TY - CONF A1 - Völzke, Holger T1 - Integration across storage, transportation and disposal – important elements of the German program N2 - This presentation addresses the following issues. Unexpected changes in national nuclear policy have significantly affected spent fuel management strategies. The initial German spent fuel and HLW disposal concept has been delayed and finally “reset” by federal law in 2013. Repository site selection criteria and procedures will be defined by the Disposal Commission’s report end of June 2016. Final site selection should be finished by 2031. The consistent German concept of dry interim storage in dual purpose casks has proven to be a safe and secure spent fuel management strategy. The need for the extended interim storage of spent fuel and HLW casks towards disposal implicates additional challenges for the nuclear waste management strategy in Germany. Recently, governmental research programs have been adjusted to address technical and scientific issues also in the predisposal area. Interim storage, subsequent transportation, and final disposal are closely linked. Integrated approaches concerning waste package designs and operations are supposed to be beneficial for the establishment of efficient long-term spent fuel and HLW management strategies. T2 - Reset of U.S. Nuclear Waste Management Strategy and Policy Meeting CY - Washington, D.C., USA DA - 17.05.2016 KW - Nuclear waste management KW - spent fuel storage KW - extended storage KW - nuclear waste disposal PY - 2016 AN - OPUS4-36354 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Stajanca, Pavol T1 - Perfluorinated polymer optical fibers for gamma radiation monitoring N2 - The sensitivity of low loss perfluorinated polymer optical fiber (PF-POF) to gamma radiation is investigated for on line radiation monitoring purposes. The radiation induced attenuation (RIA) of a commercial PF-POF based on Cytop material is measured in the visible spectral region. The fiber RIA shows strong wavelength dependence with rapid increase towards the blue side of the spectrum. The wide range of radiation sensitivities is available via careful selection of appropriate monitoring wavelength. The accessible sensitivities span from 1.99 ± 0.01 dBm⁻¹/kGy measured at 890 nm to 140.9 ± 0.6 dBm⁻¹/kGy measured at 460 nm. The fairly high radiation sensitivity as well as its wide tunability makes the fiber a promising candidate for a broad range of applications. T2 - Sixth European Workshop on Optical Fibre Sensors CY - Limerick, Ireland DA - 31.05.2016 KW - Perfluorinated polymer optical fiber KW - Cytop KW - Gamma radiation KW - Optical fiber sensors KW - Radiation dosimetry PY - 2016 DO - https://doi.org/10.1117/12.2235528 AN - OPUS4-36460 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Stajanca, Pavol A1 - Mihai, L. A1 - Sporea, D. A1 - Negut, D. A1 - Krebber, Katerina ED - Lewis, E. T1 - Perfluorinated polymer optical fiber for gamma radiation monitoring N2 - The sensitivity of low-loss perfluorinated polymer optical fiber (PF-POF) to gamma radiation is investigated for on-line radiation monitoring purposes. The radiation-induced attenuation (RIA) of a commercial PF-POF based on Cytop material is measured in the visible spectral region. The fiber RIA shows strong wavelength dependence with rapid increase towards the blue side of the spectrum. The wide range of radiation sensitivities is available via careful selection of appropriate monitoring wavelength. The accessible sensitivities span from 1.6 ± 0.2 dBm-1/kGy measured at 750 nm to 18.3 ± 0.7 dBm-1/kGy measured at 420 nm. The fairly high radiation sensitivity as well as its wide tunability makes the fiber a promising candidate for a broad range of applications. T2 - Sixth European Workshop on Optical Fibre Sensors CY - Limerick, Ireland DA - 31.05.2016 KW - Perfluorinated polymer optical fiber KW - Cytop KW - gamma radiation KW - optical fiber sensors KW - radiation dosimetry PY - 2016 UR - http://proceedings.spiedigitallibrary.org/proceeding.aspx?articleid=2525047&resultClick=1 DO - https://doi.org/10.1117/12.2235528 VL - 9916 SP - 99160H-1 EP - 99160H-4 PB - SPIE CY - Bellingham, WA, USA AN - OPUS4-36461 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Sentker, K. A1 - Yildirim, Arda T1 - Columnar axial orientation of discotic liquid crystals in nanoporous solids N2 - Successful implementation of an optical polarimetry measurement setup. Due to wall anchoring interactions HAT6 embedded in an untreated alumina membrane exhibits a radial orientation for pore sizes in between 30 nm and 80 nm. Embedded in large membranes, pore size of 180 nm, HAT6 forms the favored hexagonal columnar phase along the pore axis. T2 - 80. Jahrestagung der DPG und DPG-Frühjahrstagung CY - Regensburg, Germany DA - 06.03.2016 KW - Discotic Liquid Crystals KW - Nanoconfinement KW - Orientation PY - 2016 AN - OPUS4-36479 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schröder, Volkmar T1 - Sicherheitstechnische Eigenschaften von Erdgas-Wasserstoff-Gemischen - Auswirkungen auf den Explosionsschutz N2 - Im Beitrag werden die sicherheitstechnischen Eigenschaften von Wasserstoff diskutiert. Die Einspeisung von Wasserstoff ins Erdgasnetz wird im Hinblick auf mögliche Gefahren im Explosionsschutz durch die Veränderung von sicherheitstechnischen Kenngrößen unter Prozessbedingungen betrachtet. T2 - DVGW-Seminar "Gasinfrastruktur für Erdgas-H2-Gemische" CY - Bremen, Germany DA - 03.09.2020 KW - Wasserstoff KW - Explosionsschutz KW - Sicherheitstechnische Eigenschaften KW - Erdgasinfrastruktur PY - 2020 AN - OPUS4-51288 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Ballheimer, Viktor A1 - Quercetti, Thomas A1 - Scheidemann, Robert A1 - Wille, Frank T1 - Mechanical and thermal assessment by BAM of a new package design for the transport of SNF from a german research reactor N2 - For disposal of the research reactor of the Technical University Munich FRM II a new transport and storage cask design was under approval assessment by the German authorities on the basis of International Atomic Energy Agency (IAEA) requirements. The cask body is made of ductile cast iron and closed by two bolted lid systems with metal seals. The material of the lids is stainless steel. On each end of the cask the wood-filled impact limiters are installed to reduce impact loads to the cask under drop test conditions. In the cavity of the cask a basket for five spent fuel elements is arranged. This design has been assessed by the Bundesanstalt für Materialforschung und -prüfung (BAM) in view to the mechanical and thermal safety analyses, the activity release approaches, and subjects of quality assurance and surveillance for manufacturing and operation of the package. For the mechanical safety analyses of the package a combination of experimental testing and analytical/numerical calculations were applied. In total, four drop tests were carried out at the BAM large drop test facility. Two tests were carried out as a full IAEA drop test sequence consisting of a 9m drop test onto an unyielding target and a 1m puncture bar drop test. The other two drop tests were performed as single 9m drop tests and completed by additional analyses for considering the effects of an IAEA drop test sequence. The main objectives of the drop tests were the investigation of the integrity of the package and its safety against release of radioactive material as well as the test of the fastening system of the impact limiters. Furthermore, the acceleration and strain signals measured during the tests were used for the verification of finite-element (FE) models applied in the safety analysis of the package design. T2 - Pressure Vessels & Piping Conference 2020 CY - Online meeting DA - 03.08.2020 KW - Mechanik KW - radioaktives Material KW - Transportbehälter KW - Antragsverfahren KW - Zulassungen KW - Typ-B Versandstück KW - Thermik PY - 2020 VL - 2020 SP - 1 EP - 7 PB - ASME CY - New York AN - OPUS4-51103 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Hicke, Konstantin T1 - Infrastruktur- und Anlagenmonitoring mit verteilter faseroptischer akustischer Sensorik N2 - Anwendungsfelder von verteilter faseroptischer akustischer Sensorik (DAS) werden anhand von früheren, gegenwärtigen und zukünftigen Projekten an der BAM vorgestellt und die Leistungsfähigkeit von DAS demonstriert. Die dargestellten Anwendungen sind Monitoring von Rohrleitungen, von Unterseekabeln, von Zügen und Gleisen, von Brücken, von Strassen und Verkehr, von Erdbebenauswirkungen in urbanen Gebieten, von Bohrlöchern im Kontext Erdgasspeicher und für Exploration und Monitoring von Untergründen für Geothermie-Anwendungen. T2 - Sitzung des VDI/VDE-GMA FA 2.17 CY - Online meeting DA - 24.09.2020 KW - Verteilte faseroptische Sensorik KW - Verteilte faseroptische akustische Sensorik KW - DAS KW - Infrastrukturmonitoring KW - Zustandsüberwachung PY - 2020 AN - OPUS4-51304 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Heuser, Lina A1 - Sobek, P. T1 - Sintering of silver-alkali zinc borate glass composites N2 - High conductive silver-glass-metallization-pastes are key components in photovoltaics and advanced microelectronics. However, the underlying mechanisms of liquid phase sintering as silver dissolution, diffusion and reprecipitation are poorly understood so far. In the current work, the influence of different network modifier in alkali-zinc-borate paste-glasses on liquid phase sintering of silver-glass-composites was studied. Therefore, silver-glass-composites containing 30 vol% glass were prepared, using low melting X2O-ZnO-B2O3 glasses with X = Na, Li, and Rb (NZB, LZB, and RZB). Glass transition temperature, viscosity, glass-silver wetting, crystallization and sintering behavior was studied by means of thermal analysis, dilatometry, heating microscopy and microscopy. Similar glass transition temperatures of 450 °C (RZB), 460 °C (LZB) and 465 °C (NZB) were found by means of thermal analysis for glasses under study. Also, all glasses have a similar crystallization onset at about 550 °C, even though exhibiting with a different degree of crystallization. Despite these similarities, however, the sintering behavior, measured in terms of area shrinkage, significantly differs for the composites. This finding indicates a different degree of silver dissolution. Assuming that dissolved silver reduces the viscosity, this effect could explain why glass crystallization starts at lower temperature in the composites. For example, the crystallization peak of LZB at 629 °C measured for pure glass powder compacts was decreased to 586 °C for the composite. Confirmatively, microstructure analyses indicate different degrees of silver dissolution, as e.g. revealed by different amount of silver precipitates within the residual glass phase, and reprecipitation. Best silver dissolution appeared for the RZB glass. Nevertheless, the final densification of RZB was retarded probably due to swelling and crystallization. T2 - XRM Workshop CY - Halle, Germany DA - 03.03.2020 KW - Silver-glass-metallization-paste KW - Sintering KW - Alkali ions PY - 2020 AN - OPUS4-51243 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Tschirschwitz, Rico T1 - BAM-Aktivitäten im Bereich Elektrische Energiespeicher N2 - Der Beitrag stellt die aktuellen, relevanten BAM-Projekte im Bereich der Sicherheit elektrischer Energiespeicher vor. Weiterhin werden derzeitige Kooperationen mit der vfdb präsentiert. T2 - 82. Sitzung Referat 10, Umweltschutz der vfdb (Vereinigung zur Förderung des deutschen Brandschutzes e.V.) CY - Online meeting DA - 04.11.2020 KW - Behälterversagen KW - Fahrzeugbrand KW - Auswirkungsbetrachtung KW - Alternative Antriebe KW - Fragment PY - 2020 AN - OPUS4-51522 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gräf, T. A1 - Hicke, Konstantin A1 - Heidmann, G. A1 - Kölling, M. A1 - Menge, M. A1 - Vaterrodt, K. T1 - Integrierte lokale und verteilte faseroptische Sensorik zum flächende-ckenden Online-Monitoring von Kabelanlagen und Betriebsmitteln N2 - Faseroptische Sensorsysteme bieten heute die Möglichkeit des Online-Monitorings von sensiblen, für die Energieversorgung wichtigen Betriebsmitteln. Insbesondere Hochenergiekabel, wie diese sowohl im Offshore- als auch im Onshorebereich eingesetzt werden, sind prädestiniert für eine zustandsorientierte Überwachung. Gerade Hochspannungshochenergiekabel sind Betriebsmittel, die im Falle eines Ausfalls durch Schäden mit hohen Reparatur- und Folgekosten verbunden sind. Mit dem Einsatz von faseroptischen Sensoren sind mechanische Einflüsse wie Vibrationen z. B. verursacht durch Ankerfall, Temperaturhotspots oder auch Teilentladungsaktivitäten an dezidierten vulnerablen Stellen wie Kabelendverschlüssen oder –muffen über längere Kabelstrecken detektierbar. Der Einsatz von im Rahmen des Verbundprojekts Monalisa entwickelter faseroptischer Diagnosetechnik in Verbindung mit faseroptischen Sensoren wird hier aufgezeigt. T2 - VDE Fachtagung Hochspannungstechnik CY - Online-Meeting DA - 09.11.2020 KW - Verteilte faseroptische Sensorik KW - Energiekabel KW - Zustandsüberwachung KW - Infrastrukturmonitoring KW - Eingebettete Sensorik PY - 2020 SN - 978-3-8007-5353-6 SN - 0341-3934 VL - 2020 SP - 1 EP - 6 PB - VDE Verlag GmbH CY - Berlin AN - OPUS4-51559 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Müller, Lars T1 - Drop tests assessment of internal shock absorbers for packages loaded with encapsulations for damaged spent nuclear fuel N2 - Damaged spent nuclear fuel (DSNF) can be loaded in German dual-purpose casks (DPC) for transport and interim storage. Encapsulations are needed to guarantee a safe handling and a tight closure, separated from the package enclosure. These encapsulations shall be durable and leak-tight for a long storage period, because they are usually not accessible within periodical inspections of the DPC. Due to the general design of DPCs for standard fuel assemblies, specific requirements have to be considered for the design of encapsulations for DSNF to ensure the loading in existing package designs. Especially the primary lid system of a DPC is designed for maximum loads due to the internal impact of the content during drop test conditions. The main difference of encapsulations for damaged spent nuclear fuel is that they have usually a much higher stiffness than standard fuel assemblies. Therefore the design of an internal shock absorber, e.g. at the head of an encapsulation is required to reduce mechanical loads to the primary lid system during impacts. BAM as part of the German competent authority system is responsible for the safety assessment of the mechanical and thermal package design, the release of radioactive material and the quality assurance of package manufacturing and operation. Concerning the mechanical design of the encapsulation BAM was involved in the comprehensive assessment procedure during the package design approval process. An internal shock absorber was developed by the package designer with numerical analyses and experimental drop tests. Experimental drop tests are needed to cover limiting parameters regarding, e.g. temperature and wall thickness of the shock absorbing element to enable a detailed specification of the whole load-deformation behavior of the encapsulation shock absorber. The paper gives an overview of the assessment work by BAM and points out the main findings which are relevant for an acceptable design of internal shock absorbers. The physical drop tests were planned on the basis of pre-investigations of the applicant concerning shape, dimension and material properties. In advance of the final drop tests the possible internal impact behavior had to be analyzed and the setup of the test facility had to be validated. The planning, performance and evaluation of the final drop tests were witnessed and assessed by BAM. In conclusion it could be approved that the German encapsulation system for damaged spent nuclear fuel with shock absorbing components can be handled similar to standard fuel assemblies in existing package designs. T2 - Pressure Vessels & Piping Conference 2020 CY - Online meeting DA - 03.08.2020 KW - Drop tests KW - Internal shock absorber KW - Design assessment of RAM packages KW - Encapsulations for damaged spent nuclear fuel PY - 2020 AN - OPUS4-51550 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Bonse, Jörn T1 - Quo vadis LIPSS? - Recent and future trends on laser-induced periodic surface structures N2 - Nanotechnology and lasers are among the most successful and active fields of research and technology that have boomed during the past two decades. Many improvements are based on the controlled manufacturing of nanostructures that enable tailored material functionalization for a wide range of industrial applications, electronics, medicine, etc., and have already found entry into our daily life. One appealing approach for manufacturing such nanostructures in a flexible, robust, rapid, and contactless one-step process is based on the generation of laser-induced periodic surface structures (LIPSS). This Perspectives article analyzes the footprint of the research area of LIPSS on the basis of a detailed literature search, provides a brief overview on its current trends, describes the European funding strategies within the Horizon 2020 programme, and outlines promising future directions. KW - Laser-induced periodic surface structures (LIPSS) KW - Direct laser interference patterning (DLIP) KW - Surface functionalization KW - Literature survey KW - European funding strategies PY - 2020 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-513530 DO - https://doi.org/10.3390/nano10101950 SN - 2079-4991 VL - 10 IS - 10 SP - 1950-1 EP - 1950-19 PB - MDPI CY - Basel AN - OPUS4-51353 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Bonse, Jörn A1 - Gräf, S. T1 - Maxwell Meets Marangoni — A Review of Theories on Laser‐Induced Periodic Surface Structures N2 - Surface nanostructuring enables the manipulation of many essential surface properties. With the recent rapid advancements in laser technology, a contactless large‐area processing at rates of up to m2 s−1 becomes feasible that allows new industrial applications in medicine, optics, tribology, biology, etc. On the other hand, the last two decades enable extremely successful and intense research in the field of so‐called laser‐induced periodic surface structures (LIPSS, ripples). Different types of these structures featuring periods of hundreds of nanometers only—far beyond the optical diffraction limit—up to several micrometers are easily manufactured in a single‐step process and can be widely controlled by a proper choice of the laser processing conditions. From a theoretical point of view, however, a vivid and very controversial debate emerges, whether LIPSS originate from electromagnetic effects or are caused by matter reorganization. This article aims to close a gap in the available literature on LIPSS by reviewing the currently existent theories of LIPSS along with their numerical implementations and by providing a comparison and critical assessment of these approaches. KW - Laser-induced periodic surface structures (LIPSS) KW - Electromagnetic theories KW - Matter reorganization theories KW - Surface plasmon polaritons KW - Self-organization PY - 2020 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-514089 DO - https://doi.org/10.1002/lpor.202000215 SN - 1863-8899 VL - 14 IS - 10 SP - 2000215-1 EP - 2000215-25 PB - Wiley CY - Berlin AN - OPUS4-51408 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Scherb, T. A1 - Fantin, Andrea A1 - Checcia, S. A1 - Stephan-Scherb, Christiane A1 - Escolástico, S. A1 - Franz, A. A1 - Seeger, J. A1 - Meulenberg, W. A. A1 - d'Acapito, F. A1 - Serra, J. M. T1 - Unravelling the crystal structure of Nd5.8WO12-d and Nd5.7W0.75Mo0.25O12-d mixed ionic electronic conductors N2 - Mixed ionic electronic conducting ceramics Nd6-yWO12-d (d is the Oxygen deficiency) provide excellent stability in harsh environments containing strongly reactive gases such as CO2, CO, H2, H2O or H2S. Due to this chemical stability, they are promising and cost-efficient candidate materials for gas separation, catalytic membrane reactors and protonic ceramic fuel cell technologies. As in La6-yWO12-d, the ionic/electronic transport mechanism in Nd6-yWO12-d is expected to be largely controlled by the crystal structure, the conclusive determination of which is still lacking. This work presents a crystallographic study of Nd5.8WO12-d and molybdenum-substituted Nd5.7W0.75Mo0.25O12-d prepared by the citrate complexation route. High-resolution synchrotron and neutron powder diffraction data were used in combined Rietveld refinements to unravel the crystal structure of Nd5.8WO12-d and Nd5.7W0.75Mo0.25O12-d. Both investigated samples crystallize in a defect fluorite crystal structure with space group Fm3m and doubled unit-cell parameter due to cation ordering. Mo replacesWat bothWyckoff sites 4a and 48h and is evenly distributed, in contrast with La6-yWO12-d. X-ray absorption spectroscopy as a function of partial pressure pO2 in the near-edge regions excludes oxidation state changes of Nd (Nd3+) and W(W6+) in reducing conditions: the enhanced hydrogen permeation, i.e. ambipolar conduction, observed in Mo-substituted Nd6-yWO12-d is therefore explained by the higher Mo reducibility and the creation of additional – disordered – oxygen vacancies. KW - Powder diffraction KW - Mixed conductors KW - X-ray absorption spectroscopy PY - 2020 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-514607 DO - https://doi.org/10.1107/S1600576720012698 VL - 53 SP - 1471 EP - 1483 AN - OPUS4-51460 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 Conference 2020 CY - Online meeting DA - 03.08.2020 KW - Fire KW - Testing KW - Large scale testing KW - Calorimeter KW - Heat flux PY - 2020 SP - 1 EP - 9 PB - ASME CY - New York AN - OPUS4-51192 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin 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 - JOUR A1 - Lone, S. A. A1 - Muck, M. A1 - Fosodeder, P. A1 - Mardare, C.C. A1 - Florian, Camilo A1 - Weth, A. A1 - Krüger, Jörg A1 - Steinwender, C. A1 - Baumgartner, W. A1 - Bonse, Jörn A1 - Heitz, J. A1 - Hassel, A.W. T1 - Impact of Femtosecond Laser Treatment Accompanied with Anodization of Titanium Alloy on Fibroblast Cell Growth N2 - Herein, Ti6Al4V alloy is surface modified by femtosecond laser ablation. The microstructure image obtained by secondary electron microscopy reveals a combination of micrometer spikes or cones superimposed by nanoripples (laser‐induced periodic surface structures). To make the surface hydrophilic, anodization is performed resulting in further smoothness of microstructure and a final thickness of 35 ± 4 nm is estimated for oxide produced after anodization at 10 V (scan rate = 0.1 V s−1) versus standard hydrogen electrode. The obtained electrochemically active surface area (ECSA) is approximately 8 times larger compared with flat mirror polished Ti6Al4V surface. Combined chemical analysis by Pourbaix diagram and X‐ray photoelectron spectroscopy (XPS) analyses reveal that titanium and aluminum are passivating into TiO2 and Al2O3, but the dissolution of aluminum in the form of solvated ion is inevitable. Finally, cell seeding experiments on anodized and laser‐treated titanium alloy samples show that the growth of murine fibroblast cells is significantly suppressed due to unique surface texture of the laser‐treated and anodized titanium alloy sample. KW - Anodization KW - Femtosecond laser ablation KW - Laser-induced periodic surface structures, LIPSS KW - Ti6Al4V alloys KW - X-ray photoelectron spectroscopy PY - 2020 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-510263 DO - https://doi.org/https://doi.org/10.1002/pssa.201900838 SN - 1862-6300 SN - 1862-6319 VL - 217 IS - 13 SP - 1900838-1 EP - 1900838-9 PB - WILEY-VCH Verlag CY - Weinheim, Germany AN - OPUS4-51026 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Babutzka, Martin T1 - Überarbeitung des GfKORR-Leitfadens „Korrosionsschutz von Offshore-Windenergieanlagen" N2 - Der Vortrag stellt den aktuellen Stand und die Diskussionsthemen für die Überarbeitung des GfKORR-Leitfadens "Korrosionsschutz von Offshore-Windenergieanlagen" vor. T2 - Gemeinsame Sitzung des GfKORR Arbeitskreises „Korrosionsschutz von Windenergieanlagen“ mit der Fachgruppe „Korrosionsschutz“ der WAB e.V. CY - Online meeting DA - 07.12.2020 KW - Leitfaden KW - Korrosionsschutz KW - Offshore-Windenergieanlagen PY - 2020 AN - OPUS4-51784 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Reichardt, Adrian T1 - Assessment of ageing effects at BAM N2 - In Germany, spent nuclear fuel and vitrified high active waste is stored in dual purpose casks (DPC) at interim storage facilities. In order to ensure the transportability of the DPC to a final repository in future, the maintenance of the package design approval is realized. Therefore, the assessment of possible ageing effects during interim storage is necessary to ensure an evaluation of the transportability. The lecture presents BAM's current ageing evaluation concept in the field of trasnport law. T2 - IRSN-BAM Symposium - Safety of Transport and Storage Packages CY - Online meeting DA - 19.11.2020 KW - Ageing KW - DPC KW - Interim storage KW - Ageing management PY - 2020 AN - OPUS4-51718 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nerger, Deborah A1 - Moosavi, Robabeh A1 - Bracklow, F. A1 - Hering, M. A1 - Kühn, T. A1 - Curbach, M. A1 - Hille, Falk A1 - Rogge, Andreas ED - Papadrakakis, M. ED - Fragiadakis, M. ED - Papadimitriou, C. T1 - Impact damage characterization at RC plates with planar tomography and FEM N2 - Prediction of dynamic effects of reinforced concrete structures under impact loading is a technical challenge. This is a consequence of the great variability of the physical properties resulting from the wide adaptability of reinforced concrete and a consequence of the wide range of impact loading. Experiments and numerical investigations are normally used on a small scale to address the problem. In this paper, impact tests on reinforced conrete plates with the lateral dimensions of 1.5 m x 1.5 m and a thickness of 30 cm are presented. In bending reinforcement, besides the velocity two properties are varied, the diameter and the spatial distribution of the rebars. Experiments are performed at the Otto-Mohr-Laboratory of the Institute of Concrete Structures of the Technische Universit¨at Dresden. Due to the accelerated fall of the impactor the velocity ranges between 20 and 70 m/s. In addition to the measured quantities such as bearing forces, accelerations are also measured at 4 different positions on and under the plate, as well as the deflection at several positions. The measured data are used for the analysis of the damage form and the numerical examinations with the program Ansys Autodyn and the material model after Drucker-Prager. Numerical investigations support the tests, with detailed analysis of individual effects. These numerical computations and the planar tomographic investigations were carried out at BAM in Berlin. With the help of planar tomographic evaluation, the damaged structure is made visible and compared with the numerical results. Influences of the bending reinforcement are explained on the basis of damage evaluation in the local area and on selected measured values. In addition to the test evaluation, the tomographic and numerical methods are presented. T2 - XI International Conference on Structural Dynamics (EURODYN 2020) CY - Online meeting DA - 23.11.2020 KW - Post-impact evaluation KW - Damage characterization KW - Planar tomography KW - Drucker-Prager KW - Ansys Autodyn PY - 2020 SN - 978-618-85072-2-7 VL - 1 SP - 2521 EP - 2543 PB - Institute of Structural Analysis and Antiseismic Research, School of Civil Engineering, National Technical University of Athens (NTUA), Greece CY - Athens, Greece AN - OPUS4-51769 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin 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 - Akkerman, Floris T1 - Aktuelles zur Ökodesign-Verordnung - Entwicklung und Einschätzung zum Inverkehrbringen N2 - Vorstellung der Rechtsinstrumente Ökodesign, Darstellung der Entwicklung und Einschätzung zu Szenarien zum Inverkehrbringen am Beispiel Kühlmöbel T2 - Handel-Hersteller-Dialog der FG Kühlmöbel des VDMA CY - Online meeting DA - 07.12.2020 KW - Ökodesign KW - Energieverbrauchskennzeichnung KW - Energieeffizienz KW - Kühlmöbel KW - Supermarktkälte PY - 2020 AN - OPUS4-51817 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schürmann, K. T1 - Experimental investigations on the fatigue resistance of automatically welded tubular X-joints for jacket support structures N2 - The development within the offshore wind sector towards more powerful turbines combined with increasing water depth for new wind parks is challenging both the designer as well as the manufacturer of bottom fixed support structures. Besides XL-monopiles, the market developed an innovative and economic jacket support structure which is based on automatically manufactured tubular joints combined with standardized pipes. Besides the improvements for a serial manufacturing process the automatically welded tubular joints show a great potential in terms of fatigue resistance e.g. due to a smooth weld geometry without sharp notches. However, these benefits are not considered yet within the fatigue design process of automatically manufactured jacket substructures according to current standards due to the lack of suitable S-N curves. Therefore, 32 axial fatigue tests on single and double-sided automatically welded tubular X-joints have been performed to determine a new hot spot stress related S-N curve. Based on these constant amplitude fatigue tests a new S-N curve equal to a FAT 126 curve was computed which implicitly includes the benefits of the automatically welding procedure. T2 - EERA DeepWind 2020 CY - Trondheim, Norway DA - 15.01.2020 KW - Notch stress approach KW - Tubular X-joints KW - Automated manufacturing KW - Fatigue tests KW - Structural stress approach PY - 2020 AN - OPUS4-51873 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schumacher, David T1 - From W. C. Röntgen to modern Tomography N2 - A not complete review of X-Ray related milestones from 1895 to the 21st century. T2 - ITN GW4SHM, First Training Event CY - Online Meeting DA - 23.11.2020 KW - X-Ray KW - Computed Tomography KW - Laminography KW - Digital Detector Arrays KW - Wilhelm Conrad Röntgen PY - 2020 AN - OPUS4-51881 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin T1 - Fire reference package - Results of large-scale fire tests 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 - IRSN-BAM Symposium - Safety of Transport and Storage Packages CY - Online meeting DA - 19.11.2020 KW - Fire reference KW - Calorimetric test KW - Propane KW - Heat flux KW - Propane gas fire test facility PY - 2020 AN - OPUS4-51686 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Update on the German Spent Fuel Management Strategy N2 - The presentation provides an update on the German spent fuel Management strategy in the areas of transportation, dry interim storage and deep geological disposal. T2 - IAEA 18th TWG-NFCO CY - Online meeting DA - 07.09.2020 KW - Spent nuclear fuel KW - Final disposal KW - Safety KW - Transport and storage cask PY - 2020 AN - OPUS4-51616 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Amano, K.O.A. A1 - Hahn, S.-K. A1 - Tschirschwitz, Rico A1 - Rappsilber, Tim A1 - Krause, U. T1 - Experimental Investigation on Explosion Pressure Characteristics of Lithium-based (NMC) Pouch Batteries during Thermal Runaway N2 - Lithium ion batteries (LIBs) are prone to spontaneous and subsequent fire or explosion resulting from thermal runaway. The vented gases are not only toxic and flammable, their emission can also raise the surrounding pressure rapidly. In this study, characteristic variations of explosion pressure rise, rate of explosion pressure rise and 𝐾(sT)-value have been evaluated. The characteristic 𝐾(𝑠𝑇)-values were determined to evaluate the explosive behavior of LIBs during thermal runaway. The estimated values were compared to that of other explosive substances. T2 - Batterieforum Deutschland 2021 CY - Online meeting DA - 20.01.2021 KW - Pressure KW - Lithium KW - Thermal Runaway KW - Battery KW - Pouch PY - 2021 AN - OPUS4-52033 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gleim, Tobias A1 - Chen, Hefeng T1 - Numerical Analysis for an Electro‐Magneto‐Mechanical Phenomenon with High‐Order Accurate Methods N2 - This paper establishes an axisymmetric model for a levitation device. Therein, the Maxwell equations are combined with the balance of linear momentum. Different possible formulations to describe the MAXWELL equations are presented and compared and discussed in the example. A high order finite element discretization using GALERKIN's method in space and the generalized NEWMARK‐α method in time are developed for the electro‐magneto‐mechanical approach. Several studies on spatial and temporal discretization with respect to convergence will be investigated. In addition, the boundary influences and the domain size with respect to the levitation device are also examined. T2 - International Association for Applied Mathematics and Mechanics CY - Kassel, Germany DA - 16.03.2020 KW - High-Order Methods KW - Electro-Magneto-Mechanical KW - Levitation Device PY - 2021 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-520720 DO - https://doi.org/10.1002/pamm.202000018 VL - 20 IS - 1 SP - e202000018 PB - Wiley‐VCH GmbH CY - Online AN - OPUS4-52072 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Asna Ashari, Parsa T1 - An Analysis of the Three Knowledge and Technology Transfer Channels: Publications, Patents, Standards – The Case of Hydrogen Technology N2 - Climate change and the need to reduce greenhouse gas emissions pose tremendous challenges to policymakers, the economy, and society. In this context, the development of clean, low-emission technologies plays a crucial role in mitigating the negative impact of fossil fuels on the climate. Hydrogen is a promising energy carrier and fuel that, thanks to its versatility, can be used in many applications. However, the adoption of hydrogen technology requires sufficient trust in its safety. To proxy the development of hydrogen safety innovations, we provide an analysis along the three knowledge and technology transfer channels of publications, patents, and standards. Our results show that research on hydrogen safety has increased significantly in the last decades, with hydrogen safety patents experiencing a general upward trend between 1980 and 2020, just recently decreasing. However, an analysis of almost 100 international hydrogen and fuel cell standards shows only a small number of references to scientific publications. This apparently limited transfer of knowledge from publications points to the need to optimize the coordination of the three knowledge and technology transfer channels for the future development of hydrogen technology. Based on the exploration of this gap, we recommend that research on the three channels for hydrogen be intensified and that the impact of hydrogen safety technology research and development on their diffusion be investigated. T2 - 25th EURAS Annual Standardisation Conference – Standardisation and Innovation CY - Online meeting DA - 06.09.2021 KW - Hydrogen Standards KW - Fuel Cells KW - Knowledge and Technology Transfer KW - Publications KW - Patents KW - Standards KW - Safety PY - 2021 AN - OPUS4-53215 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin T1 - Fire Testing - Current Activities N2 - The presentation gives an overview over three current fire testing activities for testing transport packages for the transport of high-level radioactive material. Packages for the transport of high-level radioactive material must withstand severe hypothetical accidents. Regulatory test conditions shall cover these severe accident conditions and consist of mechanical tests and a following thermal test. To withstand the mechanical tests heavy weight packages are often designed with impact limiters consisting of wood encapsulated in steel sheets. The thermal test is defined precisely in the IAEA-regulations as a 30 minute fully engulfing 800 °C fire. After the fire phase a pre-damaged impact limiter might continue burning or smoldering and influence the cask thermal behavior with its energy release. The energy transferred from the impact limiter to the cask is of importance for the safety of transport packages. A full-scale fire test with an impact limiter of 2.3 m in diameter and filled with spruce wood was designed and performed. The impact limiter continued burning for 3 days. Energy transfer and temperature measurements were performed. A new test is designed to examine pressure build up and possible mechanical failures in an undamaged impact limiter with a diameter of 1.9 m. The test is designed to measure heat flux from the impact limiter in case of its ignition and burning. To furthermore examine the burning behavior of steel encapsulated wood piles, tests are prepared with wood fire containers and an infrared ignition source. A fire reference package for calorimetric tests was designed. The fire reference package design consists of a closed steel sheet cylinder with a length of 1,500 mm, an exterior diameter of 1,050 mm, and a wall thickness of 10 mm. The cylinder was filled with refractory insulation material and instrumented with thermocouples distributed all over the cylinder. The measured local steel sheet temperatures allow the determination of local as well as overall integral heat fluxes versus time and versus surface temperature. Currently, tests are planned with a new and relatively small fire reference package design. The new design will have a steel sheet cylinder with a length of 182 mm, an exterior diameter of 120 mm. Additionally heat flux sensors will be used in the new fire reference package test design. The propane gas fire will be adjusted with respect to the outcome of the fire tests to meet the requirements of the IAEA-fire. T2 - Technical Exchange IRSN – BAM Transport & Storage of Packages for Radioactive Material CY - Berlin, Germany DA - 08.09.2021 KW - Heat flux sensor KW - Propane gas fire KW - Wood fire PY - 2021 AN - OPUS4-53242 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Linnemann, Konrad 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 - JOUR A1 - Seher, Julia A1 - Fröba, M. T1 - Shape matters: The effect of particle morphology on the fast-charging performance of LiFePO4/C nanoparticle composite electrodes N2 - For the successful use of lithium-ion batteries in automotive applications, reliable availability of high storage capacity and very short recharging times are essential. In order to develop the perfect battery for a certain application, structure–property relationships of each active material must be fully understood. LiFePO4 is of great interest due to its fast-charging capability and high stability regarding its thermal resistance and chemical reactivity. The anisotropic lithium-ion diffusion through the LiFePO4 crystal structure indicates a strong dependence of the electrochemical performance of a nanostructured active material on particle morphology. In this paper, the relationship of the particle morphology and fast-charging capability of LiFePO4/C core/shell nanoparticles in half-cells was studied. For this purpose, a new multistep synthesis strategy was developed. It involves the combination of a solvothermal synthesis followed by an in situ polymer coating and thermal calcination step. Monodisperse rodlike LiFePO4 nanoparticles with comparable elongation along the b-axis (30–50 nm) and a varying aspect ratio c/a (2.4–6.9) were obtained. A strong correlation of the fast-charging capability with the aspect ratio c/a was observed. When using LiFePO4 nanoparticles with the smallest aspect ratio c/a, the best electrochemical performance was received regarding the specific capacity at high C-rates and the cycling stability. A reduction of the aspect ratio c/a by 30% (3.6 to 2.4) was found to enhance the charge capacity at 10 C up to an order of magnitude (7.4–73 mA h·g–1). KW - LiFePO4 KW - Schnellladung KW - Nanoparticles KW - Carbon KW - Chemical synthesis KW - Electrochemical cells KW - Materials PY - 2021 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-533004 DO - https://doi.org/10.1021/acsomega.1c03432 SN - 2470-1343 VL - 6 IS - 37 SP - 24062 EP - 24069 PB - American Chemical Society CY - Washington, DC AN - OPUS4-53300 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 - JOUR A1 - Wu, Z. A1 - Guo, X. A1 - Xie, G. A1 - Yan, T. A1 - Wu, Dejian A1 - Zhang, F. A1 - Ang, R. T1 - Heat and electric flux coupling of closed-loop thermoelectric generator N2 - Thermoelectric generator (TEG) has been proved as a promising technology for directly converting heat into electricity based on Seebeck effect. On the contrary, this electricity can trigger a solid-state cooling based on conventional Peltier effect. However, these two effects induce a coupling between heat and electric flux, especially for the quantitative relationship still remaining a mystery. Here, we show experimental evidence and theoretical calculation for the coupling by monitoring transient response of fluid temperature and output power. The experimental maximum heat flow in open circuit is 1162 W at cold fluid flow rate = 0.3 m3/h and fluid temperature difference ΔTf = 70 °C, enhanced by 13% owing to heat compensation from intrinsic coupling in closed-loop circuit. Meanwhile, the measured maximum output power of TEG is 18.2 W, and subsequently decreases to 15.4 W due to the objective existence of coupling. This double-edged sword in coupling vigorously inspires the potential applications in heat-dissipation situation such as spacecraft, electronic components, photovoltaic, refrigerator and etc. Present findings open a novel avenue for manipulating heat-electricity conversion in practical engineering. KW - Thermoelectric generator PY - 2021 DO - https://doi.org/10.1016/j.enconman.2021.114529 SN - 0196-8904 VL - 244 SP - 1 EP - 13 PB - Elsevier Ltd. AN - OPUS4-53661 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CHAP A1 - Droste, Bernhard A1 - Wolff, Dietmar A1 - Bevilacqua, A. A1 - Reiche, I. A1 - Harvey, J. A1 - Hirose, M. A1 - Kumano, Y. A1 - McConnell, P. A1 - Saegusa, T. A1 - Einziger, R. ED - González-Espartero, A. T1 - Methodology for a Safety Case of a Dual Purpose Cask for Storage and Transport of Spent Fuel N2 - Spent nuclear fuel which is generated in the operation of nuclear reactors needs to be safely managed following its removal from the reactor core. On-site power reactor storage pools were designed on the assumption that after a short period of time spent nuclear fuel would be removed for reprocessing and disposal or further storage elsewhere. The amount of highly radioactive spent fuel that needs to be stored over longer periods of time is growing and additional storage capacity is required. One of the widely used options for additional storage capacity is the use of casks for dry storage of spent fuel. Among various existing dry storage concepts, several Member States are utilizing a concept of dual purpose casks (DPCs). This publication provides practical advice on the structure and contents of a DPC integrated safety case with reference to existing IAEA requirements relevant to the licensing and use of transport and storage casks for spent fuel. KW - Dual Purpose Cask KW - Spent Fuel KW - Storage KW - Transport PY - 2020 UR - https://www.iaea.org/publications/10966/methodology-for-a-safety-case-of-a-dual-purpose-cask-for-storage-and-transport-of-spent-fuel SN - 978-92-0-131620-2 SN - 1011–4289 SP - 1 EP - 109 PB - IAEA Publishing Section CY - Vienna, Austria AN - OPUS4-51962 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Palkowski, Carsten T1 - BAM Round Robin Test for Heat Pumps and Air Conditioners N2 - Preliminary results of the BAM RRTs are given in this presentation. T2 - VHK Meeting CY - Online meeting DA - 11.11.2020 KW - Heat Pumps KW - Air Conditioners KW - Round Robin Test KW - Load-Based Test Method KW - Energy Label PY - 2020 AN - OPUS4-51969 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Ruiz-Hervias, J. A1 - Simbruner, Kai A1 - Cristobal-Beneyto, M. A1 - Perez-Gallego, D. A1 - Zencker, Uwe T1 - Failure mechanisms in unirradiated ZIRLO® cladding with radial hydrides N2 - The purpose of this paper is to investigate the relationship between hydride morphology, in particular the presence of radial hydrides (RHs), stress state and failure mechanisms associated with the ring compression test (RCT). Samples of ZIRLO®cladding were pre-hydrided and subjected to thermo-mechanical treatments to precipitate long radial hydrides. The results show that the reorientation treatment was very successful. A considerable fraction of RHs was generated, the radial hydride continuity factor being around 80 to 90% of the wall thickness. The samples with reoriented hydrides were tested using the RCT at room temperature. Macroscopic brittle failure was observed with sudden load drops for displacements around 0.5 mm, with a calculated “offset strain”between 0.5 and 1%. Crack nucleation occurs in RHs located in regions with the highest values of hoop stress. These locations are the inner diameter of cladding at the vertical plane of the sample (12 and 6 o’clock positions) and the outer diameter at the horizontal plane (3 and 9 o’clock positions). Noticeable load drops in the RCT are associated with unstable crack propagation events through the radial hydride network, the crack front reaching up to 90% of the wall thickness in some cases. The failure micro-mechanism is quasi-cleavage in the hydrides and micro-void nucleation, growth and coalescence in the Zr matrix, with ductile tearing patches connecting neighboring hydrides. The main conclusion is that radial hydride metrics is not the only parameter that determines cladding failure in the presence of RHs, but the interaction between the location and continuity of RHs and the stress normal to the hydride (the hoop stress in this case). Consequently, if a radial hydride is located at a position within the cladding where the hoop stress is small, a crack will not be initiated easily in the RCT. KW - ZIRLO® KW - Cladding Embrittlement KW - Radial Hydrides KW - Failure Mechanism KW - Ring compression test PY - 2021 DO - https://doi.org/10.1016/j.jnucmat.2020.152668 SN - 0022-3115 VL - 544 SP - 152668 PB - Elsevier B.V. AN - OPUS4-52000 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Simbruner, Kai T1 - Brittle failure analysis of spent fuel zirconium alloy claddings during long-term dry interim storage - Current approach at BAM N2 - Understanding the mechanical behaviour of fuel cladding is decisive for an extended dry interim storage period beyond the currently licensed period of 40 years in Germany and subsequent handling, transport, and disposal considering normal and accidental conditions. Since fuel cladding acts as the first barrier for spent fuel, its integrity should be demonstrated to enable safe and secure discharge and handling options after interim storage and subsequent transportation in preparation of final disposal. An established method for characterizing cladding material is the Ring Compression Test (RCT), where a small, cylindrical sample of the cladding tube is subjected to a compressive load. This test is a laboratory representation of a fuel rod load case and has shown a high susceptibility to failure under the occurrence of radial hydrides. Certain hydride morphologies and low temperature might even lead to brittle fracture at very small loads. The BAM research project BRUZL (Fracture mechanical analysis of spent fuel claddings during long-term dry interim storage) aims to study the results of quasi-static RCTs and to establish numerical models to gain an in-depth understanding of the stress state during the experiments. Using a fracture mechanical approach, cases of sudden failure during the RCT procedure are used to characterize the material behaviour and establish a failure criterion. As an integral part of the project BRUZL, quasi-static Ring Compression Tests have been performed to identify all experimental details, which might be helpful for numerical modelling. Unirradiated samples of the cladding material ZIRLO® have been subjected to hydrogen charging and a thermo-mechanical treatment for radial hydride reorientation. Sample preparation, testing procedures, and analysis results are presented. A numerical model has been established and an elastic-plastic material model was derived from as-received RCT samples by inverse finite element analyses. Cohesive zone modelling has been implemented to reproduce sudden load drops during RCT. The project is funded by the Federal Ministry for Economic Affairs and Energy (BMWi) under contract no. 1501561. T2 - Kolloquium der Abteilung 3 CY - Online meeting DA - 05.11.2020 KW - Ageing Management KW - Cladding Embrittlement KW - Extended Storage KW - Ring Compression Test KW - Spent Nuclear Fuel PY - 2020 AN - OPUS4-51987 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Simbruner, Kai T1 - Embrittlement of Spent Fuel Claddings ‒ Results of Ring Compression Tests N2 - An established method for characterizing cladding material is the Ring Compression Test (RCT), where a small, cylindrical sample of the cladding tube is subjected to a compressive load. This test is a laboratory representation of a fuel rod load case and has shown a high susceptibility to failure under the occurrence of radial hydrides. Certain hydride morphologies and low temperature might even lead to brittle fracture at very small loads. The BAM research project BRUZL (Fracture mechanical analysis of spent fuel claddings during long-term dry interim storage) aims to study the results of quasi-static RCTs and to establish numerical models to gain an in-depth understanding of the stress state during such experiments. Using a fracture mechanical approach, cases of sudden failure during the RCT procedure are used to characterize the material behaviour and establish a failure criterion. As an integral part of the project BRUZL, quasi-static Ring Compression Tests have been performed to identify all experimental details, which might be helpful for numerical modelling. Unirradiated samples of the cladding material ZIRLO® have been subjected to hydrogen charging and a thermo-mechanical treatment for radial hydride reorientation. Sample preparation, testing procedures, and analysis results are presented. A numerical model has been established and an elastic-plastic material model was derived from as-received RCT samples by inverse finite element analyses. Cohesive zone modelling has been implemented to reproduce sudden load drops during RCT. The project is funded by the Federal Ministry for Economic Affairs and Energy (BMWi) under contract no. 1501561. T2 - 4th GRS Workshop on Safety of Extended Dry Storage of Spent Nuclear Fuel CY - Online meeting DA - 03.06.2020 KW - Ageing Management KW - Cladding Embrittlement KW - Extended Storage KW - Ring Compression Test KW - Spent Nuclear Fuel PY - 2020 AN - OPUS4-51988 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Stamm, Michael T1 - EvalTherm - Evaluation of passive Thermography for the inspection of wind turbine blades N2 - The EvalTherm project is presented. The concept of passive thermography on rotor blades as well as first results of field measurements are discussed. As this is an industry-related conference, the focus in this paper is on practical aspects that are of interest for industrial applications. T2 - AMI Wind Turbine Blade Manufacture conference 2021 CY - Cologne, Germany DA - 15.11.2021 KW - Windenergy KW - Thermography KW - Inspection KW - NDT PY - 2021 AN - OPUS4-53928 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Lay, Vera A1 - Buske, S. A1 - Townend, J. A1 - Kellett, R. A1 - Savage, M. A1 - Schmitt, D. R. A1 - Constantinou, A. A1 - Eccles, J. D. A1 - Gorman, A. A1 - Bertram, M. A1 - Hall, K. A1 - Lawton, D. A1 - Kofman, R. T1 - 3D Active Source Seismic Imaging of the Alpine Fault Zone and the Whataroa Glacial Valley in New Zealand N2 - The Alpine Fault zone in New Zealand marks a major transpressional plate boundary that is late in its typical earthquake cycle. Understanding the subsurface structures is crucial to understand the tectonic processes taking place. A unique seismic survey including 2D lines, a 3D array, and borehole recordings, has been performed in the Whataroa Valley and provides new insights into the Alpine Fault zone down to ∼2 km depth at the location of the Deep Fault Drilling Project (DFDP)-2 drill site. Seismic images are obtained by focusing prestack depth migration approaches. Despite the challenging conditions for seismic imaging within a sediment filled glacial valley and steeply dipping valley flanks, several structures related to the valley itself as well as the tectonic fault system are imaged. A set of several reflectors dipping 40°–56° to the southeast are identified in a ∼600 m wide zone that is interpreted to be the minimum extent of the damage zone. Different approaches image one distinct reflector dipping at ∼40°, which is interpreted to be the main Alpine Fault reflector located only ∼100 m beneath the maximum drilled depth of the DFDP-2B borehole. At shallower depths (z < 0.5 km), additional reflectors are identified as fault segments with generally steeper dips up to 56°. Additionally, a glacially over-deepened trough with nearly horizontally layered sediments and a major fault (z < 0.5 km) are identified 0.5–1 km south of the DFDP-2B borehole. Thus, a complex structural environment is seismically imaged and shows the complexity of the Alpine Fault at Whataroa. KW - Imaging KW - Signal processing KW - Seismic KW - Borehole KW - DAS PY - 2021 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-539163 DO - https://doi.org/10.1029/2021JB023013 VL - 126 IS - 12 SP - 1 EP - 21 PB - American Geophysical Union AN - OPUS4-53916 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Wolff, Dietmar A1 - Orellana Pérez, Teresa A1 - Herold, Christian A1 - Bollingerfehr, W. A1 - Wunderlich, A. A1 - Prignitz, S. T1 - Anforderungen an Behälter für die Endlagerung hochradioaktiver Abfälle in Steinsalz, Tonstein und Kristallingestein N2 - Bei der Auswahl eines Standortes für ein Endlager für hochradioaktive Abfälle (Wärme entwickelnde radioaktive Abfälle und ausgediente Brennelemente) in Deutschland werden auf Grundlage des Standortauswahlgesetzes von 2017 die drei potenziellen Wirtsgesteine Steinsalz, Tonstein und Kristallingestein in Betracht gezogen. Die Auswahl eines konkreten Endlagerstandortes steht dabei in engem Zusammenhang mit den für die jeweiligen Wirtsgesteine geeignet erscheinender Endlagersystemen. Zentraler Bestandteil dieser Endlagersysteme sind die Endlagerbehälter, deren Gestaltung und Auslegung maßgeblich die Randbedingungen für die Transport- und Einlagerungstechnik vorgibt und zudem die Nachweise zur Betriebs- und Langzeitsicherheit entscheidend prägt. Daher ist es für die Behälterentwicklung erforderlich, die an Endlagerbehälter zu stellenden Anforderungen systematisch herzuleiten. Auf dieser Grundlage können anforderungsgerechte Endlagerbehälter zielgerichtet für die jeweils zu untersuchenden Endlagerstandorte in unterschiedlichen Wirtsgesteinen entwickelt werden. Dieser Beitrag fasst die wesentlichen Ergebnisse des von BAM und BGE TECHNOLOGY GmbH im Zeitraum 2017 bis 2020 bearbeiteten und vom Bundesministerium für Wirtschaft und Energie (BMWi) geförderten Forschungsvorhabens KoBrA zusammen, die in einem Abschlussbericht und vier zugehörigen Teilberichten umfassend dokumentiert sind. T2 - Tage der Standortauswahl CY - Freiberg, Germany DA - 11.02.2021 KW - Endlager KW - Behälter KW - Sicherheitsanforderungen KW - hochradioaktive Abfälle PY - 2021 SP - 1 EP - 10 AN - OPUS4-53114 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Anforderungen an Behälter für die Endlagerung hochradioaktiver Abfälle in Steinsalz, Tonstein und Kristallingestein N2 - Bei der Auswahl eines Standortes für ein Endlager für hochradioaktive Abfälle (Wärme entwickelnde radioaktive Abfälle und ausgediente Brennelemente) in Deutschland werden auf Grundlage des Standortauswahlgesetzes von 2017 die drei potenziellen Wirtsgesteine Steinsalz, Tonstein und Kristallingestein in Betracht gezogen. Die Auswahl eines konkreten Endlagerstandortes steht dabei in engem Zusammenhang mit den für die jeweiligen Wirtsgesteine geeignet erscheinender Endlagersystemen. Zentraler Bestandteil dieser Endlagersysteme sind die Endlagerbehälter, deren Gestaltung und Auslegung maßgeblich die Randbedingungen für die Transport- und Einlagerungstechnik vorgibt und zudem die Nachweise zur Betriebs- und Langzeitsicherheit entscheidend prägt. Daher ist es für die Behälterentwicklung erforderlich, die an Endlagerbehälter zu stellenden Anforderungen systematisch herzuleiten. Auf dieser Grundlage können anforderungsgerechte Endlagerbehälter zielgerichtet für die jeweils zu untersuchenden Endlagerstandorte in unterschiedlichen Wirtsgesteinen entwickelt werden. Dieser Beitrag fasst die wesentlichen Ergebnisse des von BAM und BGE TECHNOLOGY GmbH im Zeitraum 2017 bis 2020 bearbeiteten und vom Bundesministerium für Wirtschaft und Energie (BMWi) geförderten Forschungsvorhabens KoBrA zusammen, die in einem Abschlussbericht und vier zugehörigen Teilberichten umfassend dokumentiert sind. T2 - Tage der Standortauswahl CY - Freiberg, Germany DA - 11.02.2021 KW - Endlager KW - Behälter KW - Sicherheitsanforderungen KW - hochradioaktive Abfälle PY - 2021 AN - OPUS4-53115 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - RPRT A1 - Herold, Christian A1 - Orellana Pérez, Teresa A1 - Völzke, Holger A1 - Wolff, Dietmar T1 - Nationaler und Internationaler Stand zu bereits existierenden Anforderungen und Konzepten für Endlagerbehälter und Zusammenstellung sicherheitsrelevanter Behältereigenschaften; Bericht zum Arbeitspaket 1 des FuE-Verbundvorhabens KoBrA N2 - Im hier vorliegenden Bericht wurde im Rahmen einer umfassenden Literaturrecherche der nationale und internationale Stand von Wissenschaft und Technik hinsichtlich Behälterkonzepten und Behälteranforderungen erfasst. Dabei wurde eine umfangreiche Dokumentensammlung zusammengestellt und sortiert, die als Quellenbasis für alle weiteren Arbeiten zur Verfügung steht. Die Auswertung der gesammelten Informationen resultiert in einem Überblick über internationale Behälterentwicklungen sowie einer detaillierten Übersicht über die Behälterkonzepte und die ihnen zugrundeliegenden Anforderungskataloge aus elf fortgeschrittenen Endlagerprogrammen. KW - Endlager KW - Behälter KW - Sicherheitsanforderungen KW - Hochradioaktive Abfälle PY - 2020 DO - https://doi.org/10.2314/KXP:1759195804 N1 - Auftraggeber: Bundesministerium für Wirtschaft und Energie (BMWi), Förderkennzeichen: 02E11537. SP - 1 EP - 284 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin AN - OPUS4-53117 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - RPRT A1 - Herold, Christian A1 - Völzke, Holger A1 - Orellana Pérez, Teresa A1 - Wolff, Dietmar A1 - Bollingerfehr, W. A1 - Wunderlich, A. A1 - Prignitz, S. T1 - Erarbeitung von Vorschlägen für mögliche Behälterkonzepte in den drei potenziellen Wirtsgesteinen Steinsalz, Tonstein und Kristallingestein; Bericht zum Arbeitspaket 4 des FuE Verbundvorhabens KoBrA N2 - Dieser Bericht untersucht die im ersten Arbeitspaket ermittelten vorhandenen bzw. entwickelten Behälterkonzepte dahingehend, inwieweit die jeweiligen Behälterfunktionen unter den im zweiten und dritten Arbeitspaket ermittelten Randbedingungen und Einwirkungen den im dritten Arbeitspaket ermittelten Anforderungen an endlagerfähige Behälter in einem deutschen Endlager genügen. Zum anderen sollen, basierend auf den im zweiten Arbeitspaket ermittelten Randbedingungen und den im dritten Arbeitspaket hergeleiteten und zusammengestellten Anforderungen an die Endlagerbehälter, Vorschläge für mögliche generische Endlagerbehälter in den drei potenziellen Wirtsgesteinen Steinsalz, Tonstein und Kristallingestein erarbeitet werden. Die im ersten Arbeitspaket recherchierten Behälterkonzepte, deren Entwicklungslinien und zugrundeliegende Behälteranforderungen bilden hier den Ausgangspunkt für weitergehende Überlegungen hinsichtlich ihrer potenziellen Eignung für ein zukünftiges deutsches Endlager und zur Skizzierung generischer Konzepte für zukünftige Endlagerbehälter. KW - Endlager KW - Behälter KW - Sicherheitsanforderungen KW - Hochradioaktive Abfälle PY - 2020 DO - https://doi.org/10.2314/KXP:1759194123 N1 - Auftraggeber: Bundesministerium für Wirtschaft und Energie (BMWi), Förderkennzeichen: 02E11537. SP - 1 EP - 76 PB - Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin AN - OPUS4-53118 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - RPRT A1 - Herold, Christian A1 - Völzke, Holger A1 - Wolff, Dietmar A1 - Orellana Pérez, Teresa A1 - Bollingerfehr, W. A1 - Wunderlich, A. A1 - Prignitz, S. T1 - Herleitung und Zusammenstellung der Anforderungen an Endlagerbehälter für ein HAW-Endlager in den drei potenziellen Wirtsgesteinen Steinsalz, Tonstein und Kristallingestein; Bericht zum Arbeitspaket 3 des FuE Verbundvorhabens KoBrA N2 - Der Bericht zum Arbeitspaket 3 baut auf den Ergebnissen der internationalen Recherche (AP1) sowie der Zusammenstellung der Randbedingungen und Beanspruchungsgrößen für die Endlagerbehälter (AP2) auf. Die Anforderungen an die Behälter – regulatorische, betriebliche sowie solche aus der Standortgeologie und den Einwirkungen und Prozessen, denen die Behälter ausgesetzt sind – werden hergeleitet und systematisch dargestellt. Die für das Endlagersystem zu betrachtenden Nutzungsphasen werden aus den regulatorischen Anforderungen hergeleitet und charakterisiert. Die Einwirkungen auf die Behälter in den drei potenziellen Wirtsgesteinen sowie die sich für die Erfüllung der Sicherheitsfunktionen des Behälters als Teil des Endlagersystems ergebenden Behälterfunktionen werden ebenfalls wirtsgesteins- und zeitphasenabhängig betrachtet. Schließlich werden aus den Einwirkungen auf die Behälter und den Anforderungen an die Behälterfunktionen auch quantifizierbare Behälterfunktionen für alle drei potenziellen Wirtsgesteine abgeleitet. KW - Endlager KW - Behälter KW - Sicherheitsanforderungen KW - Hochradioaktive Abfälle PY - 2020 UR - https://www.bge-technology.de/fileadmin/user_upload/MEDIATHEK/f_e_berichte/KoBrA/2020-KoBrA_Bericht_AP3.pdf N1 - Auftraggeber: Bundesministerium für Wirtschaft und Energie (BMWi), Förderkennzeichen: 02E11527 und 02E11537. SP - 1 EP - 254 PB - BGE Technology CY - Peine AN - OPUS4-53119 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Asna Ashari, Parsa A1 - Blind, K. ED - Jakobs, K. T1 - An Analysis of the Three Knowledge and Technology Transfer Channels: Publications, Patents, Standards – The Case of Hydrogen Technology N2 - Climate change and the need to reduce greenhouse gas emissions pose tremendous challenges to policymakers, the economy, and society. In this context, the development of clean, low-emission technologies plays a crucial role in mitigating the negative impact of fossil fuels on the climate. Hydrogen is a promising energy carrier and fuel that, thanks to its versatility, can be used in many applications. However, the adoption of hydrogen technology requires sufficient trust in its safety. To proxy the development of hydrogen safety innovations, we provide an analysis along the three knowledge and technology transfer channels of publications, patents, and standards. Our results show that research on hydrogen safety has increased significantly in the last decades, with hydrogen safety patents experiencing a general upward trend between 1980 and 2020, just recently decreasing. However, an analysis of almost 100 international hydrogen and fuel cell standards shows only a small number of references to scientific publications. This apparently limited transfer of knowledge from publications points to the need to optimize the coordination of the three knowledge and technology transfer channels for the future development of hydrogen technology. Based on the exploration of this gap, we recommend that research on the three channels for hydrogen be intensified and that the impact of hydrogen safety technology research and development on their diffusion be investigated. T2 - 25th EURAS Annual Standardisation Conference – Standardisation and Innovation CY - Aachen, Germany DA - 05.09.2021 KW - Hydrogen KW - Fuel Cells KW - Knowledge and Technology Transfer KW - Publications KW - Patents KW - Standards KW - Safety PY - 2021 SN - 978-3-95886-421-4 SP - 1 EP - 20 CY - Mainz AN - OPUS4-53912 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Pampel, Jonas T1 - Natrium- und Lithium-Metall-Batterien - Wie gefährlich sind sie wirklich N2 - Das Verhalten von Batteriezellen bei Beschädigung ist von hoher Bedeutung für die Einschätzung der Sicherheit bei Transport, Lagerung sowie Verwendung. Vor allem im Zusammenhang mit dem exponentiell wachsenden Sektor der Lithium-Batterien kam es in der Vergangenheit immer wieder zu kritischen Vorfällen. Hierbei haben Lithium-Metall-Batterien, welche elementares Lithium enthalten, den Ruf besonders gefährlich zu sein. Um dieses Thema bewerten zu können, werden im Vortrag die Unterschiede zwischen Lithium-Ionen- und Lithium-Metall-Batterien erläutert und experimentelle Studien des Verhaltens von aktuellen Systemen bei Schädigung verglichen. Darüber hinaus wird auf die Eigenschaften sowie das Sicherheitsverhalten von zukünftigen Lithium- bzw. Natrium-Batterien eingegangen. T2 - Fachkonferenz Lithiumbatterien - Logistik, Lagerung und Entsorgung CY - Online meeting DA - 26.01.2021 KW - Lithium-Batterien KW - Sicherheit KW - Thermisches Durchgehen KW - Natrium-Batterien PY - 2021 AN - OPUS4-54055 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Pampel, Jonas T1 - Neues aus der Welt der Lithiumbatterien: Jüngste Forschungsergebnisse und deren Auswirkungen auf die Beförderung und Lagerung N2 - Das Verhalten von Batteriezellen bei Beschädigung ist von hoher Bedeutung für die Einschätzung der Sicherheit bei Transport, Lagerung sowie Verwendung. Die Auswirkungen bei Schädigung hängen natürlich von der Art der Zelle, jedoch auch vom Ladezustand und der Schädigungsmethode ab. Im Vortrag werden die Schädigungsversuche von Einzelzellen sowie Propagationsversuche an der BAM für verschieden Ladezustände präsentiert. Des Weiteren werden die aktuellen Vorgaben/Empfehlungen bezüglich der Lagerung von Lithium-Batterien kurz dargestellt. Darüber hinaus werden die neusten Entwicklung bezüglich der Vorgaben für den Transports von Natrium-Ionen-Batterien vorgestellt und diskutiert. T2 - 18. Gefahrgut Technik Tage CY - Berlin, Germany DA - 18.11.2021 KW - Lithium-Batterien KW - Sicherheit KW - Thermisches Durchgehen KW - Batterie-Lagerung KW - Batterie-Transport PY - 2021 AN - OPUS4-54078 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -