TY - CONF A1 - Vlassopoulos, E. A1 - Caruso, S. A1 - Linnemann, Konrad A1 - Nasyrow, R. A1 - Gretter, R. A1 - Fongaro, L. A1 - Papaioannou, D. T1 - Mechanical integrity of spent nuclear fuel rods T2 - Proceedings of ANS Annual Meeting 2018 N2 - The properties of spent nuclear fuel (SNF) rods change significantly during their operation life in the reactor core. Further changes occur after their discharge mainly due to the heating-cooling processes and possible ageing associated with the cumulative effects of radioactive decay induce damage in the fuel. Such changes may affect the response of the SNF rods to mechanical solicitations corresponding to normal and accidental conditions. Research activities at JRC-KARLSRUHE aim at assessing the integrity of SNF rods and processes which might affect their mechanical properties during their interim storage, transport or other handling operations. JRC Hot Cell facilities have been fully adapted to fulfil the experimental goals. The number of experiments that can be performed, however, is limited and there is an acute need to model them, using this process to validate codes, to deeper understand and to extend the results gained at the JRC beyond the conditions that have been tested. For the experimental campaigns two devices for gravitational impact and 3-point bending tests were developed and installed in a hot cell. Segments of real SNF rods pressurized at their original pressures after discharge have been investigated. The setup is fully operational and new results are reported continuously. T2 - ANS Annual 2018 CY - Philadelphia, PA, USA DA - 17.06.2018 KW - Spent nuclear fuel KW - Mechanical testing KW - Hot cell testing PY - 2018 SP - 170 EP - 172 AN - OPUS4-44862 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nasyrow, R. A1 - Papaioannou, D. A1 - Rondinella, V. A1 - Vlassopoulos, E. A1 - Linnemann, Konrad A1 - Ballheimer, Viktor A1 - Sterthaus, Jens A1 - Rolle, Annette A1 - Wille, Frank A1 - Caruso, St. T1 - Bending test device for mechanical integrity studies of spent nuclear fuel rods T2 - PATRAM 2016 - 18th International Symposium on the Packaging and Transportation of Radioactive Materials (Proceedings) N2 - This paper presents data obtained from experiments performed using a bending test set-up developed at the Joint Research Centre (JRC) – Karlsruhe, for spent fuel segment testing. Adjustable sample holders, loading modes and other experimental conditions can be im- plemented in the experiments to study the effects of different deformation ranges up to cladding failure. The experimental set-up has been adapted to hot cell remote controlling and has a modular configuration, which allows manual and motor-driven loading option. The device has been calibrated on hydrogenated, unirradiated cladding tube segments filled with alumina pellets. The final application of present set-up is to test non-defueled spent fuel rod segments, pressurized to the original spent fuel rod pressure level. The range of applicability of this device, the scope of the experimental program and the first results from actual bending tests will be discussed. T2 - PATRAM 2016 - 18th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Kobe, Japan DA - 18.09.2016 KW - Hot cell testing KW - Spent fuel assessment KW - Transport packages PY - 2016 SP - Paper 6023, 1 AN - OPUS4-40002 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Linnemann, Konrad A1 - Ballheimer, Viktor A1 - Rolle, Annette A1 - Wille, Frank T1 - Update on Work and Meetings in Germany about the Spent Fuel Behavior for Transport and Storage N2 - The presentation gives an update about the work on the spent fuel behavior for transport and storage in Germany. Recent developments and meetings are discussed. In this context the results of the hot cell tests on fuel rod segments performed at JRC in Karslruhe in collaboration with BAM are shown. Furthermore, a new research project about the investigations on potential brittle failure of cladding materials under long-term dry interim storage conditions, which is currently starting at BAM 3.4 is presented. T2 - SNL BAM Workshop CY - Albuquerque, NM, USA DA - 14.03.2018 KW - Spent nuclear fuel KW - Fuel rod behavior KW - Hot cell testing PY - 2018 AN - OPUS4-44865 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -