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 - Botsch, W. A1 - Smalian, S. A1 - Hinterding, P. A1 - Völzke, Holger A1 - Wolff, Dietmar A1 - Kasparek, Eva Maria T1 - Dual purpose cask safety evaluation - Expertise in dry storage N2 - In Germany dual purpose casks for spent nuclear fuel (SF) or high level radioactive waste (HLW) are used for safe transportation and interim storage. Key safety issues in both fields are the safe enclosure of the radioactive material, the safe removal of decay heat, securing nuclear criticality safety, limitation of radiation exposure to acceptable levels and keeping it as low as reasonable achievable (ALARA principle). Whereas these safety requirements during transportation are ensured by the Type-B(U)-design testing and approval procedure on basis of internationally agreed IAEA (International Atomic Energy Agency) requirements storage licenses are issued on national and site specific safety analyses. This paper presents experiences from recent interim storage safety evaluation and licensing procedures in Germany on basis of a Type-B(U) certified cask designs concerning specific differences from Operation and accident conditions inside the storage facility. The focus is laid on the interaction of cask and building structures with regard to shielding, heat removal and accident analyses including aircraft crash. Basic safety is assured by thick-walled metal casks with monitored double lid Systems. They also reduce radiation to levels where workers can safely operate and maintain the casks inside the storage facility. The storage building e. g. provides additional shielding and protection against extemal hazards depending on the building construction. In addition, the storage building helps to reduce radiation levels at the boundary of the storage site well below regulatory limits given by the German Radiation Protection Ordinance (StrSchV). T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 18.08.2013 KW - Dual purpose cask KW - Long-term storage PY - 2013 SP - 1 EP - 8 PB - Omnipress AN - OPUS4-30235 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -