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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.
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.
Atemluftflaschen aus Faserverbundwerkstoffen werden im Feuerwehrbetrieb hohen thermischen Belastungen ausgesetzt. Der thermisch sichere Bereich dieser Behälter ist jedoch heutzutage noch nicht einschätzbar. Deshalb haben es sich die Bundesanstalt für Materialforschung und -prüfung (BAM) im Austausch mit der Bergischen Universität Wuppertal zur Aufgabe gemacht, die Auswirkungen dieser Betriebslasten zu untersuchen. Die Erkenntnisse dieser Untersuchungsreihe werden genutzt, um einzuschätzen, ob es sicherheitstechnisch notwendig ist, besondere thermische Betriebsbedingungen in normativen Prüfkriterien zu berücksichtigen.
In einem ersten Schritt wurden Typ-III-Atemluftflaschen der Berliner Feuerwehr Umgebungsbedingungen des typischen Belastungsprofils der Brandbekämpfung (130 °C bis 250 °C, 10 Minuten) ausgesetzt, um die Erwärmung des Behältermaterials zu erfassen. Da die Größe der bestrahlten Oberfläche in einem Brandeinsatz nicht bekannt ist, erfolgte zusätzlich eine Variation der Strahlungsexposition. Strömungsprozesse, die in einem Brandeinsatz den Behälter von innen kühlen, wurden in diesem ersten Untersuchungsabschnitt noch nicht betrachtet.
Es konnte gezeigt werden, dass der Aluminium-Liner einer Typ-III-Atemluftflasche einen erheblichen Einfluss auf die Temperaturverteilung im Behältermaterial ausübt. Die hohe Leitfähigkeit des Aluminiums führt bei Verringerung der bestrahlten Behälteroberfläche zu hohen Temperaturgradienten innerhalb der Behälterwand. Die Materialtemperaturen in der Atemluftflasche konnten für das Belastungsprofil der Brandbekämpfung auf ein typisches Temperaturintervall eingegrenzt werden. Die Grenzen liefern Aussagen zur exponierten Behälteroberfläche und liegen zwischen einseitiger und Vollbestrahlung.
The arrangement of the measuring sensors allowed the
capture of air flow induced temperatures and material
temperatures on various points of the cylinder body. Four
significant temperature levels could be observed: Inside the cylinder (far from the wall, close to the wall), inside the aluminium liner and outer surface. Figure 5 shows the temperature distribution after a regular filling process with a filling time of ten minutes. The temperature sensors T1 - T9 are marked with different colors. The corresponding measurement points are shown in Figure 4. Due to the high thermal conductivity of the aluminum liner the induced temperature peaks are quickly derived. A flow-induced exceeding of the maximum approval temperature is not expected. Regarding the safety assessement the results show that the pressure and temperature profilesmustbe taken into account.
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.
Assessment experience on packages loaded with damaged spent nuclear fuel for transport after storage
(2018)
In 2017 the first German package approval certificate was issued for a dual purpose cask (DPC) design with encapsulated damaged spent nuclear fuel. At the Bundesanstalt für Materialforschung und -prüfung (BAM) a comprehensive assessment procedure was carried out with respect to the mechanical and thermal design, the containment design and quality assurance for manufacturing and operation. Main objective of this procedure was to verify the Package Design Safety Report (PDSR) fulfils the requirements according to the IAEA regulations SSR-6.
Until now only standard spent nuclear fuel assemblies were designated for interim storage and transports. Due to nuclear phase out in Germany all other kinds of SNF in particular damaged fuel has to be packed. Therefore specific requirements have to be considered in accordance with international experiences written in IAEA technical reports. In Germany damaged spent nuclear fuel (DSNF) needs a tight encapsulation with special encapsulations and clearly defined properties.
Due to the limited amount of DSNF these encapsulations are designed for storage and transport in existing packages. From the assessment experience it has been seen, corresponding PDSR need an extensively expansion to cover the design of these encapsulations and their influences on the package. Then such well-defined encapsulations can be handled like standard fuel assemblies. The main difference to standard package components is, encapsulations with permanent closure achieve their specified condition not after manufacturing but only during operation after loading and closing.
Thus specific handling instruction and test procedures are necessary especially for welding, where BAM is able to survey the quality of this first part of operation.
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 deutlich überschritten wird.
Durch experimentelle Temperaturversuche an Typ-III-Atemluftflaschen mit einem Innenbehälter aus Aluminium 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. Zudem wurden insgesamt 90 altersbedingt ausgesonderte Feuerwehr-Atemluftflaschen zerstörend geprüft, um nähere Erkenntnisse über den Sicherheitszustand am Ende der Lebenszeit zu erhalten.
In diesem Kolloquium werden Forschungsergebnisse vorgestellt, die im Rahmen einer Promotionsarbeit die Auswirkungen dieser erhöhten thermischen Betriebslasten auf eine Typ-III-Atemluftflasche mit einem Innenbehälter aus Aluminium darstellen und bewerten.
