TY - CONF A1 - Schönfelder, Thorsten A1 - Müller, Lars A1 - Komann, Steffen A1 - Wille, Frank ED - Schönfelder, Thorsten T1 - Design assessment of a dual purpose cask for damaged spent nuclear fuel N2 - 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. T2 - Proceedings of the 19th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 2019 CY - New Orleans, USA DA - 04.08.2019 KW - Assessment KW - Dual purpose cask KW - Spent nuclear fuel PY - 2019 SP - Paper 1204, 1 EP - 10 AN - OPUS4-48685 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schönfelder, Thorsten T1 - Design Assessment of a Dual Purpose Cask for Damaged Spent Nuclear Fuel N2 - 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. T2 - Proceedings of the 19th International Symposium on the Packaging and Transportation of Radioactive Materials - PATRAM 2019 CY - New Orleans, LA, USA DA - 04.08.2019 KW - Assessment KW - Dual purpose cask KW - Spent nuclear fuel PY - 2019 AN - OPUS4-48692 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Linnemann, Konrad A1 - Müller, Lars A1 - Schönfelder, Thorsten A1 - Komann, Steffen A1 - Wille, Frank T1 - Authority Experience during Design Approval Procedure for Packages Loaded with Special Encapsulations for Damaged Spent Nuclear Fuel N2 - 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. T2 - International Conference on the Management of Spent Fuel from Nuclear Power Reactors CY - Vienna, Austria DA - 24.06.2019 KW - Transport package KW - Design approval KW - Spent nuclear fuel KW - Special encapsulation PY - 2019 SP - 1 EP - 9 AN - OPUS4-48749 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schönfelder, Thorsten T1 - Einfluss thermischer Betriebsbelastungen auf die Sicherheit von Typ-III-Druckgasbehältern N2 - 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. T2 - Ausgewählte Kapitel der Werkstofftechnik - Brand- und Explosionsverhalten von Werkstoffen CY - Wuppertal, Germany DA - 11.01.2019 KW - Atemluftflasche KW - Thermische Belastung PY - 2019 AN - OPUS4-49319 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Schönfelder, Thorsten A1 - Mair, Georg W. A1 - Deuerler, F. ED - Schönfelder, Thorsten T1 - Thermische Betriebslasten von Atemluftflaschen im Feuerwehreinsatz, Teil IV: Sicherheitstechnische Bewertung N2 - 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. KW - Composite KW - Degradation KW - Druckgasbehälter KW - Faserverbundwerkstoff KW - Feuerwehr KW - Sicherheit PY - 2019 SN - 2191-007 VL - 9 IS - 07/08 SP - 36 EP - 41 PB - Springer CY - Düsseldorf AN - OPUS4-48691 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -