TY - JOUR A1 - Nagel, Thomas A1 - Rühaak, Wolfram A1 - Amann, Florian A1 - Bracke, Guido A1 - Buske, Stefan A1 - Kowalski, Julia A1 - Reiche, Sönke A1 - Schäfer, Thorsten A1 - Scheytt, Traugott A1 - Stumpf, Thorsten A1 - Völzke, Holger A1 - Wellmann, Florian A1 - Kolditz, Olaf T1 - Deep geological disposal - Editorial to the topical collection N2 - The subsurface geological environment, historically a key source of fossil and mineral resources, has seen a significant broadening of its potential applications in recent years, with increasing emphasis on its use for energy production and storage. A critical factor in utilizing subsurface space is ensuring the sustainability of management practices, with particular attention to the potential environmental impacts that may result. The current Topical Collection on Deep Geological Disposal places greater emphasis on the geotechnical aspects of geological disposal, with a particular focus on the safe isolation of hazardous materials, including radioactive waste. The Topical Collection on Deep Geological Disposal covers both experimental (laboratory and in-situ) and theoretical studies of various geotechnical applications, such as geological disposal of radioactive or other materials, e.g. coal-based solid waste, carbon dioxide sequestration in fractured reservoirs, and brine solutions, but also aspects of uranium mining. The articles in the Topical Collections are arranged under the following headings: – Fundamental studies – Experimental studies – Numerical studies KW - Disposal KW - Radioactive Waste KW - Geology PY - 2025 UR - https://nbn-resolving.org/urn:nbn:de:kobv:b43-624955 DO - https://doi.org/10.1007/s12665-024-12075-2 SN - 1866-6299 VL - 84 IS - 3 SP - 1 EP - 6 PB - Springer Nature AN - OPUS4-62495 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Weber, Mike A1 - Völzke, Holger A1 - Nieslony, Gregor T1 - Consequences of an imperfectly mounted reinforcement cage in a generical cylindrical concrete container during mechanical specimen tests N2 - By highest court decision in 2007 the issued license for the Konrad repository (a former iron ore mine) for low and intermediate level radioactive waste was finally confirmed. Since then, the site is improved, prepared and equipped for the currently planned start of waste package emplacement by 2029. The Bundesanstalt fuer Materialforschung und -pruefung (BAM, Federal Institute for Materials Research and Testing) is regularly contracted by the Bundesgesellschaft für Endlagerung (BGE, Federal Company for Radioactive Waste Disposal) as the responsible authority for waste product control, waste container design testing, and waste package acceptance. In this context BAM is mainly responsible for design testing of various container types including the evaluation quality assurance measures for container manufacturing. In the written Konrad disposal requirements all acceptance criteria for potential final disposal containers are defined. In addition to general requirements concerning container design, materials, dimensions and others, specific mechanical load scenarios the casks have to withstand are derived from an analysis of the on-site handling and emplacement procedures. Drop tests from different heights under consideration of the most damaging drop orientation and a stacking test are two examples for safety demonstrations that have to be performed during the container design testing procedure to qualify the respective container type. The containers, whether cubic or cylindrical containers, can be made from different materials like ductile cast iron, reinforced concrete or as welded construction from steel plates and profiles. In case of concrete containers the reinforcement has the function to absorb tensile forces the concrete is not able to withstand by its own. Because of manufacturing imperfections of cylindrical concrete waste containers manufactured already decades ago, the reinforcement cages are not always exactly, axisymmetrically positioned when they were poured. This inspired BAM to perform various ABAQUS finite-element (FE) simulations by using the example of a simplified cylindrical container design with generic dimensions and pure elastic material properties. As outcome the stress conditions in the container during the drop test impact under different drop positions and during the stacking test were investigated and are explained and illustrated in this contribution. Different reinforcement cage positions were calculated and compared. On the basis of the calculated tensile and compressive stress distributions suggestions are derived on how a cylindrical concrete container with an imperfectly placed reinforcement cage has to be oriented for a drop or stacking test to ensure the most damaging test scenario. T2 - ASME 2024 Pressure Vessels & Piping Conference CY - Bellevue, Washington, USA DA - 28.07.2024 KW - Container design testing procedure KW - Reinforced concrete containers KW - Drop test KW - Stacking test KW - Imperfectly mounted reinforcement cage KW - Finite-element-analysis PY - 2024 SN - 978-0-7918-8851-3 DO - https://doi.org/10.1115/PVP2024-123797 VL - 5 SP - 1 EP - 8 PB - ASME CY - New York City, USA AN - OPUS4-62558 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Collaboration on Aging Management for Extended Storage of Used Fuel T2 - 2015 International High-Level Radioactive Waste Management Conference (IHLRWM) CY - Charleston, SC, USA DA - 2015-04-12 PY - 2015 AN - OPUS4-33164 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Liu, Y. T1 - Collaboration on aging management for extended storage of used fuel N2 - A Memorandum of Understanding (MOU) between the Federal Institute for Materials Research and Testing (BAM) and Argonne National Laboratory (Argonne) was signed in the fall of 2014. Its objectives are to promote cooperation among scientists and specialists at BAM and Argonne and establish a framework for collaboration in the field of advanced technologies associated with the back end of the nuclear fuel cycle. Collaborative activities involving the BAM and Argonne may be implemented through the promotion of joint research activities and scientific workshops and conferences; the exchange of technical information; and visits by scientists, specialists, and graduate, postgraduate, and Ph.D. students. The first Argonne/BAM workshop was held at Argonne in October 2014 to discuss aging management issues related to the long-term dry storage of spent fuel. Major topics for potential collaboration on the extended storage of spent nuclear fuel and its subsequent transportation were identified. T2 - IHLRWM 2015 - 15th International high-level radioactive waste management conference CY - Charleston, SC, USA DA - 12.04.2015 KW - Aging management KW - Fuel KW - Extended storage KW - Nuclear PY - 2015 SN - 978-0-89448-719-4 SP - 814 EP - 817 AN - OPUS4-33115 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Scheidemann, Robert A1 - Kasparek, Eva Maria A1 - Qiao, Linan A1 - Müller, Karsten A1 - Droste, Bernhard A1 - Völzke, Holger T1 - Dynamic penetration tests on shock absorbing damping concrete N2 - Mechanical loading conditions of transport and storage casks for radioactive materials in accidental scenarios are highly affected by the behavior of both: the impact limiters and the footing materials. To minimize potential damages during the handling of casks, a so called damping concrete is frequently used for the footings in interim nuclear facilities. It obtains its shock absorbing properties through admixing of polymer cells. For a comprehensive mechanical evaluation of casks, advanced material models are also needed for damping concrete. In order to characterize the mechanical properties and to develop numerical material models, penetration tests were carried out at different test facilities of BAM. The tests contain dynamic penetration tests on mortared specimens with a size of 2,400 x 2,400 x 500 mm³. For these model-sized penetration tests indenters with different geometries and diameters were used. Subsequently a cylindrical cast-iron indenter with a diameter of 1.100 mm was dropped of 5 m height on a realistic damping concrete footing. T2 - WM2014 Conference CY - Phoenix, Arizona, USA DA - 02.03.2014 KW - Drop test KW - Dynamic KW - Penetration KW - Damping concrete PY - 2014 SN - 978-0-9836186-3-8 SP - Paper 14166, 1 EP - 9 AN - OPUS4-31948 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Dittrich, Matthias A1 - Kasparek, Eva Maria A1 - Völzke, Holger T1 - Präzisierung der Prüfanforderungen an Stahlblechcontainer für das Endlager Konrad N2 - Abfallgebinde, die im Endlager Konrad eingelagert werden sollen, müssen die Anforderungen und Kriterien erfüllen, die in den Endlagerungsbedingungen (SE-IB-29/08-Rev-1 [1]) und in der Produktkontrolle (SE-IB-30/08-Rev-1) festgelegt sind. Die Qualifizierung der Abfallbehälter erfolgt auf dieser Grundlage in Form von Bauartprüfungen, die von der Bundesanstalt für Materialforschung und -prüfung (BAM) im Auftrag des Bundesamtes für Strahlenschutz (BfS) durchgeführt werden. Darüber hinaus sind die im Hinblick auf Behälterbauartprüfungen relevanten Nebenbestimmungen aus dem Planfeststellungsbeschluss für das Endlager Konrad zu berücksichtigen. Zur besseren Anwendbarkeit werden diese Nebenbestimmungen in die Endlagerungsbedingungen und die Produktkontrolle eingearbeitet. Begleitend ist als Hilfestellung für die Abfallablieferer und Behälterhersteller ein Leitfaden geplant, der praktikable Nachweisstrategien aufzeigt und, soweit erforderlich, Hintergrundinformationen zu den Spezifikationen der Regelwerke liefert. Die BAM ist vom BfS beauftragt, hierfür Vorschläge zu entwickeln und Empfehlungen abzugeben. T2 - KONTEC 2015 - 12. Internationales Symposium "Konditionierung radioaktiver Betriebs- und Stilllegungsabfälle" CY - Dresden, Germany DA - 25.03.2015 PY - 2015 SP - Paper 090, 786 EP - 794 AN - OPUS4-33020 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - The German aging management approach for dry spent fuel storage in dual purpose casks N2 - Since the decision by the German government to face out nuclear electricity generation the total amount of spent nuclear fuel and high level wastes from reprocessing is limited and well determined. In addition the siting and licensing procedure to establish a final repository has been ruled by a new law in the mid of 2013 and further delays are very likely until a deep geological repository may start its operation. In the meantime dry interim storage in dual purpose casks being permanently certified for interim storage as well as transportation is the established technical solution. Several on-site as well former centralized facilities are operated successfully for many years but storage licenses are generally limited to 40 years and future lifetime extensions are predictable. Permanent aging management for storage facilities and casks is necessary to demonstrate compliance with safety requirements and furthermore to gain relevant data and information about the technical conditions of the facilities and their components for future lifetime extensions. For that reason procedures and measures are currently improved and the approach is explained in this paper. In addition, the current status and latest experiences concerning periodic safety inspections and aging management measures are discussed. T2 - PSAM 12 - Probabilistic safety assessment and management CY - Honolulu, Hawaii, USA DA - 22.06.2014 KW - Interim storage KW - Dual purpose casks KW - Spent nuclear fuel KW - Aging management PY - 2014 SP - T06 - Doc.183, 1-7 AN - OPUS4-32250 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Völzke, Holger A1 - Wolff, Dietmar A1 - Probst, Ulrich A1 - Nagelschmidt, Sven A1 - Schulz, Sebastian T1 - Long term performance of metal seals for transport and storage casks N2 - Dual purpose casks for the transportation and storage of spent nuclear fuel and other radioactive materials require very high leak tightness of lid closure systems under accident conditions as well as in the long term to prevent activity release. For that purpose metal seals of specific types with an inner helical spring and outer metal liners are widely used and have shown their excellent performance if certain quality assurance requirements for fabrication and assembling are satisfied. Well defined surface roughness, clean and dry inert conditions are therefore essential. No seal failure in a loaded cask happened under these conditions until today. Nevertheless, the considered and licensed operation period is limited and all safety assessments have been performed and approved for this period of time which is 40 years in Germany so far. However, in the meantime longer storage periods might be necessary for the future and therefore additional material data will be required. BAM is involved in the qualification and evaluation procedures of those seals from the early beginning. Because long term tests are always time consuming BAM has early decided to perform additional tests with specific test seal configurations to gain a better understanding of the long term behaviour with regard to seal pressure force, leakage rate and useable resilience which is safety relevant mainly in case of accidental mechanical loads inside a storage facility or during a subsequent transport. Main test parameters are the material of the outer seal jacket (silver or aluminium) and the temperature. This paper presents the BAM test program including an innovative test mock-up and most recent test results. Based on these data extrapolation models to extended time periods are discussed, and also future plans to continue tests and to investigate seal behaviour for additional test parameters are explained. KW - Metal Seal KW - Spent Fuel KW - Storage KW - Ageing KW - Cask KW - Leak tightness PY - 2014 DO - https://doi.org/10.1179/1746510914Y.0000000057 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 25 IS - 1 SP - 8 EP - 15 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-32327 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Update of the ESCP International Data Gap Analyses T2 - 30th INMM Spent Fuel Management Seminar CY - Arlington, VA, USA DA - 2015-01-12 PY - 2015 AN - OPUS4-32445 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Spent Fuel Management in Germany T2 - 30th INMM Spent Fuel Management Seminar CY - Arlington, VA, USA DA - 2015-01-12 PY - 2015 AN - OPUS4-32446 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Overwiev about BAM T2 - Argonne National Laboratories (ANL) - BAM Workshop CY - Argonne, IL, USA DA - 2014-10-15 PY - 2014 AN - OPUS4-32309 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Update on Extended Storage Activities ans International Data Gap Report - Germany T2 - Extended Storage Collaboration (ESCP) International Subcommitttee Meeting #11 CY - Tokyo, Japan DA - 2014-11-10 PY - 2014 AN - OPUS4-32310 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Extended Interim Storage Issues and Long-Term Investigations at BAM T2 - Sandia National Laboratories (SNL) - BAM Workshop CY - Albuquerque, NM, USA DA - 2014-10-07 PY - 2014 AN - OPUS4-32311 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - EPRI ESCP International Subcommitee Report T2 - Extended Storage Collaboration Program (ESCP) International Subcommittee Meeting #11 CY - Tokyo, Japan DA - 2014-11-10 PY - 2014 AN - OPUS4-32312 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Update on Extended Storage Activities and International Data Gap Report - Germany T2 - Extended Storage Collaboration Program (ESCP) Main Meeting and International Subcommittee Meeting #12 CY - Charlotte, NC, USA DA - 2014-12-02 PY - 2014 AN - OPUS4-32313 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - ESCP International Subcommittee Report T2 - Extended Storage Collaboration Program (ESCP) Main Meeting and International Subcommittee Meeting #12 CY - Charlotte, NC, USA DA - 2014-12-02 PY - 2014 AN - OPUS4-32314 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Long-Term Dry Spent Nuclear Fuel Storage in Germany T2 - Argonne National Laboratories (ANL) - BAM Workshop CY - Argonne, IL, USA DA - 2014-10-15 PY - 2014 AN - OPUS4-32315 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Weber, Mike A1 - Zencker, Uwe A1 - Wolff, Dietmar A1 - Völzke, Holger A1 - Herbrich, Uwe A1 - Nagelschmidt, Sven T1 - Numerical analysis of cask accident scenarios in storage facilities N2 - Existing spent nuclear fuel (SF) and high active waste (HAW) management policies and practices worldwide are the result of past presumptions that sufficient reprocessing and/or disposal capacity would be available in the near term. Consequently, in the past many countries have developed specific solutions for different periods of time due to their individual national nuclear policies. In Germany the concept of dry interim storage in dual purpose metal casks before disposal is being pursued for SF and HAW management and transport and storage licenses have been issued accordingly. The current operation licenses for existing storage facilities have been granted for a storage period of up to 40 years. This concept has demonstrated its suitability for over 20 years so far. Relevant safety requirements have been assessed for the short-term as well as for the long-term for site-specific operational and accidental storage conditions. But in the meantime significant delays in the national repository siting procedure occurred which will make extended storage periods necessary in the future. T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 18.08.2013 KW - Numerical analysis KW - Interim storage KW - Cask accident scenario PY - 2013 SP - Session H, Paper 202, 1 EP - 9 PB - Omnipress AN - OPUS4-30227 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Scheidemann, Robert A1 - Kasparek, Eva Maria A1 - Müller, Karsten A1 - Droste, Bernhard A1 - Völzke, Holger T1 - Model-sized and full-scale dynamic penetration tests on damping concrete N2 - Mechanical loading conditions of transport and storage casks for radioactive materials in accidental scenarios are highly affected by the behavior of both: the impact limiters and the footing materials. To minimize potential damages during the handling of casks, a so called damping concrete is frequently used for the footings in interim nuclear facilities. It obtains its shock absorbing properties through admixing of polymer cells. For a comprehensive mechanical evaluation of casks, advanced material models are also needed for damping concrete. In order to characterize the mechanical properties and to develop numerical material models, penetration tests were carried out at different test facilities of BAM. The tests contain static and dynamic penetration tests on cubic specimen with an edge length of 100 mm as well as mortared specimen with a size of 240 x 240 x 50 cm³. Indenters with different geometries and diameters were used for these model-sized penetration tests. Subsequently a full-scale cylindrical cast-iron indenter with a diameter of 110 cm was dropped of 5 m height on a realistic damping concrete footing. T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 18.08.2013 KW - Drop test KW - Dynamic KW - Penetration KW - Damping concrete PY - 2013 SP - 1 EP - 10 PB - Omnipress AN - OPUS4-30233 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 - TY - CONF A1 - Völzke, Holger T1 - Entsorgung der Brennelemente in Deutschland T2 - VdTÜV Forum Kerntechnik CY - Berlin, Germany DA - 2014-03-17 PY - 2014 AN - OPUS4-30680 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Spent Fuel Management in Germany - Technical Perspectives and Challenges T2 - 26th Annual Regulatory Information Conference RIC2014 CY - North Bethesda, MD, USA DA - 2014-03-11 PY - 2014 AN - OPUS4-30681 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Present Status of Spent Fuel Management in Germany T2 - INMM Spent Fuel Management Seminar XXIX CY - Arlington, VA, USA DA - 2014-01-13 PY - 2014 AN - OPUS4-30712 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Qiao, Linan A1 - Zencker, Uwe A1 - Kasparek, Eva Maria A1 - Völzke, Holger ED - Topping, B.H.V. ED - Iványi, P. T1 - Simulation of damping concrete under severe impact loads using a crushable foam model with damage mechanisms N2 - The deformation and damage behaviour of damping concrete under impact loading conditions is investigated experimentally and numerically. The material model is based on the assumption of crushable foam with volumetric or isotropic hardening combined with ductile and shear damage criteria. Model parameters are determined in static and dynamic compression tests of confined cubic specimens. The derived material model is validated by numerical simulation of penetration tests. The static and dynamic penetration of indenters into uniform as well as assembled bricks made of damping concrete is discussed. Finally, the successful calculation of a large-scale drop test with a heavy cask-like test object onto a realistic damping concrete foundation is demonstrated. T2 - 12th International conference on computational structures technology CY - Naples, Italy DA - 02.09.2014 KW - Damping concrete KW - Impact load KW - Crushable foam material model KW - Damage PY - 2014 SN - 978-1-905088-61-4 DO - https://doi.org/10.4203/ccp.106.233 SN - 1759-3433 SP - Paper 233, 1 EP - 16 PB - Civil Comp Press AN - OPUS4-31480 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Weber, Mike A1 - Zencker, Uwe A1 - Wolff, Dietmar A1 - Völzke, Holger A1 - Herbrich, Uwe A1 - Nagelschmidt, Sven T1 - Numerical analysis of cask accident scenarios in storage facilities N2 - Mechanical drop test scenarios for Type B (U) packages according to the IAEA regulations have to be carried out onto the so-called “unyielding target” (usually with cask impact limiters) and onto the puncture bar respectively. They are predefined and do not require any further investigation of scenarios that really could happen on transportation routes. Cask accident scenarios in the framework of approval procedures for interim storage sites are derived from a detailed analysis of the handling procedures necessary from arrival of cask at the site to its storing position. In that case, casks are usually handled without impact limiters. Dependent on possible drop heights, drop positions and floor properties, conservative cask accident scenarios are derived for further safety proofs. According to the mechanical assessment concept of the considered approval procedure numerical calculations have to be provided by the applicant to demonstrate mechanical cask safety. Stresses and strains in the cask body as well as in the lid System have to be identified and assessed. Using the example of a 3-mvertical-drop of a transport and storage cask for spent fuel elements onto the floor construction made of damping concrete covered by screed, BAM developed a finite element model. The finite element code ABAQUS/Explicit™ was used. Results of experimental investigations are not available. Therefore parameter studies are necessary to identify the sensitivity of the finite element model to significant Parameters and to verify the finite element models according to the requirements of the Guidelines for the Numerical Safety Analyses for the Approval of Transport and Storage Casks for Radioactive Materials (BAM GGR-008). The paper describes the modeling of the material behavior and attachment of bottom side cask components. Questions concerning the modeling of a crack length limiting reinforcement in the screed layer are discussed. The influence of the mesh density of the screed layer and its strength is considered as well. Finally, the developed finite element model can be used for a numerical safety assessment. It can help to understand the complex mechanisms of the interaction between the cask components and floor construction. T2 - WM2014 Conference CY - Phoenix, Arizona, USA DA - 02.03.2014 KW - Numerical analysis KW - Interim storage KW - Cask accident scenario PY - 2014 SN - 978-0-9836186-3-8 SP - Paper 14541, 1 EP - 12 AN - OPUS4-31516 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wolff, Dietmar A1 - Völzke, Holger A1 - Wille, Frank A1 - Droste, Bernhard T1 - Extended storage after long-term storage N2 - Existing spent nuclear fuel (SF) and high active waste (HAW) management policies and practices worldwide are the result of past presumptions that sufficient reprocessing and/or disposal capacity would be available in the near term. Consequently, in the past many countries have developed specific solutions for different periods of time due to their individual national nuclear policies. In Germany the concept of dry interim storage in dual purpose metal casks before disposal is being pursued for SF and HAW management and transport and storage licenses have been issued accordingly. The current operation licenses for existing storage facilities have been granted for a storage period of up to 40 years. This concept has demonstrated its suitability for over 20 years so far. Relevant safety requirements haven been assessed for the short-term as well as for the long-term for site-specific operational and accidental storage conditions. But in the meantime significant delays in the national repository siting procedure occured which will make extended storage periods necessary in the future. This paper describes the current situation in Germany with regard to dry cask storage and focuses on current perspectives considering regulatory, technical, and scientific aspects for storage license renewal. Since there is one case of a storage license limitation to only 20 years due to administrative reasons, first experience is currently gathered in case of an expiring storage license. Subsequent license options have been pursued intensively including the extension of the initial storage license as well as shipping all casks to another storage facility considering an extended storage period at that storage facility as well. All safety relevant aspects have to be reviewed on basis of the current state-of-the-art which might be different from the initial safety demonstrations. That includes new safety assessment standards as well as improved knowledge base. Major issues are e.g. improved accident scenario analyses, assessment methods, and consideration of aging effects from previous operation periods. Inspection programs with respect, e.g. to bolts and seals to verify leak-tightness and lid screw pre-stress have been initiated to demonstrate proper cask conditions for extended storage as well as transportation to another storage facility. T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 18.08.2013 KW - Extended storage KW - Long-term storage KW - Dual purpose cask PY - 2013 SP - Paper 184, 1 EP - 12 PB - Omnipress AN - OPUS4-30242 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Wolff, Dietmar T1 - Update on the German approach of storing spent nuclear fuel in dual purpose casks until final disposal N2 - The German approach of storing spent nuclear fuel in dual purpose casks until final disposal is based on individually licensed storage sites concerning specific nuclear inventories and dual purpose cask types. The currently approved license period is maximum 40 years. With nuclear policy changes including the phase-out decision of 2011 and a new approach for the HLW repository siting process set up 2013 by law also the spent fuel and HLW management strategy has to be adapted. This includes the timely development of disposal container concepts as part of the overall repository siting process and the need for longer interim storage periods until final disposal. Other aspects affect new regulations about the financing of the nuclear waste management by the industry and the public sector, the restructuring of responsible authorities in 2016/2017 and the adaption of R&D funding programs addressing also pre-disposal (or extended interim storage) issues. BAM as a Federal Research Institute has been responsible for or in charge of container safety Evaluation for transport and storage casks for radioactive waste for several decades and started addressing potential Extended interim storage issues already several years ago. This included participation in international projects at the IAEA or in the U.S. Extended Storage Collaboration Program (ESCP) as well as long term laboratory tests with metal seals, elastomeric seals and polymers for neutron shielding purposes. Test results of BAM are published regularly and gained data provide valuable information about thermo-mechanical and radiological degradation effects as well as the long term Performance of respective cask components. Regarding the reliable extrapolation and prediction of the long term Performance of cask materials and components for time periods of up to 80 or even 100 years the continuation and extension of laboratory tests and the development of analytical and numerical simulation models and tools is essential and under way. T2 - 16th International High -Level Radioactive Waste Management Conference (IHLRWM 2017) CY - Charlotte, NC, USA DA - 09.04.2017 KW - Spent fuel KW - Storage KW - Cask KW - Safety KW - Disposal PY - 2017 SP - 189 EP - 194 AN - OPUS4-40411 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Orellana Pérez, Teresa A1 - Völzke, Holger A1 - Wolff, Dietmar A1 - Zencker, Uwe T1 - Cladding considerations at BAM regarding extended storage spent fuel N2 - With the clear expectation of the need for extending spent fuel storage in Germany beyond the initial license period of maximum 40 years additional material data and knowledge about the long term performance and integrity of casks and internals like fuel rods will be required to meet major safety goals and regulatory requirements. Based on a broad knowledge base about fuel cladding behavior, degradation mechanisms and related potential failure mechanisms, e. g. induced by reoriented Hydride precipitation, as illustrated in this paper, a specific gap analyses for the German situation regarding fuel conditions and cladding materials should identify the specific knowledge gaps to be addressed and closed in the near future. This is of specific interest as all spent fuel assemblies are going to be transferred to dry cask storage with the next decade and as a consequence of the German nuclear phase-out decision. Within several decades, BAM as a Federal materials research institute gathered a broad range of expertise in the safety evaluation of materials, components and casks under operational and accidental thermal and mechanical conditions. This paper elucidates selected Basic considerations regarding technical and scientific knowledge about the long term aging performance and potential failure mechanisms of fuel cladding materials. Under consideration of the national R&D funding policy which has been adapted to the extended interim storage or pre-disposal needs and the competences of BAM, its future R&D strategy is explained and some R&D objectives have already been identified. BAM will continue and expand ist engagement in the area of investigating fuel cladding material behavior in the long term and developing validated simulation and analyses tools in collaboration with national and international partners. R&D outcomes shall improve the knowledge-base to close identified knowledge gaps in the area of demonstrating fuel cladding integrity and to provide crucial information with regard to future safety assessments for the extended interim spent fuel storage. T2 - 16th International High -Level Radioactive Waste Management Conference (IHLRWM 2017) CY - Charlotte, NC, USA DA - 09.04.2017 KW - Spent fuel KW - Storage KW - Fuel cladding PY - 2017 SP - 718 EP - 725 AN - OPUS4-40412 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Dittrich, Matthias A1 - Kasparek, Eva-Maria A1 - Völzke, Holger T1 - Legacy waste containers for low and intermediate level radioactive waste in Germany - Actual situation and challenges –17070 N2 - Low and intermediate level radio active waste has been produced in Germany for several decades. While a part of the waste had been deposited in the Morleben repository and the Asse mine which have been operated for just a limited period of time, the major amount is conditioned and packaged in temporarily stored waste containers. Those containers are designated for final disposal in the KONRAD repository being currently under construction and expected to start operation in 2022. As a consequence, an assessment of the waste container documentation and safety is strongly needed to receive an approval for the KONRAD repository. This requalification is challenging because those old containers have to meet the same safety requirements as new containers. T2 - WasteManagement Symposia 2017 CY - Phoenix, USA DA - 05.03.2017 KW - Radioactive waste container KW - Konrad KW - Repository PY - 2017 UR - https://www.xcdsystem.com/wmsym/2017/028.html#17070 SP - Paper 17070, 1 EP - 14 AN - OPUS4-40326 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Wolff, Dietmar T1 - Spent Nuclear Fuel and HLW Storage towards Disposal - Challenges and Perspectives of an Integrated Approach - N2 - This paper describes and discusses the major challenges of spent fuel management in Germany after the phase-out of nuclear electricity generation was decided in 2011 and a new repository siting procedure was implemented in 2013. Consequences from those decisions which were legally founded by amendments of the German Atomic Energy Act (AtG) result in the need to transfer all remaining spent fuel from limited reactor operation (last reactor shutdown until the end of 2022) into casks for subsequent dry interim storage on-site. Storage licenses are generally issued site-specific considering specific dual purpose casks (DPC) and their inventories and they are generally limited to 40 years so far. But the need for extending the interim storage period in the future has become obvious. Even though, this may not be an issue to be solved already today questions about additional safety demonstrations will arise as soon as licenses need to be extended. Certainly, these questions will ask for reliable data about the long term performance and safety of structures, systems, and components, e. g. the long term performance of cask components and materials like bolted closure systems including metal seals, or fuel rod behaviour concerning cladding materials under stress and temperature conditions. In case of dual purpose casks for storage and transportation this includes aspects on how to demonstrate transportability during or after several decades of interim storage. Long term investigations often require plenty of time and therefore need to be initiated timely. T2 - PATRAM 2016 The 18th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Kobe, Japan DA - 18.09.2016 KW - Storage KW - Spent Fuel KW - Disposal PY - 2016 UR - http://www.patram2016.org/ SN - 978-4-88898-270-2 SP - Paper 5006 AN - OPUS4-40300 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Wolff, Dietmar T1 - Spent Nuclear Fuel and HLW Storage towards Disposal - Challenges and Perspectives of an Integrated Approach - N2 - This paper describes and discusses the major challenges of spent fuel management in Germany after the phase-out of nuclear electricity generation was decided in 2011 and a new repository siting procedure was implemented in 2013. Consequences from those decisions which were legally founded by amendments of the German Atomic Energy Act (AtG) result in the need to transfer all remaining spent fuel from limited reactor operation (last reactor shutdown until the end of 2022) into casks for subsequent dry interim storage on-site. Storage licenses are generally issued site-specific considering specific dual purpose casks (DPC) and their inventories and they are generally limited to 40 years so far. But the need for extending the interim storage period in the future has become obvious. Even though, this may not be an issue to be solved already today questions about additional safety demonstrations will arise as soon as licenses need to be extended. Certainly, these questions will ask for reliable data about the long term performance and safety of structures, systems, and components, e. g. the long term performance of cask components and materials like bolted closure systems including metal seals, or fuel rod behaviour concerning cladding materials under stress and temperature conditions. In case of dual purpose casks for storage and transportation this includes aspects on how to demonstrate transportability during or after several decades of interim storage. Long term investigations often require plenty of time and therefore need to be initiated timely. T2 - PATRAM 2016 The 18th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Kobe, Japan DA - 18.09.2016 KW - Storage KW - Spent Fuel KW - Disposal PY - 2016 AN - OPUS4-40301 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Wolff, Dietmar T1 - Update on the German approach of storing spent nuclear fuel in dual purpose casks until final disposal N2 - The safe and secure long term storage of spent nuclear fuel until its final disposal in a deep geological repository is a corner stone of the German nuclear waste management strategy. So far interim storage licenses are limited to 40 years concerning the initial concept of having a repository available until 2035. But in the meantime the exploration of the designated Gorleben salt dome was finally stopped and a reset of the complete site selection process was concluded by the German Federal parliament and subsequently fixed by law. A 33-member “Commission on the storage of highly radioactive materials” was established in 2014, to elaborate a consent based siting process and to develop criteria for the safe disposal of heat generating waste. The disposal commission agreed and published its final report in 2016. As a major consequence, the necessary timeframe for establishing the final repository is going to be exceeded significantly and with that, an extension of the current dry interim storage in dual purpose casks becomes necessary. This paper explains the major actions to be taken in Germany to address all relevant issues for a future extension of storage licenses beyond the initial timeframe of 40 years. T2 - ANS Conference International High-Level Radioactive Waste Management (IHLRWM) 2017 CY - Charlotte, NC, USA DA - 09.04.2017 KW - Spent Fuel KW - Storage KW - Disposal PY - 2017 AN - OPUS4-40303 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Preserving competence in nuclear technology - BAM's contributions N2 - With regard to the nuclear phase-out in Germany preserving competence in nuclear technology is a major challenge. This presentation explains how BAM addresses this issue within its specific tasks, expertise and long term experience on nuclear waste package design testing and safety evaluation. T2 - 48th Annual Meeting on Nuclear Technology (AMNT 2017) CY - Berlin, Germany DA - 16.05.2017 KW - Nuclear Technology KW - Safety KW - Waste Packages KW - Design Testing PY - 2017 AN - OPUS4-40306 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Perspectives on extending interim storage of spent nuclear fuel (beyond the initial license period) N2 - The presentation adddresses the consequences and challenges of the German nuclear phase-out in conjunction with the restart of siting process for a high-level radioactive waste repository. Concerning spent fuel this will lead to extended interim storage periods for the dry storage casks beyond the initial licensing period of 40 years. For extending storage periods additional safety assessments and data about the long term performance of materials, components and casks will be needed and BAM has already been lauching specific R&D projects addressing identified data gaps. T2 - 8th Annual Nuclear Decommissioning Conference Europe CY - Manchester, UK DA - 24.05.2017 KW - Spent Fuel KW - Storage KW - Disposal PY - 2017 AN - OPUS4-40358 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Scheidemann, Robert A1 - Weber, Mike A1 - Völzke, Holger A1 - Kasparek, Eva Maria ED - Gomes, J.F.Silva ED - Meguid, S.A. T1 - Temperature dependendency of dynamically loaded polyurethane foam N2 - Polyurethane foam used as impact limiter material undergoes high plastic deformations, whereat the resulting stress-strain relations strongly depend on loading speed and temperature. This paper discusses the efforts necessary to develop a reliable numerical foam simulation model focussing on generation and implementation of temperature- dependent yield curves T2 - 6th International Conference on Mechanics and Materials in Design CY - Ponta Delgada, Azores, Portugal DA - 26.07.2015 KW - Impact limiter KW - Polyurethane foam KW - Finite element model KW - Strain rate KW - Temperature dependency PY - 2015 SN - 978-989-98832-3-9 SP - 1043 EP - 1046 PB - INEGI-FEUP AN - OPUS4-38889 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Kasparek, Eva A1 - Völzke, Holger T1 - Non-Heat Generating Legacy Waste - New Strategies for Older Vessels N2 - The German repository “Konrad” is approved for the final storage of approximately 300.000 m³ of non-heat generating radioactive waste considering also the expected residues from operation and decommissioning of current power plants. According to the latest survey as constituted end of 2014, a large proportion of this volume already exists, of which 100.288 m³ are fully loaded packages. As prerequisite for their “Konrad” acceptance, the vessels have to be designed against operational and accidental conditions of the site and be manufactured according to adequate quality assurance programs. The respective safety assessment performed by BAM on behalf of the Federal Office for Radiation Protection is a major challenge especially for those casks that had been produced and loaded already some decades ago. Typically, they were manufactured in big numbers over a longer period of time involving a lot of constructional and management changes. This fact in combination with the previously rather low documentation standards often causes relevant uncertainties about the specific physical and geometrical characteristics of the cask materials and components as well as about details concerning their whole assemblage. This paper highlights current assessment strategies for such older vessels including cubic steel sheet containers as well as cylindrical thick-walled casks. As compliance with each “Konrad”-requirement can hardly be shown independently, only integrated approaches promises success: First, a broader concept of data collection has to be implemented that allows closing documentation gaps by linking dispersed and diverse data, e.g. delivery slips and handwritten fabrication records, by including plausibility considerations as well as random inspection programs. Thereby, the relevant properties of all applied casks have to be identified and their potential range should be quantified as accurately as possible. This knowledge is necessary to define one or more representative configurations of the cask as the base for design testing. The actual investigation program must enable to track the influence of deviations and determine safety margins especially in the likely case that not the most conservative setting of all cask features can be tested. The paper evaluates the respective ongoing efforts of industrial applicants and summarizes BAM experiences and associated research projects. T2 - 18th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Kobe, Japan DA - 18.09.2016 KW - Requalification KW - Low and medium level radioactive waste KW - Final disposal container KW - Legacy waste KW - Konrad repository PY - 2016 SP - Paper 1014, 1 EP - 9 AN - OPUS4-38892 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Issues on Aging of Spent Fuel Storage Systems N2 - The Bundesanstalt für Materialforschung und –prüfung (BAM) and Sandia National Laboratories (SNL) entered into a Memorandum of Understanding (MOU) in September 2012 to foster technical collaborations in the areas associated with the backend of the commercial nuclear fuel cycle. Specifically, the focus is on packaging, transportation, and storage of commercial spent nuclear fuel. The institutes meet about twice each year, alternating between institutes. This provides the opportunity for staff members from the host organization more exposure to technical issues that are of concern internationally and to collaborate with technical experts working on similar problems. Since 2012, the focus of the meetings has been on technical issues associated with extended dry storage and subsequent transportation of commercial spent fuel. Topics range from hydride effects on cladding integrity, spent fuel response during Normal Conditions of Transport (NCT), finite element analyses of fuel and cask response to accident conditions, bolt and seal behavior over extended periods of time, and corrosion associated with bolts, metallic seals, and stainless steel canisters. This MOU has provided an effective leverage for technical collaboration. For example, SNL is funding (through DOE), Savannah River National Laboratories (SRNL) to look at bolt and seal degradation issues. SRNL has an MOU with BAM to collaborate on bolt and seal degradation during extended storage. Likewise, Sandia and BAM are collaborating with the EC Joint Research Center on an International Nuclear Energy Research Initiative (I-NERI) to investigate spent fuel behavior when subjected to mechanical loadings. This important work will provide insight into failure mechanisms, as well as spent fuel release fractions, given a breach of the cladding wall. This presentation provides an overview of high ranked technical issues associated with extended storage and subsequent transportation, as well as the work underway at BAM and SNL that are addressing these issues. T2 - 7th US/German Workshop on Salt Repository Research, Design, and Operation CY - Washington, DC, USA DA - 07.09.2016 KW - Spent Fuel KW - Ageing KW - Storage PY - 2016 AN - OPUS4-37318 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Long Term Storage of Spent Nuclear Fuel and HLW in Dual Purpose Casks Towards Disposal - Challenges and Perspectives T2 - International Conference on Management of Spent Fuel from Nuclear Power Reactors - An Integrated Approach to the Back-End of the Fuel Cycle CY - Vienna, Austria DA - 2015-06-15 PY - 2015 AN - OPUS4-33427 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Qiao, Linan A1 - Völzke, Holger T1 - Dynamic finite element analysis of cask handling accidents at storage sites N2 - The safety assessment of casks for radioactive material at interim storage facilities or in final repositories includes the investigation of possible handling accidents if clearly defined test conditions are not available from the regulations. Specific handling accidents usually are the drop of a cask onto the transport vehicle or the floor as well as the collision with the wall of the storage building or another cask. For such load cases an experimental demonstration of cask safety would be difficult. Therefore, numerical analyses of the entire load scenario are preferred. The lessons learnt from dynamic finite element analyses of accident scenarios with thick-walled cubical containers or cylindrical casks are presented. The dependency of calculation results on initial and boundary conditions, material models, and contact conditions is discussed. Parameter sets used should be verified by numerical simulation of experimentally investigated similar test scenarios. On the other hand, decisions have to be made whether a parameter or property is modeled in a realistic or conservative manner. For example, a very small variation of the initial impact angle of a container can cause significantly different stresses and strains. In sophisticated cases an investigation of simpler limit load scenarios could be advantageous instead of analyzing a very complicated load scenario. T2 - ASME 2015 Pressure vessels & piping conference - PVP2015 CY - Boston, Massachusetts, USA DA - 19.07.2015 KW - Finite element method KW - Simulation KW - Cask handling accident KW - Interim storage PY - 2015 SN - 978-0-7918-5702-1 SP - Paper 45606, 1 EP - 10 AN - OPUS4-34937 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Qiao, Linan A1 - Völzke, Holger T1 - Strategies for numerical modelling of metal gaskets in transport and storage casks N2 - Metal gaskets in the lid system of transport and storage casks for radioactive material have to guarantee leak-tightness and safe enclosure of the radioactive inventory under normal and accident conditions during transport, in case of accidents and for the longterm interim storage. For safety assessments by nurnerical simulation of the thermomechanical behaviour of a lid system with metal gaskets, the finite element method offers three options to use: i) special gasket elements, ii) complex three-dimensional modeHing with solid elements, and iii) a simplified axisymmetric approach. Gasket elements can be adjusted by many parameters, but they give only a global representation of the experimentally observed gasket behaviour. For calculations of the entire cask including the lid system with gaskets, nonetheless this approach is recommended. To investigate the hardly measurable impact behaviour in detail or to extrapolate the long-term behaviour, a local modeHing of all parts of a gasket and their interactions with effects like elastic-plastic deformation, creep, relaxation, and friction is necessary. The three-dimensional model can describe the change of contact area between outer jacket of the gasket and flange dependent on the load conditions, what overcomes an essential limitation of special gasket elements. To simplify the problern of investigating the underlying physical effects, an axisymmetric lid system can be modelled with axisymmetric finite elements. Usually an approximation is only necessary for the helical spring of a metal gasket. This paper explains basic ideas for an adequate finite element simulation of cask lid systems with metal gaskets and their thermo-mechanical behaviour under specific load scenarios. T2 - RAMTRANSPORT 2015 - International conference on the radioactive materials transport and storage CY - Oxford, UK DA - 19.05.2015 KW - Metal gasket KW - Finite element method KW - Simulation PY - 2015 SP - Paper RAM15-27, 1-9 AN - OPUS4-34938 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Nieslony, Gregor A1 - Hagenow, Peter T1 - Approval of Existent Waste Packages and New Package Designs in Preparation for the KONRAD Repository - 8092 T2 - 34th Annual Waste Management Conference & Exhibition (WM2008) CY - Phoenix, Arizona, USA DA - 2008-02-24 KW - Behälter KW - Behälterprüfung KW - Endlager KW - Radioaktive Stoffe KW - Qualitätssicherung KW - Sicherheit PY - 2008 SP - 1 EP - 9 AN - OPUS4-17990 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Advanced investigations to evaluate spent fuel cask safety for extended storage periods T2 - INMM Institute of Nuclear Materials Management: 50th Annual Meeting CY - Tucson, AZ, USA DA - 2009-07-12 PY - 2009 AN - OPUS4-19650 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Sterthaus, Jens A1 - Ballheimer, Viktor A1 - Droste, Bernhard A1 - Koch, Frank A1 - Probst, Ulrich A1 - Völzke, Holger A1 - Wille, Frank T1 - Analysis of bolted flange joints for lids of packages for radioactive materials T2 - ASME 2009 Pressure vessels and piping conference CY - Prague, Czech Republic DA - 2009-07-26 KW - Bolted flange joints KW - FEA KW - Modelling of gaskets KW - Assessment of leak tightness KW - Results from experiments PY - 2009 SP - PVP2009-77284, 1-8 PB - American Society of Mechanical Engineers CY - New York AN - OPUS4-19786 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Völzke, Holger T1 - Prüfungen an Zwischenlagerbehältern zur Belastbarkeit bei Einwirkungen von innen und aussen T2 - Zwischenlager-Workshop CY - Jülich, Deutschland DA - 2001-01-23 PY - 2001 SP - 177 EP - 221 CY - Jülich AN - OPUS4-21569 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Quercetti, Thomas A1 - Wieser, Günter A1 - Völzke, Holger A1 - Droste, Bernhard ED - Droste, B. ED - Kowalewsky, H. T1 - Mechanical impact assessment of cubic waste containers depending on target construction T2 - PATRAM 98 - 12th International conference on the packaging and transportation of radioactive materials CY - Paris, France DA - 1998-05-10 PY - 1998 VL - 3 SP - 1152 EP - 1159 PB - Nuclear Technology Publishing CY - Paris, France AN - OPUS4-21556 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wieser, Günter A1 - Droste, Bernhard A1 - Martens, B.-R. A1 - Probst, Ulrich A1 - Schreiber, D. A1 - Völzke, Holger ED - Droste, B. ED - Kowalewsky, H. T1 - Thermal test of a cubic ductile cast iron container filled with an ion exchanger resin T2 - PATRAM 98 - 12th International conference on the packaging and transportation of radioactive materials CY - Paris, France DA - 1998-05-10 PY - 1998 VL - 1 SP - 429 EP - 435 PB - Nuclear Technology Publishing CY - Paris, France AN - OPUS4-21560 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Völzke, Holger A1 - Wieser, Günter A1 - Zencker, Uwe A1 - Droste, Bernhard T1 - Mechanical and thermal safety analyses and demonstrations for cubic DCI multipurpose containers PY - 1997 SN - 0957-476X VL - 8 IS - 3-4 SP - 247 EP - 252 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21664 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Wieser, Günter A1 - Zencker, Uwe A1 - Droste, Bernhard T1 - Mechanical and thermal safety analyses and demonstrations for cubic DCI - multi-purpose containers T2 - 4th International conference on transportation for the nuclear industry CY - Bournemouth, Dorset, UK DA - 1997-05-13 PY - 1997 IS - Session 2, Paper 5 SP - 1 EP - 13 AN - OPUS4-21665 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Völzke, Holger A1 - Droste, Bernhard T1 - Entwicklung von Beurteilungsmethoden für Transport- und Lagerbehälter mit erhöhten metallischen Reststoffanteilen - Weiterführende Untersuchungen (EBER II) T2 - VI. Stilllegungskolloquium Hannover und 5. Statusbericht "Stilllegung und Rückbau kerntechnischer Anlagen" CY - Hannover, Deutschland DA - 2000-04-13 PY - 2000 SP - 315 EP - 326 AN - OPUS4-21591 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Völzke, Holger A1 - Droste, Bernhard T1 - Entwicklung von Beurteilungsmethoden für Transport- und Lagerbehälter mit erhöhten metallischen Reststoffanteilen (EBER) - FEM-Berechnungen zum Aufprall kubischer Gußcontainer T2 - V. Stilllegungskolloquium Hannover und 4. Statusbericht "Stilllegung und Rückbau kerntechnischer Anlagen" CY - Hannover, Deutschland DA - 1997-06-24 PY - 1997 SP - 264 EP - 275 AN - OPUS4-21659 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Völzke, Holger T1 - EBER - Entwicklung von Beurteilungsmethoden für Transport- und Lagerbehälter mit erhöhten metallischen Reststoffanteilen T2 - IV. Stilllegungskolloquium Hannover und 3. Statusbericht "Stilllegung und Rückbau kerntechnischer Anlagen" CY - Bad Dürkheim, Deutschland DA - 1995-11-08 PY - 1995 SP - 425 EP - 435 AN - OPUS4-21640 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Zeisler, Peter A1 - Völzke, Holger A1 - Rödel, Roland T1 - Development and evaluation of containers for radioactive waste disposal T2 - Developments in the transport of radioactive waste CY - Vienna, Austria DA - 1994-02-21 PY - 1994 SN - 1011-4289 IS - IAEA-TECDOC-802 SP - 233 EP - 238 AN - OPUS4-21641 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Gogolin, B. A1 - Rödel, R. A1 - Völzke, Holger A1 - Kowalewsky, Helmut T1 - Die sicherheitstechnische Prüfung von Tranport- und Lagerbehältern für abgebrannte Kernbrennstoffe T2 - Jahrestagung Kerntechnik `98 CY - München, Deutschland DA - 1998-05-26 PY - 1998 SN - 0720-9207 SP - 279 EP - 282 PB - Inforum AN - OPUS4-21607 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Völzke, Holger A1 - Zencker, Uwe A1 - Wieser, Günter A1 - Droste, Bernhard T1 - Testing and licensing of radioactive waste containers for disposal in Germany T2 - DisTec `98 - International conference on radioactive waste disposal CY - Hamburg, Germany DA - 1998-09-09 PY - 1998 VL - 2 SP - 431 EP - 436 PB - KONTEC CY - Hamburg AN - OPUS4-21608 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Völzke, Holger A1 - Rödel, Roland A1 - Droste, Bernhard T1 - A fracture mechanics safety concept to assess the impact behavior of ductile cast iron containers for shipping and storage of radioactive materials PY - 1994 SN - 0029-5493 SN - 1872-759X VL - 150 SP - 357 EP - 366 PB - North-Holland Publ. Co. CY - Amsterdam AN - OPUS4-21734 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Zeisler, Peter A1 - Völzke, Holger A1 - Rödel, Roland T1 - Development and evaluation of containers for radioactive waste disposal PY - 1994 SN - 0957-476X VL - 5 IS - 1 SP - 27 EP - 32 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21735 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Dreisvogt, H. A1 - Droste, Bernhard A1 - Völzke, Holger A1 - Probst, Ulrich T1 - Dry interim spent fuel storage casks - Licensing, evaluation and operational experience T2 - International symposium on safety and engineering aspects of spent fuel storage CY - Vienna, Austria DA - 1994-10-10 PY - 1995 IS - IAEA-SM-335/35 SP - 355 EP - 368 CY - Vienna, Austria AN - OPUS4-21728 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Völzke, Holger A1 - Rödel, Roland A1 - Zeisler, Peter A1 - Droste, Bernhard T1 - Considerations of the competent authority concerning the assessment of a brittle fracture safe ductile cast iron (DCI) cask design PY - 1995 SN - 0957-476X VL - 6 IS - 2/3 SP - 121 EP - 126 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21731 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Gogolin, Bernd A1 - Völzke, Holger A1 - Quercetti, Thomas A1 - Günther, Burkhard T1 - Extended drop tests of DCI casks with artificial flaws demonstrating the existing safety margins PY - 1995 SN - 0957-476X VL - 6 IS - 2/3 SP - 177 EP - 182 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21732 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Topic investigations of cask metal seals and polymer components for long dry storage periods T2 - Institute of Nuclear Materials Management INMM 51st Annual Meeting CY - Baltimore, MD, USA DA - 2010-07-11 PY - 2010 AN - OPUS4-21765 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Erhard, Anton A1 - Völzke, Holger A1 - Noack, Volker A1 - Weber, Wolfgang A1 - Wolff, Dietmar A1 - Rittscher, D. A1 - Schmidt, H. T1 - Construction of long term interim storage facility for nuclear reactor compartments of submarines: German support for utilisation of nuclear submarines in Russia KW - Interim storage facility KW - Nuclear reactor compartments of submarines KW - Building of the storage facility KW - Transportation of heavy compartments PY - 2008 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 19 IS - 2 SP - 117 EP - 121 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-17708 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Erfahrungen und Perspektiven bei der Bauartprüfung von Behältern zur Verpackung radioaktiver Abfälle T2 - TÜV Nord Seminar "Endlagerung radioaktiver Abfälle - Herausforderungen und Lösungen bei der Produktkontrolle radioaktiver Abfälle" CY - Hannover, Deutschland DA - 2008-06-11 KW - Endlager KW - Behälter KW - Bauartprüfung PY - 2008 SP - 11/1 EP - 11/7 AN - OPUS4-17679 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Approval of existent waste packages and new package design in preparation for the KONRAD repository T2 - Waste Management Symposia WM2008 CY - Phoenix, AZ, USA DA - 2008-02-24 PY - 2008 AN - OPUS4-17938 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Probst, Ulrich A1 - Hagenow, Peter A1 - Völzke, Holger A1 - Wolff, Dietmar A1 - Wossidlo, Peter A1 - Abbasi, Behboud A1 - Achelpöhler-Schulte, Andreas A1 - Schulz, Sebastian T1 - Investigation of seal effects according to axial compression variation of metal seals for transport and storage casks N2 - Casks for the transport and storage of heat generating radioactive waste in Germany are normally provided with screwed lid systems, which are in most cases equipped with double jacket metal seals with an inner spring wire to provide long term resistance to the seal compression force. Preservation of the high sealing quality of those seals under operational and accidental stress conditions is essentially important to the safety of those casks. Relative displacements of the lid system surfaces caused by specific impact scenarios cannot be excluded and have to be evaluated with respect to a possible increase in the leakage rate. To get representative data for such metal sealed lid systems, BAM has developed a special conceptualised flange system placed in an appropriate testing machine for relevant mechanical loading of the metal seals under static and cyclic conditions. Furthermore, the flange system enables continuous measurement of the standard helium leakage rate during each test. The primary aim of the investigation is to identify the correlation between variation of installation conditions (axial displacements) caused by external loads and the standard helium leakage rate. An essential parameter in this case is the useable resilience ru of a metal seal under relevant stress conditions. The useable resilience ru is the vertical difference in the cross-section between the seal's assembling status and the point where the leakage rate, by means of external load relieving, exceeds the quality criterion of 10-8 Pa m3 s-1. Load relieving can instantly occur due to modification of the seal groove dimension caused by accident impacts and deformation of the lid system. Furthermore, component specific basis data for the development of finite element calculation models should be collected. In the tests, seals are subjected to static and cyclic loads. All tests are performed at ambient temperature. This paper presents the test configuration, different test series and results of the current experiments. Typical load-displacement-leakage rate correlations are presented and discussed. KW - Seal effects KW - Axial compression variation KW - Metal seals KW - Helium leakage rate KW - Cyclic load PY - 2008 DO - https://doi.org/10.1179/174651008X278948 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 19 IS - 1 SP - 47 EP - 52 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-17540 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Probst, Ulrich A1 - Hagenow, Peter A1 - Völzke, Holger A1 - Wolff, Dietmar A1 - Wossidlo, Peter A1 - Abbasi, Behboud A1 - Achelpöhler-Schulte, Andreas A1 - Schulz, Sebastian T1 - Investigation of seal effects according to axial compression variation of metal seals for transport and storage casks T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 KW - Metal Seals KW - Axial Compression KW - Cycling Tests KW - Helium Leakage Rate PY - 2007 SP - 1 EP - 8 PB - Institute of Nuclear Materials Management AN - OPUS4-17542 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Erfahrungen und Perspektiven bei der Bauartprüfung von Behältern zur Verpackung radioaktiver Abfälle T2 - TÜV Nord Seminar "Endlagerung radioaktiver Abfälle" CY - Hanover, Germany DA - 2008-06-11 PY - 2008 AN - OPUS4-17597 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Aspekte der sicherheitstechnischen Begutachtung von Zwischen- und Endlagerbehältern T2 - 1. RAM-Behältersicherheitstage 2009 CY - Berlin-Horstwalde, Germany DA - 2009-03-26 PY - 2009 AN - OPUS4-19149 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Völzke, Holger T1 - Countdown für Konrad KW - Endlager KW - Radioaktive Stoffe KW - Behälter KW - Bauartprüfung KW - Sicherheit PY - 2010 SN - 0016-5808 VL - 2 SP - 28 EP - 31 PB - Storck CY - Hamburg AN - OPUS4-20914 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Topical Aspects of Waste Container Approval for the Upcoming KONRAD Repository T2 - Waste Management Symposia 2010 CY - Phoenix, AZ, USA DA - 2010-03-07 PY - 2010 AN - OPUS4-20994 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Qualifikation von Behältern für das Endlager KONRAD T2 - 7. Expertentreffen Strahlenschutz CY - Lindau/Bodensee, Deutschland DA - 2010-03-03 KW - Behälter KW - Sicherheit KW - Endlager KW - Bauartprüfung KW - Radioaktive Abfälle PY - 2010 IS - Register 12 SP - 1 EP - 8 AN - OPUS4-21001 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Aktuelle Entwicklungen auf dem Gebiet der Behälterbegutachtung in atomrechtlichen Zwischen- und Endlagerverfahren T2 - 2. RAM Behältersicherheitstage 2010, BAM CY - Berlin, Germany DA - 2010-03-18 PY - 2010 AN - OPUS4-20964 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Qualifikation von Behältern für das Endlager Konrad T2 - 7. Expertentreffen Strahlenschutz; TÜV SÜD CY - Lindau, Germany DA - 2010-03-03 PY - 2010 AN - OPUS4-20971 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Bletzer, Claus W. A1 - Zencker, Uwe A1 - Völzke, Holger A1 - Nehrig, Marko T1 - Strategien zur Bestimmung von Temperaturen von Transport- und Lagerbehältern für radioaktive Stoffe T2 - Jahrestagung Kerntechnik 2010 CY - Berlin, Deutschland DA - 2010-05-04 KW - Temperaturprofil KW - Transportbehälter KW - Radioaktive Stoffe PY - 2010 IS - Section 5 / Paper 514 SP - 1 EP - 6 CY - Berlin AN - OPUS4-22604 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Safety Aspects of Long Dry Interim Storage of Spent Fuel in Germany T2 - International High-Level Radioactive Waste Managment Conference CY - Albuquerque, NM, USA DA - 2011-04-10 PY - 2011 AN - OPUS4-23483 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Aktuelle Entwicklungen auf dem Gebiet der Behälter-Bauartprüfungen für das Endlager Konrad T2 - KONTEC 2011 CY - Dresden, Germany DA - 2011-04-06 PY - 2011 AN - OPUS4-23484 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Kasparek, Eva Maria A1 - Scheidemann, Robert A1 - Zencker, Uwe A1 - Wolff, Dietmar A1 - Völzke, Holger T1 - Effect of dynamic loading on compressional behavior of damping concrete N2 - In drop test scenarios related to assessing and licensing the storage procedure of spent fuel and high active waste, the casks under examination are generally not equipped with impact limiters. Hence, the extent of mechanical stresses in case of an assumed handling accident is largely affected by the ground properties of the reception hall floor in the specific storage facility. Unlike conventional brittle foundation materials, damping concrete performs quite well in such applications as it features high stiffness as well as high energy absorption due to the filler pore volume. However, its damping ability is not sufficiently exploited in current finite element (FE) calculations due to a lack of advanced material models for simulating its impact response. An implementation of qualified concepts that account for plastic, strain rate dependent behavior requires additional information that has to be provided by systematic test series. BAM recently started a research project to generate such data, subsequently to develop and to improve numerical methods for the analysis of impact limiters and damping foundation material and thus to optimize safety assessment tools for the design of transport and storage casks. A major part of this research concerns dynamic compression tests of variably shaped specimens conducted at a servo hydraulic 1MN impact testing machine as well as at a BAM facility for guided drop tests. This presentation focuses 100mm damping concrete cubes deformed vertically at constant rates under different constraint conditions. For example, a special fitting jig was constructed to subject the specimens to multi-axial loading. Thereby a deformation of 60% could be applied. Simulation was conducted by FE code ABAQUS™ based on material models “Concrete damaged plasticity” and “Crushable foam” which both allow defining rate sensitive nonlinear stress-strain relations in compression beyond the classic metal plasticity approach. T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Damping concrete KW - Strain rate sensitivity KW - Numerical simulation KW - Material model PY - 2010 SP - 1-8 (Thursday-T40-114) AN - OPUS4-23708 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 A1 - Wolff, Dietmar T1 - Experimentelle und numerische Untersuchungen von stoßdämpfenden Werkstoffen für Behälter zur Entsorgung radioaktiver Stoffe N2 - Die mechanische Beanspruchung von Transport- und Lagerbehältern für radioaktive Stoffe gemäß den durch die IAEA vorgegebenen Prüfszenarien oder bei Unfällen, die während der Handhabung in einer kerntechnischen Anlage auftreten können, wird maßgeblich durch das Design der Stoßdämpfer und die Eigenschaften des jeweiligen Untergrundes beeinflusst. Da der Nachweis der Behälterintegrität und -dichtheit häufig an numerische Simulationen gekoppelt ist, sind für die sicherheitstechnische Auslegung der Konstruktion zuverlässige Informationen über das Energieabsorptionsvermögen der Werkstoffe und eine geeignete Umsetzung dieser Daten in FEM - Programme erforderlich. Die im Rahmen von Falluntersuchungen bei der BAM festgestellten, teilweise erheblichen Abweichungen zwischen experimentellen und berechneten Größen sind entsprechend darauf zurückzuführen, dass die zur Verfügung stehenden numerischen Verfahren das komplexe Verhalten der stoßdämpfenden Strukturen nicht ausreichend präzise wiedergeben. Hiervon besonders betroffen sind Bauteile aus Holz und Polyurethan-Schaum (PU-Schaum), die zur Konstruktion von Behälterstoßdämpfern für die Transportkonfiguration eingesetzt werden, sowie Dämpferbeton, der in ausgewählten Bereichen im Fundament von Standort-Zwischenlagern eingebaut wird. Um die zugehörigen Materialmodelle weiter zu entwickeln und die dafür erforderliche Datenbasis zu schaffen, hat die BAM vor knapp zwei Jahren das vom BMBF geförderte Forschungsvorhaben ENREA (Entwicklung rechnerischer Analysemethoden für stoßdämpfende Strukturen beim Anprall oder Absturz von Abfallgebinden) gestartet. Wesentlicher Bestandteil ist ein systematisches Versuchsprogramm, bei dem die drei genannten Werkstoffe statisch und dynamisch hohen Druckbelastungen ausgesetzt werden. Relevante Versuchsparameter sind, neben der Dehnrate, die Temperatur und Lagerungsbedingungen sowie die Orientierung des Werkstoffes hinsichtlich der Belastungsrichtung. Dieser Beitrag präsentiert die wichtigsten Ergebnisse aus der ersten Versuchsphase, die durch weggesteuerte Versuche mit konstanten Prüfgeschwindigkeiten von 0,02 mm/s und 3000 mm/s gekennzeichnet ist. Darüber hinaus wird die Verwertung dieser Daten zur Anpassung von Materialmodellen auf der Grundlage von Nachrechnungen gezeigt, wobei die Möglichkeiten und Grenzen der verwendeten Konzepte Umrissen werden. Aufgrund des Umfangs, den die Versuche mit Holzwerkstoffen einnehmen, und des erforderlichen Aufwandes für die numerische Modellierung werden die entsprechenden Maßnahmen und Ergebnisse in einem eigenständigen Beitrag auf der KONTEC vorgestellt. T2 - KONTEC 2011 - 10. Internationales Symposium "Konditionierung radioaktiver Betriebs- und Stilllegungsabfälle" CY - Dresden, Germany DA - 06.04.2011 KW - Stoßdämpfende Werkstoffe KW - Materialmodellierung KW - Versuchsprogramm KW - Stoßbelastung KW - Dehnratenabhängigkeit KW - Temperaturabhängigkeit KW - Polyurethan Schaum KW - Dämpferbeton PY - 2011 SP - 453 EP - 458 AN - OPUS4-23709 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - ESCP Experimental Working Group Meeting T2 - ESCP Experimental Working Group Meeting CY - Baltimore, MD, USA DA - 2011-05-02 PY - 2011 AN - OPUS4-23689 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Kasparek, Eva Maria A1 - Zencker, Uwe A1 - Scheidemann, Robert A1 - Völzke, Holger A1 - Müller, Karsten T1 - Numerical and experimental studies of polyurethane foam under impact loading N2 - Proper predictions of the behaviour of shock absorber materials are of utmost importance in safety assessments for licensing casks for transport and storage of highly active waste. After having identified significant discrepancies between numerical results and the actual response of polyurethane foam limiters subjected to accidental scenarios, a new research project ENREA was established by BAM. A major objective is to enhance and to develop advanced material models intended to simulate limiters under impact loading. They should account for all major factors influencing the load–deformation relationship like temperature, strain rate and specific stress state. The corresponding test program, applicable plasticity models, the overall parameter identification strategy based on local and global optimization techniques as well as experimental and numerical results are presented here in particular for closed cell foams. KW - Polyurethane foam KW - Limiter KW - Impact loading KW - Strain rate KW - Plasticity model KW - Parameter identification PY - 2011 DO - https://doi.org/10.1016/j.commatsci.2010.11.025 SN - 0927-0256 VL - 50 IS - 4 SP - 1353 EP - 1358 PB - Elsevier CY - Amsterdam AN - OPUS4-23151 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Wolff, Dietmar T1 - Safety aspects of long dry interim cask storage of spent fuel in Germany N2 - Dry cask storage of spent fuel and high active waste front reprocessing is licensed and established in Germany for up to 40years so far. About 10years ago, the strategy has been shifted from centralized storage using facilities in Ahaus and Gorleben to cit-site storage facilities in Order to avoid immediate cask shipping from nuclear power plants. At present, several hundred casks are stored safeiy and without any major problem. BAM is highly involved in cask specific safety evaluations within the scope of licensing procedures as well as of quality assurance procedures during cask fabrication, loading and storage. A major prerequisite for any cask storage license is a valid transport Type B license. Subsequently, cask transportability has to be ensured at any point during the entire storage period. So far, this requirement is met by continuous maintenance of the Type B license. Anyhow, IAEA Type B regulations do not consider permanently loaded storage casks that have the sole purpose of being finally shipped öfter decades of storage inducing ageing effects. No transport safety demonstration has to be performed on aged cask components. T2 - International high-level radioactive waste management conference (IHLRWMC 2011) CY - Albuquerque, NM, USA DA - 10.04.2011 KW - Safety KW - Cask KW - Interim storage KW - Spent fuel PY - 2011 SP - 712 EP - 719 AN - OPUS4-23651 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Noack, Volker A1 - Nieslony, Gregor A1 - Hagenow, Peter A1 - Kovacs, Oliver T1 - Aktuelle Entwicklungen auf dem Gebiet der Behälter-Bauartprüfungen für das Endlager KONRAD N2 - Das Endlager Konrad wurde bereits im Jahr 2002 als Endlager für nicht Wärme entwickelnde radioaktive Abfälle genehmigt. Jedoch wurde diese Genehmigung anschließend beklagt und konnte erst 2007 in letzter Instanz bestätigt werden. Nachfolgend hat das Bundesamt für Strahlenschutz (BfS) mit der Planung und Realisierung zum Umbau des ehemaligen Eisenerzbergwerkes zum Endlager begonnen. Das genehmigte Endlagervolumen beträgt 303.000 m3 und basiert auf Abschätzungen für die zu erwartende Abfallmenge. Das Bergwerk selbst böte ein deutlich größeres Volumen. Mit der Einlagerung von Behältern kann allerdings erst nach Fertigstellung des Endlagers und nach derzeitigem Stand voraussichtlich nicht vor Ende dieses Jahrzehnts gerechnet werden. Gleichwohl besteht bereits heute ein hohes Interesse an der endlagergerechten Konditionierung und Verpackung der für Konrad vorgesehenen radioaktiven Abfälle, wofür nicht zuletzt von der BAM bauartgeprüfte und vom BfS zugelassene Behälter erforderlich sind. Kernpunkte der Endlagergenehmigung sind umfassende Anforderungen an Abfallprodukte und Behälter. Einzelheiten sind in den vom BfS der Genehmigung zu Grunde liegenden Berichten und Endlageranforderungen definiert. Diese enthalten vor allem Anforderungen an die Abfallprodukte und an die zu deren Verpackung erforderlichen Behälter. Mit der Genehmigungserteilung wurde auch eine Überarbeitung dieser Endlageranforderungen und hinsichtlich der Berücksichtigung Wasser gefährdender Stoffe gefordert. Diese Arbeiten werden derzeit vom BfS in Zusammenarbeit mit dem Niedersächsischen Landesbetrieb für Wasserwirtschaft, Küsten- und Naturschutz (NLWKN) und dem Institut für Sicherheitstechnik (ISTec) vorgenommen. Hinsichtlich der Anforderungen an die Endlagerbehälter wird allerdings davon ausgegangen, dass die für die Behälterbauartprüfung wesentlichen abfallprodukt- und behälterspezifischen Anforderungen davon nicht oder nur unwesentlich berührt sein werden. T2 - KONTEC 2011 - 10. Internationales Symposium "Konditionierung radioaktiver Betriebs- und Stilllegungsabfälle" CY - Dresden, Deutschland DA - 06.04.2011 KW - Behälter KW - Sicherheit KW - Endlager KW - Bauartprüfung KW - Radioaktive Abfälle PY - 2011 SP - 683 EP - 695 AN - OPUS4-23652 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Waste Container Design Testing and Qualification for the KONRAD Repository T2 - 5th International Seminar on Radioactive Waste Products (RADWAP 2008) CY - Würzburg, Germany DA - 2008-10-27 PY - 2008 AN - OPUS4-18272 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Qiao, Linan A1 - Zencker, Uwe A1 - Wieser, Günter A1 - Völzke, Holger T1 - Numerische Analyse eines ungedämpften Behälterabsturzes aus 0,3 m Höhe T2 - Jahrestagung Kerntechnik CY - Hamburg, Germany DA - 2008-05-27 KW - Duktiles Gusseisen KW - Behälterdesign KW - Sicherheitsanalyse KW - Dynamische Beanspruchungsbedingungen KW - Finite-Element-Berechnung PY - 2008 SP - 380 EP - 383 PB - INFORUM-Verl. u. Verwaltungsges. CY - Berlin AN - OPUS4-18314 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Qiao, Linan A1 - Zencker, Uwe A1 - Wieser, Günter A1 - Völzke, Holger ED - Topping, B. H. V. ED - M. Papadrakakis, T1 - Numerical safety assessment of a transport and storage cask for radioactive materials without impact limiters by the 0.3m drop test onto an unyielding target T2 - 9th International Conference on Computational Structures Technology (CST2008) CY - Athens, Greece DA - 2008-09-02 KW - Impact KW - Simulation KW - Cask KW - Safety KW - Drop KW - Foundation KW - Unyielding KW - Target PY - 2008 SN - 978-1-905088-23-2 IS - Paper 21 SP - 1 EP - 10 PB - Civil Comp Press CY - Kippen AN - OPUS4-18340 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Bletzer, Claus Wilhelm A1 - Zencker, Uwe A1 - Völzke, Holger A1 - Koch, Frank T1 - Asymmetrische Temperaturprofile in Transport- und Lagerbehältern für radioaktive Stoffe T2 - Jahrestagung Kerntechnik CY - Dresden, Deutschland DA - 2009-05-12 KW - Temperaturprofil KW - CFD-Berechnung KW - Transportbehälter KW - Radioaktive Stoffe PY - 2009 SP - 1 EP - 5(?) CY - Dresden AN - OPUS4-19431 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Wolff, Dietmar A1 - Probst, Ulrich T1 - Advanced investigations to evaluate spent fuel cask safety for extended storage periods T2 - 50th Annual Meeting of the Institute of Nuclear Materials Management (INMM) CY - Tucson, Arizona, USA DA - 2009-07-12 KW - Behälter KW - Beständigkeit KW - Sicherheit KW - Dichtungen KW - Polymere KW - Lagerung KW - Radioaktive Stoffe PY - 2009 SP - 1 EP - 10 AN - OPUS4-20707 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Völzke, Holger A1 - Droste, Bernhard A1 - Rödel, Roland T1 - Experiences and status in safety assessment methods within the scope of licensing procedures for multi-purpose flasks in Germany PY - 2000 SN - 0957-476X VL - 11 IS - 1-2 SP - 39 EP - 43 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21856 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Ellouz, Manel A1 - Noack, Volker T1 - Topical aspects of waste container approval for the upcoming KONRAD repository T2 - WM2010 - 36th Annual radioactive waste management symposium CY - Phoenix, Arizona, USA DA - 2010-03-07 KW - Behälter KW - Sicherheit KW - Endlager KW - Bauartprüfung KW - Radioaktive Abfälle PY - 2010 SN - 978-0-9828171-0-0 SP - 1 EP - 12(?) CY - Tempe, AZ, USA AN - OPUS4-21962 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Aspects on Long Term Storage of Used Nuclear Fuel and High Active Waste in Germany T2 - PATRAM 2010 (16th Internationl Symposium on the Packaging and Transport of Radioactive Material) CY - London, England DA - 2010-10-03 PY - 2010 AN - OPUS4-22239 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Behälterbegutachtung für die Zwishcenlagerung - Anforderungen - Erfahrungen - Perspektiven - T2 - 6. Symposium Lagerung und Transport radioaktiver Stoffe CY - Hanover, Germany DA - 2010-11-02 PY - 2010 AN - OPUS4-22240 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Protz, Christian A1 - Völzke, Holger A1 - Zencker, Uwe A1 - Hagenow, Peter A1 - Grünewald, Heike T1 - Entwicklung neuer Prüfmethoden zur numerischen Beanspruchungsanalyse für die Fallprüfung an Stahlblechcontainern für das Endlager Konrad N2 - Die Bundesanstalt für Materialforschung und -prüfung (BAM) führt im Rahmen einer Verwaltungsvereinbarung mit dem Bundesamt für Strahlenschutz (BfS) Bauartprüfungen für Behältertypen durch, die für die Endlagerung von nicht wärmeentwickelnden radioaktiven Abfällen in das Endlager Konrad vorgesehen sind. Zur Erlangung einer Eignungsbestätigung einer Behälterbauart für das Endlager Konrad müssen die Antragssteller die Einhaltung der vom BfS festgelegten behälterspezifischen Anforderungen nachweisen. Zentrale Bestandteile der Bauartprüfung sind die Sicherheitsnachweise zur Behälterauslegung gegen mechanische Betriebs- und Störfallbelastungen sowie gegen thermische Störfallszenarien. Die Prüfanforderungen umfassen hierbei Stapeldruckprüfung, Hebeprüfung, Fallprüfung, thermische Prüfung (Brand), ggf. einschließlich Dichtheitsprüfung zum Nachweis der Einhaltung von Dichtheitsanforderungen. Neben der Nachweisführung mittels sogenannter Baumusterprüfungen oder Obertragbarkeitsbetrachtungen können die Nachweise alternativ mittels numerischer Sicherheitsnachweise erbracht werden, sofern deren hinreichende Verifikation nachgewiesen wird, Dies kann u. a. durch den Vergleich mit hinreichend gesicherten experimentellen Ergebnissen geschehen, Die hier vorgestellten Untersuchungen sind Teil des internen Forschungsprojektes ConDrop der BAM, das zum Ziel hat, erweiterte Prüfmethoden zur Fallprüfung an Stahlblechcontainern für das Endlager Konrad mittels numerischer Beanspruchungsanalyse zu entwickeln. Dazu soll ein Finite-Elemente-(FE)-Modell entwickelt und mit experimentellen Daten, die in Fallversuchen ermittelt werden, verifiziert werden. T2 - Jahrestagung Kerntechnik 2011 CY - Berlin, Deutschland DA - 17.05.2011 KW - Falltest KW - Stahlblechcontainer KW - Endlager Konrad KW - Numerische Beanspruchungsanalyse PY - 2011 IS - Session TS-19 / Paper 161 SP - 1 EP - 3 AN - OPUS4-23755 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Kasparek, Eva Maria A1 - Scheidemann, Robert A1 - Wolff, Dietmar A1 - Zencker, Uwe A1 - Völzke, Holger T1 - Untersuchungen zum Verhalten von Dämpferbeton unter Stossbelastung N2 - Während des Transportes sind Behälter für hoch radioaktive Abfälle durch stoßdämpfende Bauteile vor Einwirkungen, die aus Unfallszenarien gemäß den IAEA Regularien resultieren können, weitestgehend geschützt. Nach dem Entfernen dieser Komponenten im Rahmen der Einlagerung ins Zwischenlager müssen Vorkehrungen getroffen sein, um Beanspruchungen der Behälter aus möglichen Handhabungsunfällen im Empfangsbereich zu reduzieren. Die Maßnahmen müssen vor allem darauf abzielen, die stoßdämpfenden Eigenschaften der potentiellen Aufprallflächen zu optimieren. Da Standardmaterialien für Fundamente nur ein geringes Energieabsorptionsvermögen aufweisen, wurde durch die Firma HOCHTIEF eine neuartige Betonmixtur entwickelt, bei der ein spezieller Leichtzuschlag zum Einsatz kommen. Zur Charakterisierung dieses sogenannten Dämpferbetons liegen Standardkennwerte vor sowie Messwerte aus Eindringversuchen, die zur Qualitätssicherung für jede Produktcharge durchgeführt werden. Das stoßdämpfende Potential des neuen Werkstoffs kann jedoch nur dann vollkommen ausgeschöpft werden, wenn die Energieabsorption in numerischen Simulationen der Behälterabstürze über die gesamte Belastungsdauer zuverlässig wiedergegeben wird. Für die Implementierung und Anpassung eines entsprechenden Materialmodelis in einem Finite Elemente (FE) Programm sind Daten aus systematischen Druckversuchen mit Variation der relevanten Einflussgrößen erforderlich. An der BAM werden daher im Rahmen eines werkstoffübergreifenden Forschungsvorhabens zur Untersuchung von stoßdämpfenden Strukturen auch die Eigenschaften von Dämpferbeton experimentell untersucht und zugehörige numerische Methoden entwickelt. Der aktuelle Beitrag behandelt die Ergebnisse der ersten Projektphase, in der kubische Probekörper mit der Kantenlänge 100mm bei unterschiedlichen Lagerungsbedingungen statisch und dynamisch gestaucht wurden. In nachfolgenden Versuchen wird der Einfluß der Probengröße ermittelt sowie die Eignung der verwendeten Materialmodelle anhand realistischer Belastungssituationen validiert. Versuchsprogramm. T2 - Jahrestagung Kerntechnik 2011 CY - Berlin, Germany DA - 17.05.2011 KW - Stoßdämpfende Werkstoffe KW - Materialmodellierung KW - Versuchsprogramm KW - Stoßbelastung KW - Dehnratenabhängigkeit KW - Temperaturabhängigkeit KW - Polyurethan Schaum KW - Dämpferbeton PY - 2011 IS - Session TS-17 / Paper 171 SP - 1 EP - 5 AN - OPUS4-23836 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Weber, Mike A1 - Qiao, Linan A1 - Droste, Bernhard A1 - Völzke, Holger T1 - Mechanical safety analyses of cast iron containers for the KONRAD repository N2 - Within the last years BAM has carried out numerous drop tests with prototype casks made of ductile cast iron onto targets according to the requirements for final disposal of non-heat generating waste in the German KONRAD repository. The results have shown that the target specifications in the acceptance criteria have to be defined more accurately to get reproducible test results with high precision. Hence, a suitable test stand foundation was developed with much effort. The integrity of the upper concrete layer of this target must be preserved during a test. Recently the geometrical properties of a tested cubic cast iron container led to a concentration of the impact forces beneath the container walls. The target was damaged strongly with the consequence of inadmissible reduction of cask stresses. For that reason the target construction was modified. However, the basic design was not changed. A prefabricated concrete slab was still joined by a mortar layer to the IAEA target of the BAM drop test facility. In the course of the optimization of the test stand foundation the concrete slab dimensions and the reinforcement were enlarged. During the drop test repetition the target kept intact. Additionally, the mechanical behavior of the cast iron container and the target was analyzed by finite element calculations. This improved target construction is suggested as a reference target for drop tests with casks whose mass and base area are covered by the container types VI or VII respectively according to the KONRAD repository acceptance criteria. The measurements during the drop tests with cast iron casks have provided the strains on the cask surface at selected positions. This allows the verification of finite element simulations of drop tests which show the stress distribution also inside the component. In September 2008 a drop test was carried out with a cylindrical cast iron cask containing an artificial material defect which was designed under consideration of critical stress states in the cask body. This drop test could demonstrate the safety against failure by fracture of a cask made of a special cast iron with reduced fracture toughness. T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Ductile iron KW - Container design KW - Safety assessment KW - Fracture mechanics KW - Dynamic loading conditions PY - 2010 SP - 1 EP - 8 (Session T28 / Paper 220) AN - OPUS4-23844 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Völzke, Holger A1 - Wieser, Günter A1 - Qiao, Linan T1 - Safety Margins of Spent Fuel Transport and Storage Casks Considering Aircraft Crash Impacts PY - 2002 SN - 0957-476X VL - 13 IS - 3-4 SP - 313 EP - 316 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-2697 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Lange, F. A1 - Hörmann, E. A1 - Schwarz, G. A1 - Droste, Bernhard A1 - Völzke, Holger A1 - Wieser, Günter T1 - Spent Fuel Transport and Storage Casks under Extreme Accidents T2 - 10th International High-Level Radioactive Waste Management Conference (IHLRWM-10) CY - Las Vegas, NV, USA DA - 2003-03-30 PY - 2003 SN - 0-89448-669-1 SP - 465 EP - 470 PB - American Nuclear Society CY - La Grange Park, Ill. AN - OPUS4-2698 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Koordinierungsstelle für Informationen zur Behälterabfertigung (KOBAF / BIBO) T2 - 3. Symposium - Beförderung und Lagerung radioaktiver Stoffe - Stand der BE-Entsorgung CY - Hanover, Germany DA - 2003-05-08 PY - 2003 AN - OPUS4-3070 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - German Competent Authority Guidance in FE Methods Applications for Package Design Assessment T2 - 14th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2004) CY - Berlin, Germany DA - 2004-09-20 PY - 2004 AN - OPUS4-4693 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Status and Developments in Design Testing and Licensing on Non-Heat Generating T2 - 4th International Seminar on Radioactive Waste Products CY - Würzburg, Germany DA - 2002-09-22 PY - 2002 AN - OPUS4-5746 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Safety Assessment Aspects of Materials for Radioactive Waste Containers T2 - 4th International Seminar on Radioactive Waste Products CY - Würzburg, Germany DA - 2002-09-22 PY - 2002 AN - OPUS4-5742 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger T1 - Waste Products and Containers -Qualification Procedures for Interim Storage and Disposal T2 - Waste Management Symposium 2005 CY - Tucson, AZ, USA DA - 2005-02-27 PY - 2005 AN - OPUS4-6993 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -