TY - CONF A1 - Wille, Frank T1 - Retaining Competence for Safe Transports of Radioactive Material N2 - 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. T2 - 7th Nuclear Decommissioning & Waste Management Summit 2020 CY - London, UK DA - 12.02.2020 KW - Aging management KW - Transport KW - Spent fuel behaviour KW - Disposal PY - 2020 AN - OPUS4-50987 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schönfelder, Thorsten T1 - Kerntechnische Entsorgung Herausforderungen im Transport und bei der Lagerung N2 - Nach der Reaktorkatastrophe in Fukushima 2011 hat die Bundesregierung beschlossen die Nutzung der Kernenergie bis zum Jahr 2022 zu beenden. Seitdem erfolgt der Rückbau und die Stilllegung der kerntechnischen Anlagen in Deutschland. Dieser Vortrag erörtert die Herausforderungen, die sich mit dem Transport und der Lagerung von Kernbrennstoffen ergeben und leitet daraus Anforderungen ab, die an Transportbehälter gestellt werden. T2 - Ausgewählte Kapitel der Werkstofftechnik - Brand- und Explosionsverhalten von Werkstoffen CY - Wuppertal, Germany DA - 24.01.2020 KW - Kerntechnische Entsorgung KW - Rückbau KW - Transport- und Lagerbehälter PY - 2020 AN - OPUS4-50428 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schlick-Hasper, Eva T1 - Vergleichende Fallversuche zur Bewertung von Fallfundamenten - Ausblick auf Untersuchungen der BAM N2 - Oft verfügen Produktionsstätten über bereits verbaute Fallfundamente, die nicht das geforderte Massenverhältnis von 1:50 aufweisen. Gemäß ADR ist jedoch auf dem Niveau der Musterprüfung zu prüfen. Es ist daher fraglich, ob die Prüfungen im Rahmen der Eigenüberwachung und die Baumusterprüfungen vergleichbare Ergebnisse liefern, wenn die Fallfundamente unterschiedlich beschaffen sind. Ziel der Untersuchungen ist daher die Entwicklung eines Untersuchungs- und Prüfkonzepts für bereits verbaute Fallfundamente für Gefahrgutverpackungen im Rahmen einer ingenieurwissenschaftlichen Promotionsarbeit. T2 - 33. Sitzung des BAM AK Prüfstellen CY - Online meeting DA - 16.09.2020 KW - Gefahrgutverpackungen KW - Fallfundamente PY - 2020 AN - OPUS4-51250 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schlick-Hasper, Eva T1 - Vergleichende Schüttwinkelmessungen - Ausblick auf Untersuchungen der BAM N2 - Es ist bislang noch keine einheitliche Vorgehensweise und kein bestimmtes Prüfverfahren für die Schüttwinkelmessung festgelegt. Bei den Prüffüllgütern handelt es sich nicht nur um gefährliche Ersatzfüllgüter, sondern zum Teil auch um gefährliche Originalfüllgüter. Es liegen noch keine systematische Untersuchungen darüber vor, welche der in den Prüfstellen gängigen Methoden sich prinzipiell für die Anwendung bei bestimmten Extremfällen von Füllgütern eignen. Ziel der Untersuchungen ist daher ein systematischer Vergleich bei der Anwendung verschiedener in den Prüfstellen gängiger Schüttwinkelmessmethoden. T2 - 33. Sitzung des BAM AK Prüfstellen CY - Online meeting DA - 16.09.2020 KW - Gefahrgutverpackungen KW - Schüttwinkel PY - 2020 AN - OPUS4-51248 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schlick-Hasper, Eva T1 - Vergleichende Fallversuche zur Bewertung von Fallfundamenten - Ausblick auf Untersuchungen der BAM N2 - Es wird ein Ausblick auf Untersuchungen der BAM gegeben, die im Rahmen einer ingenieurwissenschaftlichen Promotionsarbeit durchgeführt werden sollen. T2 - 40. Sitzung des ERFA Verpackungen CY - Online meeting DA - 05.11.2020 KW - Gefahrgutverpackungen KW - Fallfundamente PY - 2020 AN - OPUS4-51543 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 - CONF A1 - Feldkamp, Martin T1 - Heat Flux from Wood Filled Impact Limiter under Fire Conditions N2 - 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 smouldering and influence the cask thermal behaviour 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. T2 - 9th International Scientific Conference - wood & fire safety 2020 CY - Online meeting DA - 02.11.2020 KW - Fre KW - Smouldering KW - Wood PY - 2020 AN - OPUS4-51517 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schlick-Hasper, Eva T1 - Industrial leak testing of dangerous goods packagings N2 - The Dangerous Goods Regulations currently do not include limit leakage rates or sensitivity requirements for industrial leak testing procedures that are equivalent to the bubble test, which is the prescribed test method for design type testing of dangerous goods packagings. During series production of such packagings, various methods are used which often do not reach the sensitivity of the bubble test. Based on a suitable pragmatic approach, its sensitivity under industrial conditions can be considered 10-4 Pa m³/s (SLR). For the selection of a suitable industrial leak testing method, however, factors other than the sensitivity are also important, for example flow direction, pressure level and automatability. The following methods are in principal suitable and equally effective as the bubble test: pressure rise test (vacuum chamber), ultrasonic bubble leak detection and gas detection methods (pressure technique by accumulation and vacuum chamber technique). To ensure a uniform test level during design type testing and production line leak testing and therefore a comparable safety level as required by the Dangerous Goods Regulations, it is necessary to include a more precise specification in these regulations. On the one hand, this requires an information about the sensitivity of the bubble test, on the other hand, the inclusion of a list of suitable, equally effective industrial test methods with their specific boundary conditions T2 - 22nd IAPRI World Packaging Online Conference CY - Online meeting DA - 15.06.2020 KW - Bubble test KW - Dangerous goods packagings KW - Industrial leak testing KW - Leakproofness test KW - Series production PY - 2020 AN - OPUS4-51132 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 - 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 -