TY - CONF A1 - Völzke, Holger T1 - Transport- and Storage cask safety assessment - drop tests and numerical calculations T2 - Waste Management Symposium 2006 CY - Tucson, AZ, USA DA - 2006-02-26 PY - 2006 AN - OPUS4-12001 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Licensing experience of spent fuel storage/transport casks in germany T2 - International Seminar on Interim Storage of Spent Fuel ISSF 2006 CY - Tokyo, Japan DA - 2006-11-13 PY - 2006 AN - OPUS4-14108 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Drop tests and numerical impact analyses of new cask designs for high activity waste (HAW) and spent fuel - updated BAM design testing experiences - T2 - Waste Management Conference 2007 CY - Tucson, AZ, USA DA - 2007-02-25 PY - 2007 AN - OPUS4-14577 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger 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 - European Nuclear Conference ENC 2012 CY - Manchester, England DA - 09.12.2012 PY - 2012 AN - OPUS4-27116 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Innovative Disposal Container Materials: Improved Durability and Manufacturing Feasibility N2 - Deep geological disposal of high-level radioactive waste (HLW) is the internationally preferred final waste management option to prevent the biosphere from radiologically relevant release of radioactive nuclides for at least 100,000 to 1 million years. Current repository concepts are based on a multi-barrier system consisting of geological, geo-technical and technical barriers as an engineered barrier system (EBS). Considered host rocks are e.g. crystalline rocks, claystone, or rock salt. In all cases disposal containers are a crucial technical barrier to safely enclose the HLW, either spent nuclear fuel (SNF) or vitrified high-level waste (VHLW) from reprocessing. Depending on the repository concept and the respective safety case disposal containers guarantee the safe confinement of their radioactive inventory not just during handling, emplacement, and potential retrieval but also during the post-closure phase of the repository for a certain period. Required container lifetimes usually vary between 1,000 and 100,000 years depending on the selected host rock and repository concept. During container operation and their long-term disposal, they are subject to various mechanical, thermal, radiological, and geo-chemical/biological loads. Thus, mechanical stability and corrosion resistance in the long-term are among the most crucial challenges. Disposal container components lifetimes are typically calculated based on their time-dependent corrosion behaviour, with the implicit assumption that the design remains structurally stable for the required period. Even though, the durability of several component materials subjected to corrosion processes have been previously studied in detail, the interaction of mechanical processes and corrosion calls for further study, and assessment of the impact of joint degradation modes on component lifetimes will result in a more robust and defensible safety case. Besides, as corrosion occurs in a thin interfacial surface layer between the component outermost surface and the environment, specific R&D work is required to understand the long-term performance controlled by the entire engineered barrier system (EBS) and to feed simulation and extrapolations tools by representative experimental data for validation. Another approach to tackle the corrosion issue is to prevent and/or minimize it, thereby ensuring an even safer disposal. In this approach, materials much less prone to corrosion (e.g., copper, ceramic materials) can be used to fabricate the containers. Alternatively, protective coatings (e.g. copper coating) can be applied to current selected reference materials like steels. Both ways require validation of the materials durability under realistic, accelerated field conditions. The InCoManD work package 9 (Innovative and new Container/canister materials under disposal field conditions), part of the EURAD-2 European Partnership on Radioactive Waste Management (2024 – 2029), will address these issues through a collaborative project involving many countries across Europe (and beyond) with a shared goal. Building on the results of the ConCorD work package 15 (Container Corrosion under Disposal Conditions), part of the EURAD-1 programme (2019 - 2024), the InCoManD work package specifically aims to: (i) provide a better understanding of material degradation mechanisms, (ii) define optimised and innovative material solutions, (iii) develop comprehensive predictive models and common methodologies to enhance confidence in the results produced by each partner, and (iv) train new scientists in this field. T2 - safeND 2025 CY - Berlin, Germany DA - 17.09.2025 KW - Radioactive Waste Disposal KW - Disposal Container KW - Deep Geological Repository KW - Engineered Barrier System PY - 2025 DO - https://doi.org/10.5194/safend2025-40 AN - OPUS4-64254 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Research at BAM on Metal Seal Performance and Fuel Rod Integrity N2 - The presentation provides an update on preliminary results from research projects in the area of long term performance of metal seals and fuel rod integrity as safety relevant components of spent fuel transport and storage casks for spent nuclear fuel. T2 - Extended Storage Collaboration Program (ESCP) Winter Meeting 2020 CY - Online meeting DA - 09.11.2020 KW - Metal seal KW - Safety KW - Interim storage KW - Spent nuclear fuel KW - Fuel rod PY - 2020 AN - OPUS4-51615 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -