobasierten Verständnisses der Sicherheit. Darauf aufbauend wird mithilfe der Monte-Carlo-Simulation gezeigt, wo die Schwachstellen der ECE R 134 liegen und in welche Richtung die GTR 13 in der Phase 2 optimiert werden könnte. Hierzu ist es hilfreich, die Monte-Carlo Simulation als Werkzeug weiter zu entwickeln, wozu die BAM das Vh-Konzept MoCaSiB vorstellt. N2 - The presentation explains the term “safety” in a broader sense and leads to the need for a more risk-based understanding of safety. Based on this, the Monte Carlo simulation is used to show where the weak points of the ECE R 134 are and in which direction the GTR 13 could be optimized during the currently running phase 2. For this purpose, it is helpful to improve the currently operated tool for Monte Carlo simulation, for which BAM introduced the research idea “MoCaSiB”. T2 - Sitzung 18-01 des FKT- Sonderausschusses „Sicherheit von Gas- und Wasserstoffahrzeugen“ (FKT-SA SGWF) CY - TÜV Rheinland, Köln, Germany DA - 24.05.2018 KW - Probability of failure KW - Acceptance rate KW - Survival rate KW - Basic populaiton KW - Burst ratio PY - 2018 AN - OPUS4-45469 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin A1 - Grelle, Tobias A1 - Jaunich, Matthias A1 - Probst, Ulrich A1 - Wolff, Dietmar A1 - Kömmling, Anja A1 - Zencker, Uwe A1 - Orellana Pérez, Teresa A1 - Völzke, Holger A1 - Wille, Frank T1 - Ongoing research & development about metal and elastomer seals at BAM N2 - Packages for the transport and storage of radioactive materials are often sealed with elastomer or metal seals. These seals are basic components to meet the leak tightness criteria for these kind of packages. An overview over ongoing research and development concerning metal and elastomer seals is given in the presentation. Introductions in the fundamental functionality of elastomer and metal seals are presented. Ageing processes are shown for both components regarding to different ageing effects. T2 - IRSN Conference on Safe Transport of Radioactive Material CY - Fontenay aux Roses, France DA - 13.11.2018 KW - Seal KW - Seals KW - Metal seal KW - Elastomer seal KW - Long term investigation KW - Helical spring KW - Aluminum seal KW - Silver seal KW - Component test KW - Useable resilience KW - Leakage rate KW - Compression set KW - Low temperature investigation KW - Ageing KW - Radioactive KW - Transport KW - Storage KW - IAEA PY - 2018 AN - OPUS4-46881 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Wolff, Dietmar A1 - Zencker, Uwe A1 - Orellana Pérez, Teresa T1 - Ongoing R&D work at BAM N2 - The presentation provides an update on the German nuclear waste management policy towards final disposal and related reasearch at BAM. Topics include long term investigations of metal seals, investigations of fuel cladding failure mechanisms, and the development of requirements and concepts for high level radioactive waste and spent fuel disposal containers. T2 - EPRI Extended Storage Collaboration Program (ESCP) International Subcommittee Meeting 2018 CY - Munich, Germany DA - 05.06.2018 KW - Radioactive waste KW - Metal seal KW - Disposal container KW - Fuel cladding PY - 2018 AN - OPUS4-45328 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Romero-Navarrete, José A. A1 - Otremba, Frank T1 - Oblique testing of a partially filled tank on a tilt table N2 - Experimental measurements that aimed at characterizing the effect of applying simultaneously longitudinal and lateral perturbations to a partially filled container, on the forces exerted on the infrastructure, by setting the testing vehicle cargo system at an oblique angle on a tilt table. T2 - IFToMM world congress CY - Krakow, Poland DA - 30.06.2019 KW - Oblique testing KW - Filled tank KW - Tilt table PY - 2019 AN - OPUS4-48460 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neitsch, Marcel T1 - Nutzung von Recycling-Kunststoffen für die Produktion von Gefahrgutverpackungen – aktueller Stand der Norm ISO 16103 N2 - Im Vortrag wird der Stand der Weiterentwicklung der ISO 16103 dargestellt, in der Regelungen zur Qualitätssicherung bei der Herstellung von Recycling-Kunststoffen und daraus hergestellter Gefahrgutverpackungen enthalten sind. Darüber hinaus wird auf die Verbindungen zu den UN Model Regulations und zum ADR eingegangen und welche Konsequenzen sich daraus für die Zulassung und die Anerkennung des Qualitätssicherungsprogramms ergeben. T2 - 19. Gefahrgut-Technik-Tage CY - Berlin, Germany DA - 16.11.2023 KW - ISO 16103 KW - Recycling-Kunststoffe KW - Gefahrgutverpackungen PY - 2023 AN - OPUS4-58894 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Fraňa, K. A1 - Attia, S. H. A1 - Otremba, Frank T1 - Numerical simulation of the filling process in the pressure bottle N2 - Parameter study for CFD in the bottle – grid resolution plays an important role on the temperature at the specific positions, 2D axi-symetrical calculation is a sufficient solution strategy in regards to the examined particular Problem. The intensity of filling process can be controlled by pressure “User defined function” provided by experiments. Numerical simulation demonstrated feasibility to predict temperature progress during the filling process successfully validated by experiments. The turbulent model k-w SST is the best strategy for the turbulent property calculations. The most intensive turbulent kinetic energy appeared in the middle region of the pressure bottle, the impact of the eddy viscosity on the wall was mostly in the wall region. T2 - ECMMM 2018 CY - Krakow, Poland DA - 10.02.2018 KW - Numerical simulation KW - Pressure bottle PY - 2018 AN - OPUS4-44177 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Linnemann, Konrad A1 - Ballheimer, Viktor A1 - Sterthaus, Jens A1 - Rolle, Annette A1 - Wille, Frank A1 - Vlassopoulos, Efstathios A1 - Papaioannou, Dimitrios T1 - Numerical simulation of spent fuel segments under transport loads N2 - Packages for the transport of spent nuclear fuel shall meet the International Atomic Energy Agency regulations to ensure safety under different Transport conditions. The physical state of spent fuel and the fuel rod cladding as well as the geometric configuration of fuel assemblies are important inputs for the evaluation of package capabilities under these conditions. Generally, the mechanical behavior of high burn-up spent fuel assemblies under Transport conditions shall be analyzed with regard to the assumptions which are used in the containment and criticality safety analysis. In view of the complexity of the interactions between the fuel rods as well as between the fuel assemblies, basket, and cask containment, the exact mechanical analysis of such phenomena is nearly impossible. The gaps in information concerning the material properties of cladding and pellet behavior, especially for the high burn-up fuel, make the analysis more complicated additionally. As a result, enveloping analytical approaches are usually used by BAM within the safety assessment of packages approved for transport of spent nuclear fuel. To justify the safety margins of such approaches additional analyses are necessary. In this paper, numerical simulations of a segment of a spent fuel assembly are presented. The segment modeled represents the part of a generalized BWR fuel assembly between two spacers. Explicit dynamic finite element calculations are performed to simulate the spent fuel behavior under regulatory defined accident conditions of transport. A beam element formulation is used for the modeling of the fuel rods representing the compound consisting of claddings and fuel pellets. The load applied is gathered from experimental drop tests with spent fuel casks performed at BAM. A hot cell bending test performed at JRC Karlsruhe is the basis for obtaining the material behavior of the fuel rods. The material properties are determined by simulating the test setup of JRC and optimizing the results to fit the experimental load deflection curve. The simulations of the fuel Assembly segment are used to get a better understanding about the loads on fuel rods under accident conditions of transport. T2 - 17th International High-Level Radioactive Waste Management Conference (IHLRWM 2019) CY - Knoxville, Tennessee, USA DA - 14.04.2019 KW - Spent Nuclear Fuel KW - Finite Element Simulation KW - Transport packages PY - 2019 AN - OPUS4-52047 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zaghdoudi, Maha A1 - Weber, Mike A1 - Kömmling, Anja A1 - Jaunich, Matthias A1 - Wolff, Dietmar T1 - Numerical modelling of compression stress relaxation and compression set of elastomer O-rings during aging N2 - Elastomer seals are used in many industrial applications due to their excellent mechanical properties at a wide range of temperatures. Their high versatility and recovery potential under several load conditions make them well suitable for the application in containers designed for transport, storage and/or disposal of radioactive materials. In containers for low and intermediate level radioactive waste, elastomer seals are used as barrier seals, and as auxiliary seals in storage and transportation casks (dual purpose casks) for heat generating radioactive waste, such as spent fuel and high-level waste. While a seal exchange at defined intervals is typical in many conventional applications, it is impossible or at least hard to perform when principles of minimization of radiation exposure have to be considered and prohibit an unnecessary cask handling. An extensive knowledge of the change of the elastomer’s properties during aging and the availability of reliable end-of-lifetime criteria to guarantee the permanent safe enclosure of the radioactive material is mandatory. As BAM is involved in most of the national cask licensing procedures and in the evaluation of cask-related long-term safety issues, great efforts have been already made and are still planned to scientifically support this task. Compression stress relaxation and compression set were identified as key indicators of elastomer long-term performance and quantitatively investigated in comprehensive test programs. Among other representative types of elastomers, specimens made from ethylene propylene diene rubber (EPDM) were tested before, during and after aging to capture the most important of their complex mechanical properties. In the presented study, exemplary results were used to simulate the compression stress relaxation and the compression set of elastomer O-rings during aging. Regarding the influence of temperature, the time temperature superposition principle is applied in the relaxation analysis of elastomer O-rings. The proposed model is implemented in the commercial finite element software ABAQUS/Standard® [1] with a sequential temperature displacement coupling. Numerical results match the experimental compression stress relaxation measurements well. The prediction of compression set values after long-term aging shows a relatively good agreement with the experimental results. Nevertheless, all input parameters derived from the specimen tests, additional assumptions concerning boundary conditions and modeling strategy are discussed with regard to the identified slight discrepancies. The possibility to extend the finite element model to represent the O-ring seal’s ability to recover after a (fast) partial release is taken into account T2 - ASME 2020 Pressure Vessels & Piping Conference (PVP2020) CY - Online meeting DA - 03.08.2020 KW - Stress relaxation KW - Ageing KW - Compression Set KW - O-ring KW - Sequential analysis KW - Simulation PY - 2020 AN - OPUS4-52135 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Weber, Mike A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Zencker, Uwe T1 - Numerical approach to determine the correct puncture bar length for the IAEA puncture bar drop test N2 - Among other mechanical tests the 1 meter drop onto a steel puncture bar shall be considered for accident safe packages for the transport of radioactive material. According with the IAEA regulations “the bar shall be of solid mild steel of circular section, 15.0 ± 0.5 cm in diameter and 20 cm long, unless a longer bar would cause greater damage…”. The most damaging puncture bar length can be estimated by iterative processes in numerical simulations. On the one hand, a sufficient puncture bar length has to guarantee that shock absorbers or other attachments do not prevent or reduce the local load application to the package, on the other hand, a longer and thus less stiff bar causes a smaller maximum contact force. The contrary influence of increasing puncture bar length and increasing effective drop height shall be taken into account if a shock absorber is directly placed in the target area. The paper presents a numerical approach to identify the bar length that causes maximum damage to the package. Using the example of two typical package masses the sensitivity of contact forces and puncture bar deformations to the initial length are calculated and assessed with regard to the international IAEA package safety requirements. T2 - ASME Pressure Vessels and Piping Conference 2018 CY - Prague, Czech Republic DA - 15.07.2018 KW - Length of puncture bar KW - Mechanical assessment KW - Numerical simulation KW - Puncture bar test KW - Transport of radioactive materials PY - 2018 SP - PVP2018-84614, 1 EP - 7 AN - OPUS4-46538 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Weber, Mike A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Zencker, Uwe T1 - Numerical Approach to Determine the Correct Length for the IAEA Puncture Bar Drop Test N2 - Among other mechanical tests the 1 meter drop onto a steel puncture bar shall be considered for accident safe packages for the transport of radioactive material. According with the IAEA regulations “the bar shall be of solid mild steel of circular section, 15.0 ± 0.5 cm in diameter and 20 cm long, unless a longer bar would cause greater damage…”. The most damaging puncture bar length can be estimated by iterative processes in numerical simulations. On the one hand, a sufficient puncture bar length has to guarantee that shock absorbers or other attachments do not prevent or reduce the local load application to the package, on the other hand, a longer and thus less stiff bar causes a smaller maximum contact force. The contrary influence of increasing puncture bar length and increasing effective drop height shall be taken into account if a shock absorber is directly placed in the target area. The paper presents a numerical approach to identify the bar length that causes maximum damage to the package. Using the example of two typical package masses the sensitivity of contact forces and puncture bar deformations to the initial length are calculated and assessed with regard to the international IAEA package safety requirements. T2 - ASME Pressure Vessels and Piping Conference 2018 CY - Prague, Czech Republic DA - 15.07.2018 KW - Transport of radioactive materials KW - Mechanical assessment KW - Puncture bar test KW - Length of puncture bar KW - Numerical simulation PY - 2018 AN - OPUS4-45785 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Weber, Mike A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Zencker, Uwe T1 - Numerical approach to determine a package dependent bar length for the iaea pin drop test N2 - The Federal Institute for Materials Research and Testing (BAM) is assessing the mechanical and thermal safety performance of packages for the transport of radioactive materials. Drop testing and numerical calculations are usually part of the safety case concepts, where BAM is performing the regulatory tests at their own test facility site. Among other mechanical tests the 1 meter drop onto a steel puncture bar shall be considered for accident safe packages. According to the IAEA regulations “the bar shall be of solid mild steel of circular section, 15.0 ± 0.5 cm in diameter and 20 cm long, unless a longer bar would cause greater damage…”. Particularly with regard to the German transport- and storage cask designs, often made from ductile cast iron, an accurate determination of the puncture bar length to guarantee a load impact covering the worst case scenario can be imperative. If the fracture mechanical proof for the cask material shall be provided by a test, small deviations in the concentrated load applied can be decisive for the question if the cask fails or not. The most damaging puncture bar length can be estimated by iterative procedure in numerical simulations. On the one hand, a sufficient puncture bar length shall guarantee that shock absorbers or other attachments do not prevent or reduce the local load application to the package, on the other hand, a longer and thus less stiff bar causes a smaller maximum contact force. The contrary influence of increasing puncture bar length and increasing effective drop height shall be taken into account if a shock absorber is directly placed in the target area. The paper presents a numerical approach to identify the bar length that causes maximum damage to the package. Using the example of two typical package masses the sensitivity of contact forces and puncture bar deformations to the initial length are calculated and assessed with regard to the international IAEA package safety requirements. T2 - PATRAM 2019 CY - New Orleans, LA, USA DA - 04.08.2019 KW - IAEA KW - 1-m-punch-bar-drop-test KW - Numerical approach KW - Bar length KW - Finite element analysis PY - 2019 AN - OPUS4-49013 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Günzel, Stephan A1 - Mair, Georg T1 - Normung und Sicherheit im Leichtbau - Sicherheitsbetrachtungen aus Sicht der Regelsetzung am Beispiel von Behältern für den Wasserstofftransport N2 - Es werden Methoden, Betrachtungen und Bewertungen der Sicherheit aus Sicht der Regelsetzung am Beispiel von Behältern für den Wasserstofftransport vorgestellt. T2 - 18. Cottbuser Leichtbauworkshop CY - Cottbus, Germany DA - 14.03.2024 KW - Sicherheit KW - Wasserstoff KW - Gefahrgut KW - Bewertung KW - Druckgefäß PY - 2024 AN - OPUS4-59697 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -