TY - RPRT A1 - Völzke, Holger A1 - Wolff, Dietmar A1 - Barnabas, I. A1 - Ordogh, M. A1 - Shirai, K. A1 - Saegusa, T. A1 - Cho, C.-H. A1 - Kook, D. A1 - Lopez, J. F. A1 - Conde, J. M. A1 - Alejano, C. A1 - Lloret, M. A1 - Quecedo, M. A1 - Shea, J. A1 - Ross, P. J. A1 - White, N. A1 - Rossiter, G. A1 - Hodgson, Z. A1 - Sorenson, K. A1 - McConnell, P. A1 - Hanson, B. ED - Sorenson, K. ED - Shirai, K. ED - Völzke, Holger T1 - Extended storage collaboration program - International subcommittee report - International perspectives on technical data gaps associated with extended storage and transportation of used nuclear fuel N2 - The US Electric Power Research Institute (EPRI) chartered a volunteer committee in November 2009 to share information and data related to extended storage and subsequent transportation of used nuclear fuel. This committee is named the Extended Storage Collaboration Program (ESCP) and was initially comprised of representatives from industry (fuel and cask vendors, utilities, the Nuclear Energy Institute, and EPRI), as well as government (e.g., US Department of Energy) and the US Nuclear Regulatory Commission. The primary motivation for establishing this committee was the recognition that used fuel will need to be stored past the regulatory licensing timeframe. In the US, this is mainly a result of the cessation of licensing activities for the planned Yucca Mountain repository. Recognizing that there is a global interest in extended storage and transportation, the International Subcommittee was established in December 2010 to extend the reach of ESCP internationally in order to fully address extended storage and transportation issues, as they apply to different systems, national policies, and regulations around the world. This Subcommittee serves to deepen the overall understanding of degradation mechanisms associated with storage and transportation systems, expand the access to data and programs related to extended storage and transportation, and strengthen the overall technical basis for programmatic decisions. The International Subcommittee established three basic objectives: 1. Conduct a technical data gap survey 2. Assess opportunities to leverage specific research to benefit the larger international group 3. Integrate our work with relevant International Atomic Energy Agency (IAEA) committee work This report constitutes completion of Objective #1. The International Subcommittee worked to identify and prioritize technical gaps that need to be addressed to support licensing activities within their own countries. Because there are varying types of storage and transportation system designs, national policies and regulations, there are identified commonalities as well as differences that stress the importance of this work on an international scale. Section 5 of this report identifies and prioritizes all of the identified data gaps for each participating organization. However, important data gaps were identified that had a consensus of opinion of being a high priority. These technical gaps, as a function of storage system component are: 1. Fuel – hydride effects on fuel cladding and retrievability of fuel after storage 2. Canister – general canister corrosion and stress corrosion cracking of canister closure welds, particularly in marine environments 3. Closure – degradation of bolts and seals (metallic and organic) 4. Overpack – concrete degradation Dry storage systems were originally designed for limited periods. With extended dry storage, it is generally believed that used fuel can be stored safely and securely past the regulatory time period. However, the technical arguments need to be made to justify extended licensing periods. Addressing the data gaps will provide the necessary arguments to justify license extensions. In the development of this report, the International Subcommittee met five times over a period of 18 months to work through the issues of identifying and prioritizing the data gaps, and discussing of technical issues as they pertain to the safety of used fuel storage and transportation. The meeting locations and dates were: 1. Vienna June 2010 2. London October 2010 3. Charlotte December 2010 4. Berlin June 2011 5. Charlotte December 2011 This report is not meant to be a technical document. Rather, it is an overview of country regulatory policy, a review of in-country operational status and used fuel inventory, followed by a role-up of identification and prioritization of technical data gaps. Technical documents that were used in the data gap assessments are referenced. It is important to note that this document represents only the opinions of the contributors. This document in no way represents any official country position. The organizations providing support to the writing of this report are: Germany: - Bundesanstalt für Materialforschung und -prüfung Hungary: - Radioaktiv Julladekokat Kezelo Kozhasznu - Som System Kft. Japan: - Central Research Institute of Electric Power Industry South Korea: - Korea Atomic Energy Research Institute - Korea Radioactive Waste Management Corporation Spain: - Consejo de Seguridad Nuclear - ENRESA Empresa Nacional de Residuos Radiactivos - ENUSA Industrias Avanzadas United Kingdom: - EDF Energy - National Nuclear Laboratory Ltd. United States: - Pacific Northwest National Laboratory - Sandia National Laboratories KW - Used/spent fuel dry storage KW - Used/spent fuel transportation KW - Extended used/spent nuclear fuel storage KW - High burnup spent fuel storage and transportation KW - Spent fuel storage and transportation KW - Extended Storage Collaboration Program (ESCP) KW - ESCP International Subcommittee PY - 2012 UR - https://www.epri.com/research/products/1026481 N1 - This final report was prepared as part of the volunteer Extended Storage Collaboration Program (ESCP). VL - 1026481 SP - 1 EP - 132 PB - Electric Power Research Institute (EPRI) CY - Palo Alto, CA, USA AN - OPUS4-27405 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Kasparek, Eva Maria A1 - Völzke, Holger A1 - Scheidemann, Robert A1 - Zencker, Uwe A1 - Wolff, Dietmar T1 - Experimental and numerical studies of shock absorbing materials for containers for radioactive waste N2 - Safety assessments of Containers for Transport and storage of radioactive materials involvedrop scenarios prescribed in the regulations of the International Atomic Energy Agency - IAEA or potential accidents that might occur in a specific nuclear facility. Hereby, the design of impact limiters and foundation properties of the handling Region have a major effect on the mechanical loading of the cask and lid System. Reliable numerical simulations, which very often constitute a relevant part of such safety proofs, require systematic information About the energy absorption potential of the respectiye materials and its implementation in FEM (finite element) programs. However, when performing drop tests, BAM (BAM Bundesanstalt für Materialforschung und -prüfung, Federal Institute for Materials Research and Testing) identified significant differences between numerical and experimental results, which most likely result from numerical methods that do not sufficiently reproduce the behaviour of impact limiting structures. Particularly concerned are Container impact limiter made of wood or Polyurethane foam as well as damping concrete bricks, which are embedded in foundations of German interim storages. PY - 2012 SN - 1431-5254 VL - 57 IS - 6 SP - 397 EP - 401 PB - Inforum CY - Berlin AN - OPUS4-26261 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Kasparek, Eva Maria A1 - Völzke, Holger A1 - Scheidemann, Robert A1 - Zencker, Uwe T1 - Numerical and experimental investigations of polyurethane foam for use as cask impact limiter in accidental drop scenarios N2 - Rigid, closed-cell polyurethane foams are frequently used as cask impact limiters in nuclear materials and hazardous waste transport due to their high energy-absorption potential. When assessing the cask integrity in accidental scenarios based on numerical simulations, a description of the foam damping properties is required for different strain rates and for a wide temperature ränge with respect to waste heat generation in conjunction with critical operating and environmental conditions. Implementation and adaption of a respective finite element material model strongly relies on an appropriate experimental data base. Even though extensive impact experiments were conducted e.g. in Sandia National Laboratories, Savannah River National Laboratory and by Rolls Royce plc, not all relevant factors were taken into account. Hence, BAM who is in Charge of the mechanical evaluation of such packages within the approval procedure in Germany, incorporated systematic test series into a comprehensive research project aimed to develop numerical methods for a couple of damping materials. In a first step, displacement driven compression tests have beenperformed on confined, cubic specimens at five loading rates ranging from 0.02 mm/s to 3 m/s attemperatures between +90°C and -40°C. Materials include two differentPolyurethane foam types called FR3718 and FR3730 having densities of 280 kg/m3 and 488 kg/m3 from the product line-up of General Plastics Manufacturing Company. Their data was used to adapt an advanced plasticity model allowing for reliably simulating cellular materials under multi-axial compression States, Therefore, an automated parameter identification procedure had been established by combining an artificial neural network with local optimization techniques. Currently, the selected numerical material input values are validated and optimized by means of more complex loading configurations with the prospect of establishing methods applicable to impact limiters under severe accidental conditions. The reference data base is provided by experiments, where weights between 212 kg and 1200 kg have been dropped from heights between 1.25 m and 7 m on confined 10 cm cubic foam specimens. By presenting the deviations between experimental values and the corresponding Output of finite element simulations, the Potentials and restrictions of the resulting models are highlighted. T2 - WM2012 - Waste management conference CY - Phoenix, AZ, USA DA - 26.02.2012 KW - Plasticity KW - Finite elements KW - Material models KW - Rate dependency KW - Temperature dependency KW - Compression tests KW - Drop tests KW - Parameter identification PY - 2012 SN - 978-0-9836186-1-4 N1 - Serientitel: WM Symposia – Series title: WM Symposia IS - Paper 12099 SP - 1 EP - 9 AN - OPUS4-26270 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -