TY - JOUR A1 - Kasparek, Eva Maria A1 - Völzke, Holger A1 - Scheidemann, Robert A1 - Zencker, Uwe A1 - Wolff, Dietmar T1 - Experimental and numerical studies of shock absorbing materials for containers for radioactive waste PY - 2012 SN - 1431-5254 VL - 57 IS - 6 SP - 397 EP - 401 PB - Inforum CY - Berlin AN - OPUS4-26261 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Kasparek, Eva Maria A1 - Völzke, Holger A1 - Scheidemann, Robert A1 - Zencker, Uwe T1 - Numerical and experimental investigations of polyurethane foam for use as cask impact limiter in accidental drop scenarios T2 - WM2012 - Waste management conference CY - Phoenix, AZ, USA DA - 2012-02-26 KW - Plasticity KW - Finite elements KW - Material models KW - Rate dependency KW - Temperature dependency KW - Compression tests KW - Drop tests KW - Parameter identification PY - 2012 SN - 978-0-9836186-1-4 N1 - Serientitel: WM Symposia – Series title: WM Symposia IS - Paper 12099 SP - 1 EP - 9 AN - OPUS4-26270 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Wolff, Dietmar A1 - Kasparek, Eva Maria A1 - Botsch, W. A1 - Drotleff, H.-W. A1 - Hinterding, P. A1 - Smalian, S. T1 - Safety aspects of dry spent fuel storage and spent fuel management N2 - Dry storage Systems are characterized by passive and inherent safety systems ensuring safety even in case of severe incidents or accidents. After the events of Fukushima, the advantages of such passive and inherently safe dry storage systems have become more and more obvious. In Germany dry storage of spent nuclear fuel (SNF) and high level wastes (HLW) in dual purpose casks fulfills both transport and storage requirements. Basic safety requirements consider safe enclosure of the radioactive materials under normal operation and accident conditions, safe decay heat removal, subcriticality and shielding. Mostly, storage facilities are designed as concrete buildings above the ground, but due to regional constraints, one storage facility has also been built as a rock tunnel. The decay heat is always removed by natural air flow; further technical equipment is not needed. Safe enclosure, subcriticality and shielding are mainly guaranteed by massive thick-walled metal casks. TÜV NORD Nuclear and BAM present their long experience concerning the licensing process for sites and casks and inform about spent fuel management and issues concerning dry storage of spent fuel and high level waste. T2 - ENC 2012 - European Nuclear Conference CY - Manchester, UK DA - 10.12.2012 KW - Spent nuclear fuel (SNF) KW - High level waste (HLW) KW - Dry storage systems KW - Safety assessment PY - 2012 SN - 978-92-95064-14-0 SP - 1 EP - 5 PB - European Nuclear Society CY - Brussels, Belgium AN - OPUS4-27557 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Protz, Christian A1 - Völzke, Holger A1 - Ellouz, Manel A1 - Kasparek, Eva Maria A1 - Zencker, Uwe A1 - Grünewald, Heike A1 - Gründer, Klaus-Peter T1 - ConDrop - Development of numerical simulation approaches for drop test analyses of steel sheet containers N2 - According to disposal requirements, containers for radioactive waste have to withstand drop tests at defined conditions corresponding to the considered package category. Alternatively to prototype drop tests, numerical methods can be applied, if they are suitable and sufficiently verified. In this context BAM (Federal Institute for Materials Research and Testing) started the research project ConDrop to develop a reliable Finite Element (FE) model describing the mechanical behavior of a box shaped steel container during a drop test and to determine unfavorable scenarios within future safety assessment procedures of comparable steel sheet containers. In a first step, a FE model of a representative steel sheet container was developed. Flat bottom-side drop tests with the unloaded container from different heights onto an IAEA target were simulated. In order to verify the numerical calculations, two drop tests with an unloaded KONRAD Type V steel sheet container were carried out at the BAM drop test facility. Both drop tests (flat drop from heights 0.4 m and 5 m onto the unyielding IAEA target) had been documented by various extensive measurements: strain and deceleration measurement by means of strain gauges and accelerometers, high-speed video as well as optical 3D-measurements using the method of projected fringes in combination with close range photogrammetry. The measured strain and deceleration values are presented and compared with the calculated results. T2 - 53rd INMM Annual meeting CY - Orlando, FL, USA DA - 15.07.2012 KW - INMM 53rd annual meeeting PY - 2012 SP - 1 EP - 7 AN - OPUS4-26417 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -