TY - CONF A1 - Linnemann, Konrad A1 - Ballheimer, Viktor A1 - Müller, Lars A1 - Rolle, Annette A1 - Wille, Frank A1 - Droste, Bernhard T1 - Aspects of spent fuel behavior assessment for transport packages T2 - International Conference on Management of Spent Fuel from Nuclear Power Reactors - An Integrated Approach to the Back-End of the Fuel Cycle N2 - Transport packages for spent nuclear fuel have to be assessed with respect to specific transport conditions which are defined in the safety regulations of the International Atomic Energy Agency. In general, gastight fuel rods constitute the first barrier of the containment system. The physical state of the spent fuel and the fuel rod cladding as well as the geometric configuration of the fuel assemblies are important inputs for the evaluation of the package safety under transport conditions. The objective of this paper is to discuss the methodologies accepted by BAM for the authority assessment of spent fuel behavior within the package design approval procedure of German package designs. In particular, cracks or failures in the fuel rod cladding can occur under regulatory transport conditions. These defects can cause the release of gas, volatiles, fuel particles or fragments into the package cavity and have to be considered properly in the safety analysis. Another issue is the transport of defective fuel rods. One concept is to use special canisters which can be handled like fuel assemblies. This concept requires additional assessment concerning drying, sealing and the mechanical and thermal design of such canisters. The package as a mechanical system is characterized by a complex set of interactions, e.g. between the fuel rods within the assembly as well as between the fuel assemblies, the basket, and the cask containment. This complexity together with the limited knowledge about the material properties and the variation of the fuel assemblies regarding cladding material, burn-up and the operation history makes an exact mechanical analysis of the fuel rods nearly impossible. The simplified approaches to consider conservatively spent fuel behavior currently accepted by BAM are presented here. T2 - International Conference on Management of Spent Fuel from Nuclear Power Reactors - An Integrated Approach to the Back-End of the Fuel Cycle CY - Wien, Austria DA - 15.06.2015 KW - Transport packages KW - Spent fuel assessment PY - 2015 SP - 1 AN - OPUS4-38102 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko A1 - Wille, Frank A1 - Feldkamp, Martin A1 - Rolle, Annette T1 - Aspects of gas generation caused by residual water inside ILW packages T2 - RAMTRANS 2015 - 10th International conference on radioactive materials transport and storage (Proceedings) N2 - Packages for intermediate level waste (ILW) often contain residual water besides the actual waste. The water either exists as obvious free water or it may be bound physically or chemically, e.g. as pore water. Water driven gas generation could occur by vaporisation and by radiolysis. Steam as the result of vaporisation causes an increasing pressure inside a package and can affect corrosion. Vaporisation and condensation processes itself change the thermal behaviour of the content especially during strongly unsteady thermal situations like accident fire situations. Radiolysis changes the chemical composition of the content which could cause an unexpected interaction, e.g. hydrogen embrittlement. Besides the pressure build-up the radiolysis of water generates hydrogen and oxygen, which can be highly flammable respectively explosive. The gas generation caused by vaporisation and radiolysis must be taken into account during the design and the safety assessment of a package. Pressure build-up, a changed thermal behaviour and content chemistry, and especially the risk of accumulation of combustible gases exceeding the limiting concentration for inflammability has to be considered in the safety assessment. Approaches to ensure the transportability of stored packages due to radiolysis will be discussed. T2 - RAMTRANS 2015 - 10th International conference on radioactive materials transport and storage CY - Oxford, UK DA - 19.05.2015 KW - Typ-B KW - ILW package KW - Gas generation KW - Radiolysis KW - Wet content PY - 2015 SP - 1 EP - 7 AN - OPUS4-33429 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin A1 - Nehrig, Marko A1 - Bletzer, Claus Wilhelm A1 - Musolff, André A1 - Wille, Frank T1 - Combustion of wood encapsulated in steel sheets during fire test T2 - RAMTRANS 2015 - 10th International conference on radioactive materials transport and storage (Proceedings) N2 - Packages for the transport of radioactive material are often equipped with impact limiters consisting of wood, encapsulated by Steel sheets. These impact limiters shall ensure the transport cask meets the IAEA safety requirements. After damage caused by the mechanical tests the package has to withstand a severe fire scenario. According to the regulations during and following the fire test, the specimen shall not be artificially cooled and any combustion of materials of the package shall be permitted to proceed naturally. Due to results of the French institute IRSN it was shown that after the fire test an additional energy supply from a pre-damaged impact limiter should be taken into account. The combustion or smouldering of wood was of interest. BAM started a first test phase to examine the issue of combustion for such kind of package components. The goal was to understand the phenomena under the consideration of relevant regulatory boundary conditions. Several metal buckets were filled with wood and equipped with thermocouples. The test specimens have been prepared with different damage arrangements to take the influence of the mechanical tests into account. This paper shows the experimental Setup and the conduction of the tests. The first test shows that pre-damaged metal encapsulations can lead to smouldering of the wood and with this to a Supplement energy release after the end of the 30 minute fire. The consequence could be, to consider additional thermal loads of wood filled impact limiters to filled the IAEA regulations, if the conditions of the tests are transferable to the safety analysis of the package design. T2 - RAMTRANS 2015 - 10th International conference on radioactive materials transport and storage CY - Oxford, UK DA - 19.05.2015 KW - Typ-B KW - Impact limiter KW - Shock absorber KW - Wood KW - Thermal test KW - Fire test PY - 2015 SP - 1 EP - 9 AN - OPUS4-33407 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Ballheimer, Viktor A1 - Quercetti, Thomas A1 - Sterthaus, Jens T1 - Considereation of Gaps between Content and Lid within Package Design Assessment T2 - Ramtrans 2015, Conference on Radioactive Materials Transport and Storage T2 - Ramtrans 2015, Conference on Radioactive Materials Transport and Storage CY - Oxforn, UK DA - 2015-05-19 PY - 2015 AN - OPUS4-33448 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Ballheimer, Viktor A1 - Quercetti, Thomas A1 - Sterthaus, Jens T1 - Consideration of gaps between content and lid within package design assessment T2 - RAMTRANS 2015 - 10th International conference on radioactive materials transport and storage (Proceedings) N2 - Type B(U) packages for the transport of radioactive material have to withstand accident conditions of transport defined in the regulations of the International Atomic Energy Agency in form of different mechanical (drop) tests with a subsequent thermal test. According to the regulatory requirements the orientation of the package in drop tests shall be such to cause the most damaged state in the components performing the safety functions. For the package Iid system a 9 m drop onto the unyielding target with Iid side downwards is often the most damaging orientation. The impact Ioads acting on the Iid in this orientation result mainly from interaction between Iid and internal content. In case of a movable content its impact onto the inner side of the Iid can cause additional Ioad peaks on the Iid and the Iid bolts. The intensity of the internal collision depends on the position of content relating to Iid at the time of package first contact with target. Due to physical limitations an axial gap, which could be set in "pre-drop" configuration of package or which could spontaneously appear during the drop test, usually does not cover the maximum size possible in specific package design. In this context, the combination of drop tests with post-test analysis can be helpful to better estimate the effect of internal impact. The paper summarizes some aspects of this issue based on the BAM experience in the design assessment of Type B(U) transport packages. Additionally the paper shall support applicants in German approval procedures to reduce rounds of questions and ensure delivery of reliable safety case documents to the authorities. T2 - RAMTRANS 2015 - 10th International conference on radioactive materials transport and storage CY - Oxford, UK DA - 19.05.2015 KW - Transport packages KW - Accident conditions of transport KW - Internal impacts KW - Lid/content interaction KW - Radioactive material PY - 2015 SP - 1 EP - 10 AN - OPUS4-33419 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin A1 - Wille, Frank A1 - Droste, Bernhard T1 - Experience feedback from BAM safety assessment of transport packages T2 - RAMTRANS 2015 - 10th International conference on radioactive materials transport and storage (Proceedings) N2 - BAM as competent authority regarding assessment of mechanical and thermal design, activity release and quality assurance measures of Type-B(U) transport packages developed a thesaurus of experience feedback topics from recent assessment procedures. The list is structured according to the European PDSR guide. It involves issues, which from BAM's point of view, needed clarification during the last package design assessment procedures. The list contains issues from Operation (e.g. deactivation of handling lugs not intended for package handling), maintenance (e.g. leak tightness of impact limiting devices) to technical assessment (e.g. formation of hydrogen by radiolysis and its impact on pressure and ignitability, consideration of ageing mechanisms, thermo-mechanical assessment, impact of gaps between content and flask) as well as to general and specific safety analysis report requirements (e.g. report structure and required data). T2 - RAMTRANS 2015 - 10th International conference on radioactive materials transport and storage CY - Oxford, UK DA - 19.05.2015 KW - Transport KW - RAM KW - Radioactive material KW - Cask KW - Flask KW - Nuclear fuel PY - 2015 SP - 1 EP - 7 AN - OPUS4-33420 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank T1 - Qualitätsfall bei der Fertigung von Tragzapfen für Castor-Behälter T2 - Informationsaustausch zur verkehrsrechtlichen Aufsicht bei der Beförderung radioaktiver Stoffe T2 - Informationsaustausch zur verkehrsrechtlichen Aufsicht bei der Beförderung radioaktiver Stoffe CY - Handelskammer, Bremen, Deutschland DA - 2015-01-27 PY - 2015 AN - OPUS4-32785 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank T1 - Auffälligkeiten an Hebeösen von UF6-Behältern T2 - Informationsaustausch zur verkehrsrechtlichen Aufsicht bei der Beförderung radioaktiver Stoffe T2 - Informationsaustausch zur verkehrsrechtlichen Aufsicht bei der Beförderung radioaktiver Stoffe CY - Handelskammer, Bremen, Deutschland DA - 2015-01-27 PY - 2015 AN - OPUS4-32786 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Sterthaus, Jens A1 - Ballheimer, Viktor A1 - Apel, Andreas A1 - Neumann, Martin A1 - Kuschke, Christian T1 - Approaches of Trunnion Design T2 - IAEA Working Group Meeting on Tie-Down System Design T2 - IAEA Working Group Meeting on Tie-Down System Design CY - IAEA Vienna, Austria DA - 2015-02-23 PY - 2015 AN - OPUS4-32791 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CHAP A1 - Wille, Frank A1 - Nehrig, Marko A1 - Feldkamp, Martin ED - Sorenson, K.B. T1 - Thermal performance of transportation packages for radioactive materials T2 - Safe and secure transport and storage of radioactive materials - 1st Ed. N2 - Prevention of damage caused by heat is one of the objectives during package safety evaluation. This chapter describes basics of heat transfer and major aspects of regulatory requirements. Package temperature criteria and fire test conditions are explained. Special package design features regarding material properties and safety evaluation concepts are discussed. Experimental fire testing is performed by pool fire or with the help of a furnace. Analysis by numerical or analytical approaches show temperature gradients and whether compliance with the regulatory requirements and specified design temperatures is met. The tightness of the package lid system influenced by geometry changes is in the focus of a holistic thermo-mechanical approach considering the entire mechanical and thermal load conditions according the regulatory requirements. KW - Package KW - Safety KW - Storage KW - Transport KW - Testing KW - Convection KW - Fire test KW - Heat KW - Insulation KW - Thermal analysis PY - 2015 SN - 978-1-78242-309-6 SN - 978-1-78242-322-5 DO - https://doi.org/10.1016/B978-1-78242-309-6.00008-3 N1 - Serientitel: Woodhead publishing series in energy – Series title: Woodhead publishing series in energy IS - 78 SP - Chapter 8, 107 EP - 121 PB - Woodhead Publ. AN - OPUS4-33842 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -