3.3 Sicherheit von Transportbehältern
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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.
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.
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.
The first German package design approval certificate for a dual purpose cask intended for loading with damaged spent nuclear fuel was issued recently. BAM as part of the competent authority system in Germany carried out a comprehensive assessment procedure with respect to the mechanical and thermal design, the release of radioactive material and the quality assurance aspects of manufacturing and operation. Packages for the transport and storage of radioactive material have been assessed by BAM for many years, thus the common assessment procedure is well-known and good practice. Up to now only SNF without defects or HLW with well-defined properties were designated for long-term Interim storage and transports afterwards. Due to Germany’s nuclear phase out all other kinds of spent nuclear fuel in particular damaged spent nuclear fuel shall be packed as well. Damaged spent nuclear fuel needs a tight closure with Special encapsulations and clearly defined properties in Germany. In addition, these encapsulations shall be long-term durable, because they are not accessible after loading in a packaging within periodical inspections. The main difference to Standard package components is that encapsulations with a permanent closure achieve their specified conditions not after manufacturing but only during operation, after loading and closing. To ensure compliance with the specific conditions, special measures for quality assurance are necessary during operation of each encapsulation, e.g. drying and sealing, which were assessed by BAM. The present paper gives an overview of the conducted assessment from BAM and point out the findings concerning to the special closure lid of the approved encapsulation, which is screwed and welded. A wide verification concept is necessary to show the specific tightness under transport conditions. Together with quality assurance measures during first operation steps these encapsulations with damaged spent nuclear fuel can be handled like standard fuel assemblies in approved package designs.
German package design approvals were granted recently for dual purpose casks (DPC) intended for loading with encapsulated damaged spent nuclear fuel (DSNF). Comprehensive assessment procedures were carried out by the authority BAM with respect to the mechanical and thermal package design, the activity release of radioactive material and quality assurance aspects for manufacturing and operation of each packaging. The objective of each procedure was to verify the Package Design Safety Report (PDSR) and the relevant guidelines fulfils the requirements of the IAEA regulations.
Previous approvals of German SNF package designs consider mainly standard fuel assemblies with defined specifications and properties for transport and interim storage. Due to the nuclear power phase-out in Germany all kinds of SNF, e.g. damaged spent fuel rods shall be packed in DPC now. Therefore specific requirements shall be considered in accordance with international experiences including IAEA technical reports. The main requirement for DSNF is a tight encapsulation with specific defined properties under transport and storage conditions.
Due to the interim storage period of currently up to 40 years the encapsulation with DSNF in the casks shall also be long term durable. Thus specific loading and drying procedures are necessary and had to be qualified during the approval process. BAM assessed these drying procedures and could confirm the long-term behaviour of the encapsulation and the suitability of the drying equipment. This special equipment was qualified in a “cold handling”. In addition, it was shown that the behaviour of the test equipment used in the qualification process was comparable with the original equipment, e.g. test fuel rods or test encapsulation. In the development of the drying process, experience was obtained in how to put the requirements of the IAEA regulations and related IAEA technical reports into practice.
The paper gives an overview of approval assessment and testing experience made by BAM and point out the main resulting requirements on drying processes for these kinds of encapsulations with DSNF.
Atemluftflaschen aus Faserverbundwerkstoffen werden bei einem Brandeinsatz situationsabhängig hohen thermischen Belastungen ausgesetzt. Die Grenzen der sicheren thermischen Belastbarkeit dieser Behälter werden jedoch heutzutage nicht abgeprüft. Deshalb hat 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.
In diesem vierten und letzten Teil dieser Aufsatzreihe werden die Ergebnisse der analytischen Beanspruchungsanalysen vorgestellt, die mit dem entwickelten Hybrid-Behältermodell berechnet wurden. Unter simulierten Einsatzbedingungen des Brandeinsatzes wird dabei ein bisher nicht hinreichend beachtetes thermisches Degradationsverhalten berücksichtigt. Zur Bewertung der realen Degradation einer Atemluftflasche im Feuerwehrbetrieb, werden zudem die Ergebnisse von 90 zerstörenden Prüfungen vorgestellt, die an altersbedingt ausgesonderten Atemluftflaschen durchgeführt wurden. Die Erkenntnisse dieser Untersuchungsreihe werden final in einer sicherheitstechnischen Bewertung kondensiert.
German package design approvals were granted recently for dual purpose casks (DPC) intended for loading with encapsulated damaged spent nuclear fuel (DSNF). Comprehensive assessment procedures were carried out by the authority BAM with respect to the mechanical and thermal package design, the activity release of radioactive material and quality assurance aspects for manufacturing and operation of each packaging. The objective of each procedure was to verify the Package Design Safety Report (PDSR) and the relevant guidelines fulfils the requirements of the IAEA regulations.
Previous approvals of German SNF package designs consider mainly standard fuel assemblies with defined specifications and properties for transport and interim storage. Due to the nuclear power phase-out in Germany all kinds of SNF, e.g. damaged spent fuel rods shall be packed in DPC now. Therefore specific requirements shall be considered in accordance with international experiences including IAEA technical reports. The main requirement for DSNF is a tight encapsulation with specific defined properties under transport and storage conditions.
Due to the interim storage period of currently up to 40 years the encapsulation with DSNF in the casks shall also be long term durable. Thus specific loading and drying procedures are necessary and had to be qualified during the approval process. BAM assessed these drying procedures and could confirm the long-term behaviour of the encapsulation and the suitability of the drying equipment. This special equipment was qualified in a “cold handling”. In addition, it was shown that the behaviour of the test equipment used in the qualification process was comparable with the original equipment, e.g. test fuel rods or test encapsulation. In the development of the drying process, experience was obtained in how to put the requirements of the IAEA regulations and related IAEA technical reports into practice.
The paper gives an overview of approval assessment and testing experience made by BAM and point out the main resulting requirements on drying processes for these kinds of encapsulations with DSNF.
Atemluftflaschen aus Faserverbundwerkstoffen werden bei einem Brandeinsatz situationsabhängig hohen thermischen Belastungen ausgesetzt. Die Grenzen der sicheren thermischen Belastbarkeit dieser Behälter werden jedoch heutzutage nicht abgeprüft. Deshalb hat 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 Untersuchungen sollen genutzt werden, um zu beurteilen, wie thermische Betriebsbedingungen in normierten Prüfkriterien sicherheitstechnisch berücksichtigt werden sollten.
Um die Beanspruchungen innerhalb des Behältermaterials berechnen zu können wird in diesem dritten Teil der Aufsatzreihe die Entwicklung eines analytischen Hybrid-Behältermodells vorgestellt, in dem die für den Brandeinsatz zu erwartenden Materialtemperaturen, deren Ermittlung im Fokus des ersten und zweiten Teils dieser Untersuchungsreihe standen, eingebunden werden. Dabei werden im Modell erstmalig Schädigungsmechanismen berücksichtigt, die eine thermische Überbelastung des Faserverbundwerkstoffs einbeziehen.
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.
Atemluftflaschen aus Faserverbundwerkstoffen werden bei einem Brandeinsatz situationsabhängig hohen thermischen Belastungen ausgesetzt. Die Grenzen der sicheren thermischen Belastbarkeit dieser Behälter werden jedoch heutzutage nicht abgeprüft. 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 sollen genutzt werden, um zu beurteilen, wie thermische Betriebsbedingungen in normierten Prüfkriterien sicherheitstechnisch berücksichtigt werden sollten.
In diesem zweiten Teil der Untersuchungsreihe werden Strömungsversuche dargestellt, die an dem untersuchten Baumuster einer Typ-III-Atemluftflasche unter Laborbedingungen durchgeführt wurden. Basierend auf den Wärmestrahlungsversuchen des ersten Teils dieser Untersuchungsreihe und auf den Strömungsversuchen wird ein analytischer Berechnungsansatz vorgestellt, der die instationäre Temperaturentwicklung im Material der Typ-III-Atemluftflasche konservativ annähert.
Anhand der berechneten Materialtemperaturen kann festgestellt werden, dass unter dem typischen Feuerwehr-Belastungsprofils von 130 °C bis 250 °C die Zulassungstemperatur der Typ-III-Atemluftflasche von 65 °C um bis zu 95 °C überschritten werden kann. Aus diesen Temperaturüberschreitungen können zwei Unsicherheiten identifiziert werden. Die Auslegung des Faserverbundwerkstoffs orientiert sich normgerecht an der oberen Zulassungstemperatur. Wird die Typ-III-Atemluftflasche im Brandeinsatz eingesetzt, ist es möglich, dass der lasttragende Faserverbundwerkstoff partiell über seinen nominellen Auslegungsbereich hinaus erwärmt wird. Eine weitere Unsicherheit ergibt sich für den Sicherheitsnachweis im Rahmen der Zulassungsprüfung. Für die Typ-III-Atemluftflaschen erfolgen für den Temperaturbereich des Brandeinsatzes kein statischer und kein dynamischer Festigkeitsnachweis.