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In Germany the concept of dry interim storage of spent fuel in dual purpose metal casks is implemented, currently for periods of up to 40 years. The casks being used have an approved transport package design in accordance with the international IAEA transport regulations as well. The storage of spent nuclear fuel and high-level waste in dual purpose casks (DPC) is related with the challenge of maintaining safety for transportation over several decades of storage.
Besides consideration of aging mechanisms by appropriate design, material selection and operational controls to assure technical reliability by aging management measures, an essential issue is the continuous control and update of the DPC safety case.
Not only the technical objects are subject of aging but also the safety demonstration basis is subject of “aging” due to possible changes of regulations, standards and scientific/technical knowledge.
To ensure a safe transport in future to a destination which is not known yet (because of not yet existing repository sites) periodical reviews of the Package Design Safety Report (PDSR), in connection with periodic renewals of package design approval certificates, have to be carried out.
Das Einsatzspektrum von den besonders leichten Druckbehältern aus Faserverbund-werkstoffen erweitert sich kontinuierlich. Dies führt dazu, dass mit der erweiterten Verwendung auch die thermisch zulässigen Einsatzgrenzen dieser Behälter ausgeschöpft und sogar teilweise überschritten werden. So können bspw. Atemluftflaschen im Brandeinsatz der Feuerwehr an der Behälteroberfläche derart hohen Umgebungstemperaturen ausgesetzt werden, dass die zulässige Höchsttemperatur von 65 °C um bis zu 185 °C überschritten wird.
Diese Arbeit untersucht und bewertet die Auswirkungen dieser erhöhten thermischen Betriebslasten auf die Typ-III-Atemluftflasche. Dieser Behältertyp besteht aus einem Innenbehälter aus Aluminium, der von einem Faserverbundwerkstoff umschlossen ist.
Durch Analyse der thermischen Betriebslasten in ausgewählten Anwendungsbereichen und durch experimentelle Temperaturversuche an Probebehältern konnte gezeigt werden, dass bei der Brandbekämpfung die untersuchten Atemluftflaschen lokal über das in der Zulassung abgeprüfte Temperaturspektrum erhitzt werden. Der Glasübergangsbereich des Faserverbundwerkstoffs wird partiell um bis zu 95 °C überschritten. Um die reale Sicherheit der Atemluftflasche bewerten zu können, wurde ein analytisches Hybridbehältermodell entwickelt, das die Beanspruchungen mit validierten Materialtemperaturverläufen berechnet. Mit der Einbindung von Schädigungsansätzen konnte ein bisher nicht hinreichend beachtetes thermisches Degradationsverhalten in den Berechnungen berücksichtigt werden. Die sicherheitstechnische Bewertung basierte auf der Gegenüberstellung der Beanspruchungen aus den realen Betriebsbelastungen und abzuprüfenden Zulassungskriterien. Zudem wurden insgesamt 90 altersbedingt ausgesonderte Feuerwehr-Atemluftflaschen zerstörend geprüft, um nähere Erkenntnisse über den Sicherheitszustand am Ende der Lebenszeit zu erhalten. Die Versuche wurden ebenfalls zur Validierung der Schädigungsansätze genutzt.
Als Ergebnis der Arbeit wird am Beispiel des untersuchten Baumusters gezeigt, dass die Sicherheit dieser Atemluftflasche am Lebensende noch hinreichend ist. Jedoch konnte an einigen Exemplaren dieses großzügig dimensionierten Baumusters eine erhöhte Abnahme der Festigkeit festgestellt werden. Sollten Atemluftflaschen auf die vorgeschriebenen Normanforderungen optimiert werden, d.h. weniger überdimensioniert sein, wäre dem thermisch bedingten Sicherheitsverlust eine erheblich detailliertere Aufmerksamkeit zu widmen.
Typical transport packages used in Germany are equipped with wooden impact limiting devices. In this paper we give an overview of the latest status regarding the development of a finite element material model for the crush of spruce wood. Although the crush of wood – mainly in longitudinal direction – is a phenomenon governed by macroscopic fracture and failure of wood fibres we smear fracture and failure mechanisms over the continuous voume. In first step we altered an existing LS-DYNA material model for foams, which considers an ellipse shaped yield surface written in terms of the first two stress invariants. The evolution of the yield surface in the existing model depends on the volumetric strain only. For the use with spruce wood, we modified the existing material model to consider the deviatoric strain for the evolution of the yield surface as well. This is in accordance with the results of crush tests with spruce wood specimens, where the crushing deformation was rather deviatoric for uniaxial stress states and rather volumetric for multiaxial stress states We rate the basic idea of this approach to be reasonable, though other problems exist regarding the shape of the yield surface and the assumption of isotropic material properties. Therefore we developed a new transversal isotropic material model with two main directions, which considers different yield curves according to the multiaxiality of the stress state via a multi-surface yield criterion and a non-associated flow rule. The results show the ability to reproduce the basic strength characteristics of spruce wood. Nevertheless, problems with regularization etc. show that additional investigations are necessary.
Packages for the transport of radioactive material are often equipped with impact limiters consisting of wood, encapsulated by steel sheets. These impact limiters shall ensure that transport casks meet the IAEA safety requirements. After damage caused by the mechanical tests the package has to withstand a severe fire scenario. It is required that the mechanical tests have to produce maximum damage, taking into account the thermal test. Furthermore, any damage, which would give rise to increased radiation or loss of containment or affect the confinement system after the thermal test, should be considered. Concerning the thermal test, the IAEA safety requirements state that during and following the fire test, the specimen shall not be artificially cooled and any combustion of materials of the package shall be permitted to proceed naturally. Different works from the French Institute for Radiological Protection and Nuclear Safety (IRSN) and BAM show that additional energy supply from a pre-damaged impact limiter to the cask could occur caused by smoldering of the wood. This effect should be considered within the safety assessment of the package. A heat wave from the fire could overlap with the additional energy from the impact limiter in the sealing system. In 2015 BAM conducted small scale
fire tests with wood filled metal drums showing continuing combustion processes during the cooling down phase. As not much is known about smoldering processes in wood filled impact limiters, it is highly complex to define pre-damage of impact limiters, which are conservative, regarding the most damaging energy flow from the impact limiter to the containment system in dependence of time. More research has to be done to develop models to examine the effects of smoldering impact limiters on the containment of packages for the assessment. The process of smoldering is described with regard to the requirements in the thermal safety assessment. Parameters influencing the smoldering process are identified. BAM operates test facilities to examine the issue of mechanical damage, combustion and heat transfer of packages for transport of radioactive material. A thermal test will take place with a wood filled test specimen with a diameter of about 2.3 meters. The aim is to understand the phenomena of smoldering under the consideration of relevant regulatory boundary conditions.
Packages for the transport of radioactive material are often equipped with impact limiters consisting of wood, encapsulated by steel sheets. These impact limiters shall ensure that the transport casks meet the mechanical and thermal IAEA regulatory test requirements. According to the accident conditions of transport it is mandatory to expose the specimens to a cumulative effect by mechanical and thermal impacts. The mechanical tests consist of a free drop from 9 m onto a flat unyielding target and a 1 m drop onto a puncture bar. After damage caused by mechanical test sequences the package has to withstand a severe fire scenario. Corresponding to the IAEA advisory material it is required that the impact attitudes for the 9 m drop test and for the puncture test have to be such as to produce maximum damage, taking into account the thermal test. Moreover, any damage, which would give rise to increased radiation or loss of containment or affect the confinement system after the thermal test, should be considered. During and following the thermal test, the specimen shall not be artificially cooled and any combustion of materials of the package shall be permitted to proceed naturally. Different works from the French Institute for Radiological Protection and Nuclear Safety (IRSN) and BAM show that additional energy supply from a pre-damaged impact limiter to the cask could occur. This effect should be considered within the safety assessment of the containment. Thermal effects at the closure system of the cask, which might result in an elevated activity release, have to be excluded. BAM conducted small scale tests with wood filled metal buckets showing continuing combustion processes during the cooling down phase. These test results are presented. As not much is known about smouldering processes in wood filled impact limiters, it is highly complex to define pre-damage of impact limiters, which are conservative, regarding the maximum damaging energy flow from the impact limiter to the containment system. More research has to be done to develop models to examine the effects of smouldering impact limiters on the containment of packages for the transport of radioactive material. Aspects of assessment and its difficulties are shown. BAM as a competent authority for the approval of transport casks for radioactive material in Germany operates the test facilities to examine the issue of mechanical damage, combustion and heat transfer for such kind of package systems. For this purpose the knowledge from real drop tests with casks of a mass partly over 100 tons was transferred to a test application. A thermal test will take place with a wood filled test specimen with a diameter of about 2.3 meters. The aim is to understand the phenomena of smouldering under the consideration of relevant regulatory boundary conditions. The process of smouldering is described with regard to the requirements in the thermal assessment of safety of packages for the transport of radioactive material. Requirements concerning the pre-damage of packages for the maximum damage of impact limiters are discussed. Parameters influencing the smouldering process are identified.