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Organisationseinheit der BAM
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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).
A reliable finite element analysis presupposes a qualified model of the object to be analyzed. The finite element mesh density may significantly vary throughout a model. A transition between dissimilar meshes can be accomplished by a gradual change of element size or by an interface with constraint conditions. Some issues may arise from such mesh transitions. Generally, a finer mesh can transmit signals of higher frequency than a coarser mesh. Stress wave propagation through the model could be affected by the transition region or the artificially induced interface. Stress waves generated within the fine mesh could be partly encapsulated by the surrounding coarse mesh. Therefore poor mesh transitions could result in reflections or shape changes of stress waves. A thin rod is investigated to demonstrate the effects.
This study supports the development of the ASME Guidance Document "Use of Explicit Finite Element Analysis for the Evaluation of Nuclear Transport and Storage Packages in Energy-Limited Impact Events".
Storage
(2018)
The whole conference focused on gaps in research concerning hydrogen and hydrogen safety. This presentation focus on storage aspects and shows the current gaps in research from the point of view of the authors. They have differences in background, from university via manufacturer and safety institute to hydrogen operating industry. The different purposes of storage are covered (onboard storage, stationary storage and transport of gases) as well as the different designs (steel to pure composite/plastic).
In den internationalen Gefahrgutvorschriften ist vorgeschrieben, dass Säcke und flexible Großpackmittel (Flexible Intermediate Bulk Container – FIBC) staubdicht sein müssen. Eine quantitative Definition des Terminus Staubdichtheit, wie in anderen Technikgebieten üblich, ist jedoch nicht gegeben. Auch geeignete Prüfverfahren zum Nachweis der Staubdichtheit sind in den Vorschriften nicht genannt.
In der Praxis der stichpunkartigen Kontrollen von Gefahrguttransporten durch die Schwerlastgruppe der Autobahnpolizei Münster werden immer wieder Austritte von pulverförmigen oder körnigen Gefahrgütern aus eigentlich intakten Säcken und FIBC detektiert. Es wird ein Überblick über die im Jahr 2018 festgestellten Gefahrgutaustritte aus diesen Gefahrgutverpackungen sowie eine systematische Einordnung hinsichtlich betroffener Bauarten und möglicher Ursachen gegeben.
Bei der Stofffreisetzung aus intakten Gefahrgutverpackungen liegt ein mechanischer Transport von Partikeln durch Leckkanäle, z. B. im Verschluss-, Naht- oder Wandungsbereich, vor. Generell kommen zwei Freisetzungswege in Frage: Einerseits eine Langzeit-Freisetzung während des Transports, hervorgerufen durch eine kombinierte Wirkung von Stapellast des Füllguts und Transportvibrationen; andererseits eine stoßartige Freisetzung.
Auf Grundlage von durchgeführten Untersuchungen hinsichtlich der stoßartigen Freisetzung pulverförmiger Stoffe aus Gefahrgutsäcken werden erste Lösungsansätze hin zu einer Verbesserung der Staubdichtheit von Gefahrgutsäcken und -FIBC vorgestellt. Es wird ein Ausblick auf nachfolgende Arbeiten gegeben.
Die Verfügbarkeit von Behältern für die Entsorgung nicht Wärme entwickelnder radioaktiver Abfälle im Endlager Konrad stellt ein wesentliches Element des nationalen Entsorgungskonzeptes für diese Abfallart dar. Grundlage für die Verfügbarkeit geeigneter Behälter sind typspezifische Bauartprüfungen, auf deren Grundlage eine Eignungs-feststellung in Form eines Prüfzeugnisses durch die Bundesgesellschaft für Endlagerung mbH (BGE), vormals Bundesamt für Strahlenschutz (BfS), erfolgt. Die Prüfgrundlagen sind in den durch das BfS (heute BGE) veröffent-lichten „Anforderungen an endzulagernde radioaktive Abfälle“ (Endlagerungsbedingungen) sowie der zugehörigen „Produktkontrolle radioaktiver Abfälle, radiologische Aspekte“ (PK) verankert. Die Eignungsfeststellung für eine Behälterbauart ist gleichzeitig die Grundlage für eine Behälterserienfertigung entsprechend den im Prüfzeugnis verankerten Spezifikationen und Randbedingungen.
Mit den Gesetzen zur Neuordnung der Organisationsstruktur im Bereich der Endlagerung (Mitte 2016) und zur Neuordnung der Verantwortung in der kerntechnischen Entsorgung (Mitte 2017) mit der Finanzierung des Kern-energieausstiegs wurden wesentliche Weichenstellungen im Hinblick auf den anstehenden Rückbau der bereits stillgelegten und in den kommenden Jahren noch stillzulegenden deutschen Kernkraftwerke vorgenommen. Bezüg-lich der nicht Wärme entwickelnden radioaktiven Abfälle führt dies zu einer spürbaren Intensivierung der Anstren-gungen zur Bereitstellung qualifizierter Gebinde für das Endlager Konrad, das nach aktueller Planung bis 2027 sei-nen Einlagerungsbetrieb aufnehmen soll. Dies wiederum führt zu einer erheblichen Verdichtung der Verfahren zur Behälterbauartprüfung, die allen Seiten (Antragsteller, BGE, Gutachter) erhebliche Anstrengungen abfordert.
Die Bundesanstalt für Materialprüfung und –forschung (BAM) ist auf Grundlage des Kap. 7 der o. g. „Produktkon-trolle …“ (PK) von der BGE mit den Behälterbauartprüfungen für das Endlager Konrad beauftragt. Hierbei ist eine Vielzahl von Anforderungen zu berücksichtigen, wozu neben den Anforderungen an Abfallbehälter gemäß Kap. 5 der Endlagerungsbedingungen weitere Anforderungen an die Verpackung (Kap. 3.2.2 PK), Kenngrößen (Kap. 3.5.1 PK) und schließlich die eigentliche Prüfung von Behältern/Verpackungen zählt (Kap. 7 PK). Letzteres beinhaltet die umfassende Behälterbeschreibung und –spezifikation, die Behälterauslegung, die thermischen und mechanischen Baumusterprüfungen (z.B. Brand- und Fallprüfungen), und schließlich die qualitätssichernden Maßnahmen für Her-stellung und Betrieb der Behälter. Neben der klassischen Bauartprüfung neuer Behältertypen spielt auch die Prü-fung bereits hergestellter Behälter, sog. Altbehälter, eine wesentliche Rolle, da sich etliche tausend Gebinde be-reits in der Zwischenlagerung befinden und nach Möglichkeit für das Endlager Konrad qualifiziert werden sollen.
Dieser Beitrag berichtet aktuell über den Umfang und Stand der laufenden Bauartprüfungen bei der BAM unter Be-rücksichtigung der besonderen Herausforderungen und der zuletzt erzielten Fortschritte. Dabei erfordert die paral-lele Bearbeitung der zahlreichen Verfahren einen verstärkten Koordinierungsbedarf hinsichtlich vergleichbarer fach-licher Aspekte sowie hinsichtlich Priorisierung und Ressourceneinsatz. Bei den experimentellen Nachweisen (Fall- und Brandversuche) betrifft das hinsichtlich der Nutzung der Versuchseinrichtungen bei der BAM die Koordination mit anderen Prüfaufträgen, wie z. B. verkehrsrechtliche Baumusterprüfungen. Schließlich erfordern diverse Fach-fragen zur Interpretation der Anforderungen aus Endlagerungsbedingungen und Produktkontrolle intensive Abstim-mungsprozesse zwischen BAM, BGE und Antragstellern. Wichtige Ergebnisse mit übergeordneter Bedeutung wer-den in Form erläuternder Fachnotizen durch die BGE veröffentlicht und können so bei zukünftigen Antragsverfahren berücksichtigt werden.
The characterization of spent fuel and radioactive waste is essential in the evaluation of the ability of these materials to meet acceptance criteria. Prior to determining a method for spent fuel characterization, it is necessary to identify the type of data required to support safety and other analyses for the storage, transportation and final disposal of spent fuel. BAM’s understanding and capabilities in the field of spent fuel characterization are presented for the scope of a coordinated research project on the topic.
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 a Consultancy Meeting, BAM as contributor to Task 3 presented current results of the failure analysis of irradiated ZIRLO® claddings under conditions of the Ring Compression Test.
German packages for the transport of spent nuclear fuel are assessed with respect to specific transport conditions which are defined in the safety regulations of the International Atomic Energy Agency. In general, gastight fuel rods constitute the first barrier of the containment system. The physical state of the spent fuel and the fuel rod cladding as well as the geometric configuration of the fuel assemblies are important inputs for the evaluation of the package safety under transport conditions. The objective of this paper is to discuss the methodologies accepted by German authority BAM for the evaluation of spent fuel behavior within the package design approval procedure. Specific test conditions will be analyzed with regard to assumptions to be used in the activity release and criticality safety analysis. In particular the different failure modes of the fuel rods, which can cause release of gas, volatiles, fuel particles or fragments, have to be properly considered in these assumptions. The package as a mechanical system is characterized by a complex set of interactions, e.g. between the fuel rods within the assembly as well as between the fuel assemblies, the basket, and the cask containment. This complexity together with the limited knowledge about the material properties and the variation of the fuel assemblies regarding cladding material, burn-up and the operation history makes an exact mechanical analysis of the fuel rods nearly impossible. The application of sophisticated numerical models requires extensive experimental data for model verification, which are in general not available. The gaps in information concerning the material properties of cladding and pellets, especially for the high burn-up fuel, make the analysis more complicated additionally, and require a conservative approach. In this context some practical approaches based on experiences by BAM within safety assessment of packages for transport of spent fuel will be discussed. Ongoing research activities to investigate SNF mechanical behavior in view of gas and fissile material release under transport loads are presented.
Tanks with capacity larger than 700 m3, could be exposed to a resonance excitation when subjected to earthquake motions, regardless of the fill level. Further studies to assess the dynamic forces linked to such resonance and close-to-resonance situations, in a context of a standard overloading situation due to sloshing forces.
Lithium-ion batteries usually consist of numerous individual cells. There is ongoing discussion about enhancing sustainability by considering the replacement of heavily aged or damaged cells. Nevertheless, the planned replacement of individual cells poses significant challenges in ensuring the required reliability and safety of the refurbished device.
Zur Charakterisierung von Brandschutzbeschichtungssystemen für Gas-
Lagertanks ist ein Großbrandversuch erforderlich. Zur Ermittlung der produktspezifischen Beschichtungsdicke sind Plattenbrandversuche notwendig. Für Brandprüfungen existieren verschiedene Brandkurven (z.B. ETK, Hydrocarbonkurve, Schwelbrandkurve, BAM-Kurve) um Prüfmuster je nach Anwendungsfall zu zertifizieren. Diese Brandkurven unterscheiden sich hinsichtlich des Temperaturgradienten. Zur Gewährleistung der Übertragbarkeit der BAM-Prüföfen (Kleinprüfstand DIN 4102-8 (Klep) und 1-m³ Ofen) auf die NORM ISO 21843 (2018-09) ist es erforderlich einen Wärmeintrag von 90 – 120 kW/m² in das Prüfmuster zu garantieren.
Ein Aspekt des Gefahrguttransportes, der an Bedeutung in den letzten Jahren zugenommen hat, ist die Versorgung von Wasserstofftankstellen und anderen H2-Großverbrauchern über die Schiene aber insbesondere über die Straße.
Mit Blick auf die primäre Form der Speicherung wird der Begriff der Sicherheit über den Aspekt der Häufigkeit eines definierten Ereignisses erläutert und auf die Besonderheiten der Druckgefäße aus Verbundwerkstoffen hingewiesen, wie auch den regulatorischen Hintergrund der Lebensdauerüberprüfung nach 15 Jahren nach den Vorgaben der zuständigen Behörde. In Deutschland sind diese Vorgaben in der BAM-Gefahrgutregel 021 geregelt, die in der GGR 022 durch eine Regelung zur Wiederkehrenden Prüfung dieser Umschließungen ergänzt wird.
Beide BAM-Gefahrgutregeln basieren auf einem probabilistischen Ansatz und einer Konsequenzabschätzung über das Druck-Volumen-Produkt der Druckgefäße. Die neu im Recht verankerte EN 17339 ist die erste Norm, die speziell fest montierte Compositespeicher für den Wasserstofftransport regelt. Sie ermöglicht eine erhebliche Gewichtreduktion und führt eine Obergrenze für das Druckvolumen ein.
Es wird kurz erläutert, dass gerade mit Blick auf Wasserstofftransporte über eine Arbeitsgruppe der Vereinten Nationen eine Begrenzung des Konsequenzpotentials in das internationale Recht eingeführt werden soll und welche Kriterien bei der systematischen Ermittlung des akzeptierten Wertes von 1.5 Mio bar Liter Einfluss haben.
Mit Blick auf die Energiewende sieht es die BAM als besonders wichtig an, die Transportkosten zu senken, indem der Prüfaufwand reduziert und gleichzeitig die Erkenntnistiefe aus der betrieblichen Überwachung verbessert wird. Hierzu muss die Datenbasis für die probabilistische Bewertung der Lebensdauer von zerstörenden Prüfungen auf zerstörungsfreie Prüfungen umgestellt werden und idealerweise die 100% Prüfung zumindest in der ersten Hälfte des sicheren Lebens auf Stichproben reduziert werden.
Dies und andere Aufgaben, die wichtig für eine sichere und attraktive Wasserstoffwirtschaft sind werden von dem Kompetenzzentrum H2Safety@BAM bearbeitet, dass in seinen Grundzügen kurz vorgestellt wird.
Der Beitrag beinhaltet Themen vom H2Safety@BAM-Kompetenzfeld Sensorik, Analytik und zertifizierte Referenzmaterialien (SensRef) mit Fokus auf Mess- und Prüfverfahren mit verschiedenen Sensortechnologien und Ultraschallwellen:
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.
Second life für E-Akkus
(2021)
The stacking sequence of a real scale type IV pressure vessels has been found. Feasibility study of a multiscale model has been carried out by modifying the original stacking sequence. All of the results were displayed in a Sample Performance Chart (SPC), where different burst pressure in terms of mean and scatter had been found.
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.
Safety criteria for the transport of hydrogen in permanently mounted composite pressure vessels
(2019)
The recent growing of the net of hydrogen fuelling stations increases the demands to transport compressed hydrogen on road by tube-trailers in composite pressure vessels. As transport regulation the ADR is applicable in Europe and adjoined regions and used for national transport in EU. This regulation provides requirements based on the burst pressure of each individual pressure vessel, regardless the capabilities of the transported hydrogen and relevant consequences resulting from worst case scenarios. In 2012, BAM (German Federal Institute for Materials Research and Testing) introduced consequence-dependent requirements and established them in national requirements concerning the “UN service life checks” etc.) to consider the transported volume and pressure of gases. However, this results in a stringent requirement in case of using large pressure vessels (tubes) on tube-trailers. In the studies presented here, the key safety factors for using hydrogen trailers are identified and reviewed through some safety measures from some countries like Japan, USA and China. Subsequently, the risk, chance, failure consequences of using trailers are evaluated, in addition, the difficulties for approving huge pressure vessels (large tubes) are addressed. There, a maximum acceptable pressure-volume product is defined. Finally, a performance-based criterion for the balance of chance and risk of hydrogen trailers is suggested to add into regulations and consequently into standards for hydrogen trailers.
The presentation explains the intended way of BAM in tackling the safety issues in the project TAHYA.
The way how the term “safety” is used in TAHYA 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 current regulations are. Thus, a concept for optimization of relevant regulations, codes and standards will be elaborated during the project. For this purpose, it is helpful to improve the currently operated tool for Monte Carlo simulation, which will need additional data for monitoring the outcome. Strength data, that will be determined by BAM and the other partners during the already agreed test program can be used for this purpose without additional effort.
In this lecture, the safety assessment of hydrogen gas storage systems is presented using the example of composite pressure vessels. The main element is a probabilistic approval approach based on five steps. Firstly, the testing and evaluation of properties at the beginning of life are shown. Secondly, methods for artificial aging and the effect on the residual strength are presented. Thirdly, testing against dedicated accidents is introduced. Fourthly, effects on the surveillance of production quality are discussed. Finally, degradation and the end of life are estimated. Background information and examples are given for each step. The assessment presented is a method applicable for many safety-related systems.
In this lecture, the safety assessment of hydrogen gas storage systems is presented using the example of composite pressure vessels. The main element is a probabilistic approval approach based on five steps. Firstly, the testing and evaluation of properties at the beginning of life are shown. Secondly, methods for artificial aging and the effect on the residual strength are presented. Thirdly, testing against dedicated accidents is introduced. Fourthly, effects on the surveillance of production quality are discussed. Finally, degradation and the end of life are estimated. Background information and examples are given for each step. The assessment presented is a method applicable for many safety-related systems.
In this lecture, the safety assessment of hydrogen gas storage systems is presented using the example of composite pressure vessels. The main element is a probabilistic approval approach based on five steps. Firstly, the testing and evaluation of properties at the beginning of life are shown. Secondly, methods for artificial aging and the effect on the residual strength are presented. Thirdly, testing against dedicated accidents is introduced. Fourthly, effects on the surveillance of production quality are discussed. Finally, degradation and the end of life are estimated. Background information and examples are given for each step. The assessment presented is a method applicable for many safety-related systems.
In this lecture, the safety assessment of hydrogen gas storage systems is presented using the example of composite pressure vessels. The main element is a probabilistic approval approach based on five steps. Firstly, the testing and evaluation of properties at the beginning of life are shown. Secondly, methods for artificial aging and the effect on the residual strength are presented. Thirdly, testing against dedicated accidents is introduced. Fourthly, effects on the surveillance of production quality are discussed. Finally, degradation and the end of life are estimated. Background information and examples are given for each step. The assessment presented is a method applicable for many safety-related systems.
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.
In this presentation safety aspects of hydrogen transportation are discussed. At first, the regulatory background and level of safety are presented. In the second part, the modelling of consequence due to sudden rupture of pressure receptacles is explained. Finally, the results are used to define a limit for consequence to enable an acceptable and safe transport of hydrogen.
Hydrogen is a central component of the energy transition and the European Green Deal for a climate-neutral Europe. To be able to achieve the targets defined by 2045, the EU and the German government have drafted a framework for action and are making long-term investments in research, development and the rapid implementation of innovative hydrogen technologies.
The conditions for a successful energy transition and the economic use of green hydrogen as a clean energy carrier are Hydrogen readiness and a rapid market ramp-up, as well as the establishment of the necessary value chains in the national and European framework. Reliable quality and safety standards are the prerequisite for ensuring safety of supply and environmental compatibility and for creating trust in these technologies.
BAM has bundled its expertise in the field of hydrogen technologies into a competence center H2Safety@BAM to create confidence in the technology and to support the hydrogen strategies of the German government and the EU. The topic of hydrogen has been current at BAM for more than one hundred years and is also currently the focus of numerous research and cooperation activities. The competence centre H2Safety@BAM and its vision of “We build trust in hydrogen technologies” will be presented with its many safety-related topics, which can be found throughout the entire hydrogen value chain. Two deep dives will present the results on projects dealing with the design-to-cost issue of classical pressurized gas storage containments and the consequences of the release of liquid hydrogen, which will be roughly compared to the release of ammonia.
In Germany, BAM is the competent authority in the field of dangerous goods transport. The international dangerous goods transportation rules are presented and their adaptation into German law is described. BAM is responsible for dangerous goods packaging testing, manufacturer surveillance, packaging approvals and inspection of IBC and provides “Gefahrgutregeln” (GGR) to define the processes, e.g. of dangerous goods packagings approvals and surveillance.”
Auf Initiative der Europäischen Kommission ist die Europäische Eisenbahn Agentur seit einigen Jahren damit beauftragt, in Zusammenarbeit mit einer Reihe von Expertinnen und Experten aus Europa harmonisierte Leitlinien für das Risikomanagement im Gefahrgutsektor zu entwickeln und fortzuschreiben.
Der Vortrag informiert über die Entwicklung und den Stand der Arbeiten zum „Inland Transport of Dangerous Goods Risk Management Framework“ (RMF):
- Warum gibt es das Risk Management Framework?
- Wer ist an der Entwicklung beteiligt?
- Wie ist das Risk Management Framework aufgebaut, an wen richtet es sich und was beinhaltet es?
- Welche grundsätzlichen Fragen sind zu klären?
- Wie geht es weiter?
For transport operations according IAEA regulations SSR-6, the package shall be securely stowed and the package shall be capable to withstand specific effects, e.g. accelerations, during routine transport conditions. The supporting IAEA Advisory Material SSG-26 provides information how to do that. General information and detailed load factors for use in safety demonstrations are provided.
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 factors vary between different countries and lead to difficulties during the validation of foreign approval certificates. The background of the existing guidance including specified load values was not clear enough. The application of specified values and the boundary conditions, i.e. transport conditions, seemed to be improvable.
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. In addition, complementary questions relative to the operational aspects were discussed. Revised load values for different transport modes were proposed. The values are derived from standards and include safety factors now.
As a result of those discussions, the international working group wrote new guidance material for stowage in transport, addressing all the previously quoted topics.
The nuclear phase out in Germany will lead to a challenge finding skilled staff for all areas in nuclear business. Transport of spent fuel and high-level nuclear waste is an ongoing task over the next decades during the decommissioning of nuclear power plants and after the interim storage. The international regulations were adapted and address the issue of transports after storage now. The topic of aging and assessment of the development of the state-of-art technology are in focus. German research funds are supporting the investigations of future challenges of transport and storage of the nuclear heritage. BAM is involved and works on several topics related to the aging issue of packages. The behaviour of spent fuel claddings, long-term behaviour of metal and elastomeric gaskets and sensor/monitoring techniques of waste disposal are examples of research fields.
Biofuels including ethanol and biodiesel (FAME) represent a renewable fuel alternative to petroleum-derived transport fuels. The aim of this work was to study the interaction between high density polyethylene (HDPE) with permeation barriers in form of polyamide (PA) and fluorination, and biofuels such as E85 (fuel with 85 % ethanol), biodiesel and B10 (heating oil with 10 % biodiesel). 10 l jerrycans made of polyethylene with permeation barrier of PA were filled with E85 and biodiesel and exposed to temperatures of 20 °C and 40 °C for 5 years. Half of the 20 l jerrycans of HDPE for filling with B10 were fluorinated at the inner layer to prevent permeation before the exposure. Tensile properties were determined once a year, and FTIR-spectroscopy was used to evaluate possible changes.
The tensile properties tensile strength and breaking elongation of HDPE jerrycan cuttings with permeation barrier decreased, but not significantly, after immersion in E85, biodiesel and B10. The elasticity modulus of the polyethylene grades was especially reduced during exposure to E85.
The FTIR spectra of HDPE jerrycan cuttings with permeation barrier showed that immersion tests for five years with the test fuels at 20 °C and 40 °C did not lead to a decomposition of the permeation barriers.
In Europe biodiesel gained from rapeseeds are considered as an alternative to common fossil fuels due to its environmental performance and its independence from import of raw materials. Biodiesel is also suitable to serve as blending component to heating oil. In that case, it must be considered that changes of fuel composition might cause material degradation.
The objective of this research was to investigate the resistance of metallic materials exposed to heating oil, heating oil blend B20 with 20 % biodiesel and pure biodiesel. Furthermore, the resistance of metals to eight-year aged B10 and six-year aged pure biodiesel was evaluated. Ageing of biodiesel forms acids and water which might propagate metal corrosion. The investigated metals (aluminium, unalloyed steel, austenitic CrNi-steel, copper, die cast zinc and brass) are commonly used for components in middle distillate facilities.
According to DIN 50905-4 the immersed metals were exposed in a climate chamber at 50°C for 4 weeks. The metallic materials were evaluated as resistant if the annual corrosion rate due to uniform corrosion remained under 0.1 mm/year and no localized corrosion in the form of pitting occurred.
The corrosion rates of the exposed materials stayed far below the limit of 0.1 mm/year for all tested fuels. An exception was die cast zinc ZP0410 in eight-year aged B10; a corrosion rate up to 0.3 mm/year due to uniform corrosion was measured. In no case localized corrosion occurred. Copper and brass caused discolouration of biodiesel from yellow to green.
In conclusion, the tested metallic materials were resistant in heating oil, heating oil blend B20 and pure biodiesel at 50 °C. Even the metals exposed to six-year aged biodiesel and eight-year aged B10 showed no uniform or localized corrosion; except for zinc, which was not resistant in eight-year aged B10.
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.
Übersicht über die gefahrgutrechtlichen Anforderungen zur Bauartprüfung und dem Qualitätsmanagement für Verpackungen für nicht zulassungspflichtige Versandstücke.
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.
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.
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.
Recent developments in standards and IAEA guidance material for package load attachment points
(2018)
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.
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.
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.
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.
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
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.
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.