TY - JOUR A1 - Apel, Andreas A1 - Ballheimer, Viktor A1 - Kuschke, Christian A1 - Schubert, Sven A1 - Wille, Frank T1 - Approach for use of acceleration values for packages of radioactive material under routine conditions of transport N2 - The most relevant source of reference for load cases of packages for the transport of radioactive material under routine conditions is Appendix IV of the International Atomic Energy Agency (IAEA) Advisory Material TS-G-1·1. The acceleration values given there leave many questions open and have to be agreed upon with the involved competent authorities. Consequently, the actual load cases applied for a safety analysis may differ widely and could cause problems for international transport. To avoid such difficulties, it seems obvious that the according passages in TS-G-1·1 should be modified with the objective of making the load case data more consistent for a harmonized application in the IAEA member states. Papers pointing out in this direction were discussed at the PATRAM 2010 conference. The way to improve the acceleration data may lie in investigations and measurements considering, for example different types of vehicles and package masses. However, what should be the goal of such kind of surveys? Can such investigation provide values for every worldwide load case possible under routine conditions of transport? In particular, the different designs of vehicles give a reason to doubt that such an aim is realistic. The approach in this paper is to show that a less ambitious aim is more effective. Therefore, an approximate scheme is preferred, which renders better assistance in determining the appropriate acceleration values. KW - Radioactive materials KW - Safety assessment KW - IAEA regulations KW - Load cases KW - Routine conditions of transport KW - IAEA advisory material TS-G-1.1 KW - Appendix IV KW - Revision of load case data KW - Acceleration values PY - 2013 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 24 IS - 2 SP - 55 EP - 59 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-30378 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Komann, Steffen A1 - Wille, Frank A1 - Schubert, Sven T1 - Neue Regel für das Alterungsmanagement N2 - Die Regelwerksanforderungen für Verpackungen für den Transport radioaktiver Stoffe basieren auf den Empfehlungen der IAEA und werden über die verkehrsträgerspezifischen internationalen Regelwerke in nationales Recht umgesetzt. Um die Anforderungen des Regelwerkes zu erläutern, entwickelt die Bundesanstalt für Materialforschung und -prüfung (BAM) Gefahrgutregeln (BAM-GGR), welche die Entwickler, Hersteller und Betreiber von Behältern über die von der BAM angewandten Verfahren bei der Umsetzung gesetzlicher Bestimmungen informieren und unterstützen sollen. KW - Gefahrgut KW - Radioaktive Stoffe KW - Alterung KW - Transport PY - 2023 VL - 2023 IS - 9 SP - 16 EP - 18 PB - Heinrich Vogel CY - München AN - OPUS4-58577 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rolle, Annette A1 - Droste, Bernhard A1 - Schubert, Sven A1 - Probst, Ulrich A1 - Wille, Frank T1 - Verification of activity release compliance with regulatory limits within spent fuel transport casks T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Radioactive material KW - Safety assessment KW - Leakage mechanism KW - Leakage rate KW - Sealing behavior PY - 2010 SP - 1 EP - 8(?) AN - OPUS4-32193 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schubert, Sven T1 - Assessment Feedback on Material Compatability and Determination of Material Parameters for Transport Packages used as Dual Purpose Casks T2 - International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2013) CY - San Francisco, CA, USA DA - 2013-08-18 PY - 2013 AN - OPUS4-30264 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Komann, Steffen A1 - Wille, Frank A1 - Rolle, Annette A1 - Probst, Ulrich A1 - Schubert, Sven T1 - Consideration of aging mechanism influence on transport safety of dual purpose casks for spent nuclear fuel of HLW N2 - When storage of spent nuclear fuel or high level waste is carried out in dual purpose casks (DPC), the effects of aging on safety relevant DPC functions and properties have to be managed in a way that a safe transport after the storage period of several decades is capable and can be justified and certified permanently throughout that period. The effects of aging mechanisms (e.g. radiation, different corrosion mechanisms, stress relaxation, creep, structural changes and degradation) on the transport package design safety assessment features have to be evaluated. Consideration of these issues in the DPC transport safety case will be addressed. Special attention is given to all cask components that cannot be directly inspected or changed without opening the cask cavity, like the inner parts of the closure system and the cask internals, like baskets or spent fuel assemblies. The design criteria of that transport safety case have to consider the operational impacts during storage. Aging is not the subject of technical aspects only but also of ‘intellectual’ aspects, like changing standards, scientific/technical knowledge development and personal as well as institutional alterations. Those aspects are to be considered in the management system of license holders and in appropriate design approval update processes. The paper addresses issues that are subject of an actual International Atomic Energy Agency TECDOC draft 'Preparation of a safety case for a dual purpose cask containing spent nuclear fuel'. KW - Transport KW - Storage KW - Spent fuel KW - High-level waste KW - Aging KW - Metal seals KW - Transport and storage casks KW - Spent nuclear fuel KW - Aging mechanisms KW - Corrosion KW - Safety assessment PY - 2014 DO - https://doi.org/10.1179/1746510914Y.0000000070 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 25 IS - 3-4 SP - 105 EP - 112 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-33428 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Quercetti, Thomas A1 - Müller, Karsten A1 - Schubert, Sven T1 - Comparison of experimental results from drop testing of a spent fuel package design using a full-scale prototype model and a reduced-scale model T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 KW - Drop KW - Testing KW - Experiment KW - Prototype KW - Reduced-scale KW - Full-scale PY - 2007 SP - 1 EP - 8 PB - Institute of Nuclear Materials Management AN - OPUS4-18624 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Quercetti, Thomas A1 - Müller, Karsten A1 - Schubert, Sven T1 - Comparison of experimental results from drop testing of spent fuel package design using full scale prototype model and reduced scale model N2 - This paper presents a comparison between full scale prototype and reduced scale model drop test data in regard to similarity mechanics. Together with a current BAM research project, the paper contributes to the further development of mechanical evaluation methods for safety assessment of RAM transport and storage packages including the transferability of package impact response from reduced scale models to full scale packages. KW - Full scale KW - Reduced scale KW - Drop testing KW - Similarity PY - 2008 DO - https://doi.org/10.1179/174651008X362575 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 19 IS - 4 SP - 197 EP - 202 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-20135 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Schubert, Sven A1 - Probst, Ulrich A1 - Winkler, H. P. T1 - Behaviour of metallic seals in CASTOR casks under normal and accident conditions of transport: qualification requirements KW - Transport cask KW - Seal KW - Leak tightness KW - Accident KW - Qualification program KW - Transportbehälter KW - Radioaktive Stoffe KW - Dichtung KW - Dichtheit KW - Unfall KW - Qualifikationsprogramm PY - 2009 DO - https://doi.org/10.1179/174651009X12555104004055 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 20 IS - 4 SP - 179 EP - 182 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-20708 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Schubert, Sven A1 - Kraus, Werner T1 - Verhalten von metallenen Großpackmitteln (IBC) und ihrer Druckausgleichseinrichtungen unter äußerer Feuereinwirkung PY - 1999 SN - 1434-9728 SN - 1436-4948 SN - 0372-2457 SN - 0376-1185 VL - 40 IS - 4 SP - 37 EP - 41 PB - Springer-VDI-Verl. CY - Düsseldorf AN - OPUS4-12035 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schubert, Sven T1 - Behaviour of metallic seals in CASTOR-casks under normal and accident conditions of transport: qualification requirements T2 - PATRAM 2007, The 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, FL, USA DA - 2007-10-22 PY - 2007 AN - OPUS4-16143 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -