TY - CHAP A1 - Wille, Frank A1 - Nehrig, Marko A1 - Feldkamp, Martin ED - Sorenson, K.B. T1 - Thermal performance of transportation packages for radioactive materials 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 - 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 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 - Nehrig, Marko A1 - Scheidemann, Robert A1 - Wille, Frank A1 - Ballheimer, Viktor T1 - Investigation of the internal impact during a 9 m drop test of an accident-safe waste package N2 - The safety assessment of packages for the transport of radioactive material follows the IAEA regulations and guidance. The specified regulatory tests cover severe accidents and demonstrate the package containment system integrity. Special attention must be drawn to the behaviour of the content which could move inside the package due to unpreventable gaps caused by the loading procedure and the structure of the content. A possible internal impact of the content which occurs during the drop tests onto the lid system is investigated. The IAEA regulations SSR-6 and the Guidance SSG-26, revised recently, consider input from Germany and France related to the significance of internal gaps. In the context of a waste package design assessment, a model was equipped with a representative content to conduct a drop test with an internal impact. The weight and kinetic impact of this content covered all possible real contents. The objective of the test was to maximize the load onto the lid system and to prove the mechanical integrity by complying with the required leak tightness. The test was conducted conservatively at a package temperature lower than -40 °C at the BAM Test Site Technical Safety. This paper gives an overview of efforts to address internal gaps and their consequences, and the BAM efforts with the implementation of this topic into IAEA regulations and guidance material. The paper then focuses on the conduction of a drop test and investigation of internal component impact. T2 - ASME 2021 Pressure Vessels & Piping Conference (PVP2021) CY - Online meeting DA - 13.07.2021 KW - Internal gaps KW - Drop test KW - IAEA PY - 2021 SN - 978-0-7918-8535-2 DO - https://doi.org/10.1115/PVP2021-60996 SP - 1 EP - 6 PB - American Society of Mechanical Engineers (ASME) CY - New York, NY, USA AN - OPUS4-54742 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko T1 - Investigation of the internal impact during a 9 m drop test of an accident-safe waste package N2 - The safety assessment of packages for the transport of radioactive material follows the IAEA regulations and guidance. The specified regulatory tests cover severe accidents and demonstrate the package containment system integrity. Special attention must be drawn to the behaviour of the content which could move inside the package due to unpreventable gaps caused by the loading procedure and the structure of the content. A possible internal impact of the content which occurs during the drop tests onto the lid system is investigated. The IAEA regulations SSR-6 and the Guidance SSG-26, revised recently, consider input from Germany and France related to the significance of internal gaps. In the context of a waste package design assessment, a model was equipped with a representative content to conduct a drop test with an internal impact. The weight and kinetic impact of this content covered all possible real contents. The objective of the test was to maximize the load onto the lid system and to prove the mechanical integrity by complying with the required leak tightness. The test was conducted conservatively at a package temperature lower than -40 °C at the BAM Test Site Technical Safety. This paper gives an overview of efforts to address internal gaps and their consequences, and the BAM efforts with the implementation of this topic into IAEA regulations and guidance material. The paper then focuses on the conduction of a drop test and investigation of internal component impact. T2 - ASME 2021 Pressure Vessels & Piping Conference (PVP2021) CY - Online meeting DA - 13.07.2021 KW - Drop test KW - Internal gaps KW - IAEA PY - 2021 AN - OPUS4-54744 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin A1 - Quercetti, Thomas A1 - Gleim, Tobias A1 - Nehrig, Marko A1 - Musolff, André A1 - Wille, Frank T1 - R&D Activities by BAM Related to Transport Package Fire Testing N2 - Packages for the transport of radioactive material shall meet the mechanical and thermal test requirements of the International Atomic Energy Agency (IAEA) regulations for package design approval. Besides mechanical testing, the Federal Institute for Materials Research and Testing (BAM) performs thermal tests in accordance with the IAEA regulations. The thermal test includes a 30-minute 800°C fully engulfing fire. BAM continuously performs various thermal experiments for the investigation of the thermal response of packages with respect to the IAEA fire. The purpose of this paper is to give an overview of the already performed, ongoing and future physical tests and experiments of BAM in the field of thermal investigations. These research and development works shall support our competencies for the authority package design assessment. BAM operates a propane gas fire test facility. To be able to carry out comparative investigations and validity between the propane fire and the in detail prescribed pool fire test in the regulations, BAM carries out various calorimetric tests and investigates the boundary conditions of the fire with the help of fire reference packages. At the same time, we are conducting various fire scenarios with wood-filled impact limiters. Large-scale fire tests of impact limiters are carried out on a full scale as well as on a small scale. Influencing variables are investigated in particular by means of geometric changes and the consideration of artificial damages, in particular holes. In addition to propane fire as a heat source, thermal scenarios are also investigated with hydrogen as heat source and an infrared radiator system to ignite test specimens. For these numerous test arrangements, the transferability to existing and newly developed transport package designs is essential and fruitful within the review of design approvals, especially for Dual Purpose casks with a long-lasting operation time. T2 - 20th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 22) CY - Juan-Les-Pins, France DA - 11.06.2023 KW - Fire KW - Testing KW - Hydrogen KW - Wood KW - Propane KW - Heat Flux KW - Fire Reference Package KW - Radioactive Material PY - 2023 SP - 1 EP - 10 AN - OPUS4-57721 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko T1 - Effects of additional gases resulting from residual water inside ILW packages 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. A 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 behavior 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 behavior and content chemistry, and especially the risk of accumulation of combustible gases exceeding the limiting concentration for flammability has to be considered in the safety assessment. Approaches to ensure the transportability of stored packages due to radiolysis will be discussed. T2 - ASME 2016 Pressure Vessels & Piping Conference (PVP2016) CY - Vancouver, BC, Canada DA - 17.07.2016 KW - Radiocactive material KW - Thermal KW - Pressure build-up KW - Gas generation PY - 2016 AN - OPUS4-38448 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko A1 - Wille, Frank A1 - Rolle, Annette A1 - Linnemann, Konrad T1 - Effects of additional gases resulting from residual water inside ILW packages 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. A 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 behavior 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 behavior and content chemistry, and especially the risk of accumulation of combustible gases exceeding the limiting concentration for flammability has to be considered in the safety assessment. Approaches to ensure the transportability of stored packages due to radiolysis will be discussed. T2 - ASME 2016 Pressure Vessels & Piping Conference (PVP2016) CY - Vancouver, BC, Canada DA - 17.07.2016 KW - Radioactive material KW - Pressure build-up KW - Gas generation PY - 2016 SN - 978-0-7918-5045-9 VL - 7 SP - Paper 63008, 1 EP - 6 AN - OPUS4-38451 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin A1 - Nehrig, Marko A1 - Bletzer, Claus A1 - Musolff, André A1 - Erenberg, Marina A1 - Wille, Frank T1 - Behaviour of Wood Filled Impact Limiters during Fire Test 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 mechanical and thermal IAEA regulatory test 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 thermal test, the specimen shall not be artificially cooled and any combustion of materials of the package shall be permitted to proceed naturally. Corresponding to results of the French institute IRSN combustion and smouldering of wood inside the impact limiter occurred during and after the fire test. An additional energy supply from a pre-damaged impact limiter to the cask could be the consequence for the safety assessment of the containment. 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. BAM is in the preparation process for a second test phase. A thermal test will take place with a wood filled test specimen weighing about 2Mg. T2 - The 18th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2016) CY - Kobe, Japan DA - 18.09.2016 KW - Large scale testing KW - Fire test KW - Impact limiter KW - Shock absorber KW - Thermal test KW - Typ-B KW - Wood KW - Smouldering PY - 2016 SP - paper no. 1011 AN - OPUS4-37854 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin A1 - Erenberg, Marina A1 - Nehrig, Marko A1 - Bletzer, Claus A1 - Musolff, André A1 - Schönfelder, Thorsten A1 - Wille, Frank T1 - Behavior of wood filled impact limiters during the IAEA thermal test 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 that transport casks meet the IAEA safety requirements. After damage caused by the mechanical tests the package has to withstand a severe fire scenario. It is required that the mechanical tests have to produce maximum damage, taking into account the thermal test. Furthermore, any damage, which would give rise to increased radiation or loss of containment or affect the confinement system after the thermal test, should be considered. Concerning the thermal test, the IAEA safety requirements state that 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. Different works from the French Institute for Radiological Protection and Nuclear Safety (IRSN) and BAM show that additional energy supply from a pre-damaged impact limiter to the cask could occur caused by smoldering of the wood. This effect should be considered within the safety assessment of the package. A heat wave from the fire could overlap with the additional energy from the impact limiter in the sealing system. In 2015 BAM conducted small scale fire tests with wood filled metal drums showing continuing combustion processes during the cooling down phase. As not much is known about smoldering processes in wood filled impact limiters, it is highly complex to define pre-damage of impact limiters, which are conservative, regarding the most damaging energy flow from the impact limiter to the containment system in dependence of time. More research has to be done to develop models to examine the effects of smoldering impact limiters on the containment of packages for the assessment. The process of smoldering is described with regard to the requirements in the thermal safety assessment. Parameters influencing the smoldering process are identified. BAM operates test facilities to examine the issue of mechanical damage, combustion and heat transfer of packages for transport of radioactive material. A thermal test will take place with a wood filled test specimen with a diameter of about 2.3 meters. The aim is to understand the phenomena of smoldering under the consideration of relevant regulatory boundary conditions. T2 - ASME 2017 Pressure Vessels and Piping Conference (PVP2017) CY - Waikoloa, Hawaii, USA DA - 16.07.2017 KW - Fire test KW - Wood KW - IAEA KW - Smoldering KW - Smouldering KW - Shock absorber KW - Thermal test KW - Combustion KW - Impact limiter PY - 2017 SN - 978-0-7918-5802-8 VL - 7 SP - Article UNSP V007T07A038, 1 EP - 9 AN - OPUS4-43172 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Erenberg, Marina A1 - Bletzer, Claus A1 - Feldkamp, Martin A1 - Musolff, André A1 - Nehrig, Marko A1 - Wille, Frank T1 - Experimental investigations of the burning behaviour of transport package impact limiters and of fire spread impact onto the cask N2 - Accident safe packages for the transport of spent nuclear fuel and high-level waste shall fulfil international IAEA safety requirements. Compliance is shown by consecutive mechanical and thermal testing. Additional numerical analysis are usually part of the safety evaluation. For damage protection some package designs are equipped with wood filled impact limiters encapsulated by steel sheets. The safety of these packages is established in compliance with IAEA regulations. Cumulative mechanical and fire tests are conducted to achieve safety standards and to prevent loss of containment. Mechanical reliability is proven by drop tests. Drop testing might cause significant damage of the impact limiter steel sheets and might enable sufficient oxygen supply to the impact limiter during the fire test to ignite the wood filling. The boundary conditions of the fire test are precisely described in the IAEA regulatory. During the test the impact limiter will be subjected to a 30 minute enduring fire phase. Subsequent to the fire phase any burning of the specimen has to extinguish naturally and no artificial cooling is allowed. At BAM a large-scale fire test with a real size impact limiter and a wood volume of about 3m3 was conducted to investigate the burning behaviour of wood filled impact limiters in steel sheet encapsulation. The impact limiter was equipped with extensive temperature monitoring equipment. Until today burning of such impact limiters is not sufficiently considered in transport package design and more investigation is necessary to explore the consequences of the impacting fire. The objective of the large scale test was to find out whether a self-sustaining smouldering or even a flaming fire inside the impact limiter was initiated and what impact on the cask is resulting. The amount of energy, transferred from the impact limiter into the cask is of particular importance for the safety of heavy weight packages. With the intention of heat flux quantification a new approach was made and a test bench was designed. T2 - ASME 2018 Pressure Vessels and Piping Conference CY - Prague, Czech Republic DA - 15.07.2018 KW - Shock absorber KW - Impact limiter KW - Wood KW - Thermal testing KW - Fire KW - Smoldering KW - IAEA KW - Fire test PY - 2018 SN - 978-0-7918-5170-8 VL - PVP2018 SP - 84714-1 EP - 84714-10 AN - OPUS4-46984 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Linnemann, Konrad A1 - Nehrig, Marko A1 - Musolff, André A1 - Wille, Frank T1 - Experience by BAM in the transport package safety assessment of German waste containers N2 - Transport and storage containers for low and midlevel radioactive waste are getting more and more of relevance due to the nuclear phase out decision in 2011. For higher activities Type B(U) approved waste containers will be needed for the shut down and dismantling phases of NPPs. It is expected that large quantities are required in the near future. German waste containers are generally approved for transport and interim storage and are also intended for the final disposal in the Konrad repository. BAM is involved in the authority licensing of transport package designs in Germany. In this context, BAM is responsible for the assessment of safe containment, mechanical, thermal and quality management issues. BAM also operates test facilities and performs drop as well as thermal tests during package licensing procedures. This paper summarizes our experience in the transport package design assessment of Type B(U) waste containers. A general overview of the approval process, the requirements and approaches BAM applies are described. Some examples are used to illustrate different aspects and technical issues we are addressing during the package assessment. In the first part of the paper the specific design aspects of German waste containers are described. Here, a general overview is given e.g. about closure systems, impact limiter designs, and the handling concepts. Furthermore, the wide range of radioactive content and their physical behavior including the impact on the packages assessment are described. The second part is focused on questions about the licensing and assessment process of German waste containers from the BAM authority point of view. The general approaches for the strategy of demonstration are outlined on the basis of the test conditions according to IAEA Regulations SSR-6. Furthermore, particular issues of the mechanical and thermal assessment with respect to the specific test conditions are discussed. For accident conditions of transport, aspects to be mentioned are e.g. the assessment of the lid bolts, the axial gap applied between content and lid, and the thermal behavior of the wood filled impact limiter after the fire test. However, issues of the assessment for routine and normal conditions of transport are addressed in this paper, too. The intention of this paper is introduce recent approval procedure experience in Germany, describing technical evaluation issues and so reduce rounds of questions during applications. T2 - 2018 WM Symposia CY - Phoenix, AZ, USA DA - 18.03.2018 KW - Transport packages KW - Safety assessment KW - Lowlevel and midlevel radioactive waste PY - 2018 SP - Paper 18469, 1 EP - 10 AN - OPUS4-44861 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko T1 - Large Scale IAEA Thermal Test with Wood filled Impact Limiters N2 - Packages for the transport of radioactive material are often equipped with impact limiters consisting of wood. Mostly this wood is encapsulated by steel sheets. The impact limiters are needed to ensure that the transport casks meet the IAEA safety requirements. According to the IAEA safety requirements a package has to withstand consecutively severe mechanical tests followed by a thermal test. The mechanical tests have to produce maximum damage concerning the thermal test. Following this, the impact limiters may have serious pre-damage when the thermal tests begins. The IAEA safety requirements state that 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. Small scale fire tests with wood filled metal drums by BAM and works of the French Institute for Radiological Protection and Nuclear Safety (IRSN) showed that pre-damaged steel encapsulated wooden structures could start smoldering initiated by the thermal test. These processes supply additional energy to the cask which should be considered within the safety assessment of the package. As not much is known about smoldering processes in encapsulated wooden structures with a reduced oxygen supply the need for a test was identified. To investigate the influence of a smoldering impact limiter concerning the amount of energy supplied to the cask in dependence of the time BAM conducted a large scale impact limiter thermal test. For that, a pre-damaged impact limiter with a diameter of 2,3 m was mounted on a water tank simulating a cask. A complex system of a regulated pump, a heater, a cooler, a slide valve, a flow meter and numerous thermocouples were installed and connected to a control unit to ensure all needed operating conditions. After a pre-heating compared to typical SNF decay-heat, the 30 min lasting fire phase of the thermal test was started. After that, the expected and initiated smoldering began. The results of the large scale test are presented in this poster. Systematic small scale tests will follow to identify the influence of different parameters, e.g. moisture content and scale effects. The tests took place at BAM Test Site for Technical Safety (TTS) with its various possibilities for mechanical and thermal tests. The results of these tests will have direct influence in the safety assessment of transport cask for the transport of radioactive material. T2 - SNL BAM Workshop CY - Albuquerque, NM, USA DA - 14.03.2018 KW - Type-B Package KW - Thermal Test PY - 2018 AN - OPUS4-45313 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CHAP A1 - Nehrig, Marko A1 - Wille, Frank ED - Saegusa, Toshiari ED - Sert, Gilles ED - Völzke, Holger ED - Wille, Frank T1 - Internal Pressure build-up of Waste Packages with Wet Contents Under Fire Impact N2 - Intermediate level waste often contains residual water or other liquids. The liquids can be decomposed due to radiolysis and can also vaporize especially under fire impact. These pressure generating processes are described. One example for the pressure determination inside a closed cask is discussed using two different approaches: analytical and CFD KW - Wet Content KW - Pressure build-up KW - Type-B Package PY - 2018 SN - 978-981-3234-03-1 SP - 195 EP - 209 PB - World Scientific Publishing CY - Singapore ET - Erste AN - OPUS4-45301 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko T1 - Large Scale IAEA Thermal Test with Wood filled Impact Limiters N2 - Packages for the transport of radioactive material are often equipped with impact limiters consisting of wood. Mostly this wood is encapsulated by steel sheets. The impact limiters are needed to ensure that the transport casks meet the IAEA safety requirements. According to the IAEA safety requirements a package has to withstand consecutively severe mechanical tests followed by a thermal test. The mechanical tests have to produce maximum damage concerning the thermal test. Following this, the impact limiters may have serious pre-damage when the thermal tests begins. The IAEA safety requirements state that 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. Small scale fire tests with wood filled metal drums by BAM and works of the French Institute for Radiological Protection and Nuclear Safety (IRSN) showed that pre-damaged steel encapsulated wooden structures could start smoldering initiated by the thermal test. These processes supply additional energy to the cask which should be considered within the safety assessment of the package. As not much is known about smoldering processes in encapsulated wooden structures with a reduced oxygen supply the need for a test was identified. To investigate the influence of a smoldering impact limiter concerning the amount of energy supplied to the cask in dependence of the time BAM conducted a large scale impact limiter thermal test. For that, a pre-damaged impact limiter with a diameter of 2,3 m was mounted on a water tank simulating a cask. A complex system of a regulated pump, a heater, a cooler, a slide valve, a flow meter and numerous thermocouples were installed and connected to a control unit to ensure all needed operating conditions. After a pre-heating compared to typical SNF decay-heat, the 30 min lasting fire phase of the thermal test was started. After that, the expected and initiated smoldering began. The results of the large scale test are presented in this poster. Systematic small scale tests will follow to identify the influence of different parameters, e.g. moisture content and scale effects. The tests took place at BAM Test Site for Technical Safety (TTS) with its various possibilities for mechanical and thermal tests. The results of these tests will have direct influence in the safety assessment of transport cask for the transport of radioactive material. T2 - 2018 WM Symposia CY - Phoenix, AZ, USA DA - 18.03.2018 KW - Type-B Package KW - Accident Conditions of Transport KW - Thermal Test PY - 2018 AN - OPUS4-45310 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko A1 - Erenberg, Marina A1 - Feldkamp, Martin A1 - Bletzer, Claus A1 - Musolff, André A1 - Wille, Frank T1 - Large Scale IAEA Thermal Test with Wood filled Impact Limiters N2 - Packages for the transport of radioactive material are often equipped with impact limiters consisting of wood. Mostly this wood is encapsulated by steel sheets. The impact limiters are needed to ensure that the transport casks meet the IAEA safety requirements. According to the IAEA safety requirements a package has to withstand consecutively severe mechanical tests followed by a thermal test. The mechanical tests have to produce maximum damage concerning the thermal test. Following this, the impact limiters may have serious pre-damage when the thermal tests begins. The IAEA safety requirements state that 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. Small scale fire tests with wood filled metal drums by BAM and works of the French Institute for Radiological Protection and Nuclear Safety (IRSN) showed that pre-damaged steel encapsulated wooden structures could start smoldering initiated by the thermal test. These processes supply additional energy to the cask which should be considered within the safety assessment of the package. As not much is known about smoldering processes in encapsulated wooden structures with a reduced oxygen supply the need for a test was identified. To investigate the influence of a smoldering impact limiter concerning the amount of energy supplied to the cask in dependence of the time BAM conducted a large scale impact limiter thermal test. For that, a pre-damaged impact limiter with a diameter of 2,3 m was mounted on a water tank simulating a cask. A complex system of a regulated pump, a heater, a cooler, a slide valve, a flow meter and numerous thermocouples were installed and connected to a control unit to ensure all needed operating conditions. After a pre-heating compared to typical SNF decay-heat, the 30 min lasting fire phase of the thermal test was started. After that, the expected and initiated smoldering began. The results of the large scale test are presented in this poster. Systematic small scale tests will follow to identify the influence of different parameters, e.g. moisture content and scale effects. The tests took place at BAM Test Site for Technical Safety (TTS) with its various possibilities for mechanical and thermal tests. The results of these tests will have direct influence in the safety assessment of transport cask for the transport of radioactive material T2 - 2018 WM Symposia CY - Phoenix, AZ, USA DA - 18.03.2018 KW - Type-B Package KW - Thermal Test PY - 2018 SP - Paper 18257, 1 EP - 11 AN - OPUS4-45311 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko T1 - Wood Filled Shock Absorber under Thermal Test Conditions - Future Investigations - T2 - IRSN/BAM-Workshop about fire testing CY - Paris, France DA - 2015-04-13 PY - 2015 AN - OPUS4-33144 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Sterthaus, Jens A1 - Ballheimer, Viktor A1 - Bletzer, Claus Wilhelm A1 - Linnemann, Konrad A1 - Nehrig, Marko A1 - Wille, Frank T1 - Numerical approach for containment assessment of transport packages under regulatory thermal test conditions N2 - The requirements of the IAEA safety standards for Type B(U) packages include the thermal test as part of test sequences that represents accident conditions of transport. In comparison to mechanical tests, e.g., 9 m drop onto an unyielding target with short impact durations in a range of approximately 10 ms to 30 ms, the extended period of 30 min is defined in regulations for exposure of a package to a fire environment. Obviously, the required containment capability of the package has to be ensured not only after completing the test sequence but also over the course of the fire test scenario. Especially, deformations in the sealing area induced by the non-uniform thermal dilation of the package can affect the capability of the containment system. Consequently, thermo-mechanical analyses are required for the assessment. In this paper some aspects of finite element analysis (FEA) of transport packages with bolted closure systems under thermal loading are discussed. A generic FE model of a cask is applied to investigate the stress histories in the bolts, lid, and cask body as well as the deformations in the sealing area and the compression conditions of the gasket. Based on the parameter variations carried out, some recommendations in regard to modeling technique and results interpretation for such kind of analyses are finally given. T2 - PVP2014 - ASME 2014 Pressure vessels & piping division conference CY - Anaheim, CA, USA DA - 20.07.2014 KW - Transport packages KW - Containment KW - Thermo-mechanical analyses KW - FEA KW - Gasket PY - 2014 SN - 978-0-7918-4600-1 DO - https://doi.org/10.1115/PVP2014-28199 VL - 3 SP - 28199, 1 EP - 14 AN - OPUS4-32349 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko T1 - Thermal Test Driven Pressure Build-up Inside Type-B Packages Containing Weg Rdioactive Waste T2 - 17th International Symposium on the Packaging and Transport of Radioactive Materials (PATRAM 2013) CY - San Francisco, CA, USA DA - 2013-08-18 PY - 2013 AN - OPUS4-30275 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko A1 - Feldkamp, Martin A1 - Bletzer, Claus Wilhelm A1 - Wille, Frank T1 - Thermal test driven pressure build-up inside type-B packages containing wet radioactive waste N2 - In recent years several German approval procedures for ductile cast iron transport containers containing wet intermediate level waste were conducted. BAM, as one of the German competent authorities, was involved in the complex design assessment work with this specific issue. Thermal analysis is one part of the authority assessment work done by BAM in Germany. The radioactive contents of package designs which were not dried, only drained, consist of saturated ion exchange resin and a small amount of free water. Compared to the safety assessment of packages with dry content, attention must be paid to some more specific points. The most interesting point, however, is the pressure build-up inside the package due to vaporization. This could be caused by radiolysis of the liquid and must be taken into account for the storage period. The inner pressure of the package leads to mechanical loads to the package body, the lid and the lid bolts. Thus, the pressure is the driving force on the gasket system regarding the activity release and a possible loss of tightness. The paper deals primarily with the pressure build-up inside the package caused by the transport regulatory thermal test (30 min at 800 °C) as part of the cumulative test scenario under accident conditions of transport. The pressure build-up is estimated by calculation in a very conservative way regarding conduction and heat radiation. Furthermore the paper discusses a conservative approach for the estimation of the resulting pressure depending on the percentage of water inside the cask. To get trustworthy results without an exact specification of the content, experimental fire tests should be conducted. However, this paper shows the difficulties of assessing casks containing wet content. From the authority assessment point of view, drying of the content could be an effective way to avoid the above described pressure build-up and the associated difficulties for the safety assessment. T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 18.08.2013 KW - Type-B KW - Wet content KW - Pressure build-up KW - Radioactive waste KW - Thermal test PY - 2013 SP - Paper 108, 1 EP - 10 PB - Omnipress AN - OPUS4-30197 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin A1 - Erenberg, Marina A1 - Nehrig, Marko A1 - Bletzer, Claus A1 - Musolff, André A1 - Wille, Frank A1 - Schönfelder, Thorsten T1 - Aspects of assessment of packages with wood filled impact limiters during fire tests 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 that the transport casks meet the mechanical and thermal IAEA regulatory test requirements. According to the accident conditions of transport it is mandatory to expose the specimens to a cumulative effect by mechanical and thermal impacts. The mechanical tests consist of a free drop from 9 m onto a flat unyielding target and a 1 m drop onto a puncture bar. After damage caused by mechanical test sequences the package has to withstand a severe fire scenario. Corresponding to the IAEA advisory material it is required that the impact attitudes for the 9 m drop test and for the puncture test have to be such as to produce maximum damage, taking into account the thermal test. Moreover, any damage, which would give rise to increased radiation or loss of containment or affect the confinement system after the thermal test, should be considered. During and following the thermal test, the specimen shall not be artificially cooled and any combustion of materials of the package shall be permitted to proceed naturally. Different works from the French Institute for Radiological Protection and Nuclear Safety (IRSN) and BAM show that additional energy supply from a pre-damaged impact limiter to the cask could occur. This effect should be considered within the safety assessment of the containment. Thermal effects at the closure system of the cask, which might result in an elevated activity release, have to be excluded. BAM conducted small scale tests with wood filled metal buckets showing continuing combustion processes during the cooling down phase. These test results are presented. As not much is known about smouldering processes in wood filled impact limiters, it is highly complex to define pre-damage of impact limiters, which are conservative, regarding the maximum damaging energy flow from the impact limiter to the containment system. More research has to be done to develop models to examine the effects of smouldering impact limiters on the containment of packages for the transport of radioactive material. Aspects of assessment and its difficulties are shown. BAM as a competent authority for the approval of transport casks for radioactive material in Germany operates the test facilities to examine the issue of mechanical damage, combustion and heat transfer for such kind of package systems. For this purpose the knowledge from real drop tests with casks of a mass partly over 100 tons was transferred to a test application. A thermal test will take place with a wood filled test specimen with a diameter of about 2.3 meters. The aim is to understand the phenomena of smouldering under the consideration of relevant regulatory boundary conditions. The process of smouldering is described with regard to the requirements in the thermal assessment of safety of packages for the transport of radioactive material. Requirements concerning the pre-damage of packages for the maximum damage of impact limiters are discussed. Parameters influencing the smouldering process are identified. T2 - WM 2017 Conference CY - Phoenix, AZ, USA DA - 05.03.2017 KW - Fire test KW - Wood KW - Combustion KW - Smouldering KW - Smoldering KW - Impact limiter KW - Shock absorber KW - Thermal test KW - IAEA PY - 2017 SN - 978-0-9828171-6-2 SP - 1 AN - OPUS4-40157 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 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 - Nehrig, Marko T1 - Aspects of Gas Generation Caused by Residual Water inside ILW Packages T2 - Ramtrans 2015 10th International Conference on Radioactive Materials Transport and Storage CY - Oxford, UK DA - 2015-05-19 PY - 2015 AN - OPUS4-33450 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 - JOUR A1 - Pham-Van, S. A1 - Hinkelmann, R. A1 - Nehrig, Marko A1 - Martinez, I. T1 - A comparison of model concepts and experiments for seepage processes through a dike with a fault zone N2 - eepage processes through a dike with a fault zone on the landside and on the seaside are numerically and experimentally investigated. The numerical simulation is based on a two-phase (water-gas) flow model concept for porous media. Different discrete model concepts accounting for the fault zones are compared among each other and with the experiments. A good agreement between experimental and numerical results was obtained when the fault zones were discretized with 1D elements or with highly resolved 2D elements. We generally recommend choosing 1D elements. When the fault zone is modeled as an open pipe, the seepage velocity is considerably overestimated. Concerning dike stability, a fault zone on the landside is much worse compared to a fault zone on the seaside. KW - Fault zones KW - Fractured-porous media KW - Water-gas flow KW - Numerical modelling KW - Dike PY - 2011 DO - https://doi.org/10.1080/19942060.2011.11015359 SN - 1997-003X SN - 1994-2060 VL - 5 IS - 1 SP - 149 EP - 158 PB - CSE Dept., the H.K. PolyU CY - Hong Kong AN - OPUS4-23281 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko A1 - Wille, Frank A1 - Quercetti, Thomas A1 - Masslowski, Jörg-Peter A1 - Droste, Bernhard A1 - Pope, R. T1 - Historical view and experiences with the crush test for light weight packages T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Crush test KW - IAEA regulations KW - Type-B PY - 2010 SP - 1 EP - 8(?) AN - OPUS4-23303 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko T1 - Historical view and experiences with the crush test for light weight packages T2 - 16th International Symposium on the Packaging and Transport of Radioactive Materials PATRAM CY - London, England DA - 2010-10-03 PY - 2010 AN - OPUS4-23334 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Nehrig, Marko A1 - Wille, Frank A1 - Quercetti, Thomas A1 - Masslowski, Jörg-Peter A1 - Droste, Bernhard A1 - Pope, R. T1 - Historical view and experiences with crush test for light weight packages N2 - The crush test for light weight and low density type B packages was introduced for the first time into the 1985 edition of the International Atomic Energy Agency (IAEA) transport safety regulations. In the early 1970s, the need for an additional mechanical test besides or instead of the well known 9 m drop test was deliberated. Various authors and test facilities, including BAM and Sandia National Laboratories (SNL), were able to prove that the level of safety provided by IAEA drop and puncture tests in the regulations did not protect against dynamic crush forces to smaller packages. As early as the third PATRAM symposium held in 1971 (Richland, WA, USA), Robert F. Barker asked for '... a more strenuous crushing test for protecting small, light weight packages ...' BAM developed from research activities a proposal as to which types of packages should be subject to crush tests and how the crush tests should be performed, which was presented at the 5th PATRAM symposium held in 1978 (Las Vegas, NV, USA). At the IAEA, the possible need for a crush test was first mentioned in 1977. The subject for a discussion, besides the principal need for this test, was also the development of suitable set of crush test boundary conditions. It took more than four years of discussion until a dynamic crush test similar to today's test was recommended by experts to the IAEA regulatory revision panel. Finally, after a rigorous evaluation process in which also the boundary conditions were determined, the crush test was proposed to be incorporated into the IAEA regulations. BAM and SNL participated in the crush test development and implementation process right from the beginning in the early 1970s until its implementation in the IAEA regulations in 1985. Today, BAM performs crush test procedures according to para. 727(c) of TS-R-1, which have not been changed since their first implementation. Crush tests performed in 2002 at BAM will be discussed. These approval design tests were performed on birdcage pellet transport containers under normal and accident conditions according to the IAEA regulations. KW - Package testing KW - Crush testing KW - Regulations PY - 2011 DO - https://doi.org/10.1179/1746510911Y.0000000016 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 22 IS - 3 SP - 125 EP - 129 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-25349 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko A1 - Bletzer, Claus Wilhelm A1 - Wille, Frank T1 - Pressure build-up inside packages containing wet intermediate level radioactive waste due to thermal loads N2 - Over the last years several transport approval procedures were finished for ductile cast iron containers containing wet intermediate level waste. BAM was involved in the assessment of mechanical and thermal aspects, activity release and material and component behavior regarding fulfillment of the regulatory requirements. The radioactive contents of these package designs which were not dried, only drained, consist of saturated ion exchange resin and a small amount of free water. Regarding wet contents, the most interesting point, however, is the pressure build-up inside the package due to vaporization. This could be aused by radiolysis of the liquid and must be taken into account for the storage period. The paper deals primarily with the pressure build-up inside the package aused by the regulatory thermal test (30 min at 800°C) as part of the cumulative test scenario under accident conditions of transport. The pressure build-up is estimated by calculation in a very conservative way regarding conduction and heat radiation. To get trustworthy results without an exact specification of the content, physical fire tests should be conducted. This paper will result in the strong advice, that contents should be dried to ensure a positive outcome of the safety assessment. T2 - ASME 2012 Pressure vessels & piping division conference CY - Toronto, Ontario, Canada DA - 15.07.2012 KW - Radioactive material KW - Pressure build-up KW - Wet intermediate level waste PY - 2012 SP - PVP2012-78282, 1-6 PB - American Society of Mechanical Engineers CY - New York AN - OPUS4-26321 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko T1 - Safety Assessment Aspects of Type-B(U) Packages Containing Wet Intermediate Level Waste T2 - RAMTRASNPORT 2012 CY - London, England DA - 2012-05-22 PY - 2012 AN - OPUS4-26325 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko T1 - Pressure build-up Inside Packages Containing Wet Intermediate Level Radioactive Waste due to Thermal Loads T2 - ASME PVP 2012 CY - Toronto, Canada DA - 2012-07-15 PY - 2012 AN - OPUS4-26327 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Feldkamp, Martin A1 - Nehrig, Marko A1 - Bletzer, Claus Wilhelm A1 - Wille, Frank T1 - Pressure build-up during the fire test in type B(U) packages containing water - 13280 N2 - The safety assessment of packages for the transport of radioactive materials with content containing liquids requires special consideration. The main focus is on water as supplementary liquid content in Type B(U) packages. A typical content of a Type B(U) package is ion exchange resin, waste of a nuclear power plant, which is not dried, normally only drained. Besides the saturated ion exchange resin, a small amount of free water can be included in these contents. Compared to the safety assessment of packages with dry content, attention must be paid to some more specific issues. An overview of these issues is provided. The physical and chemical compatibility of the content itself and the content compatibility with the packages materials must be demonstrated for the assessment. Regarding the mechanical resistance the package has to withstand the forces resulting from the freezing liquid. The most interesting point, however, is the pressure build-up inside the package due to vaporization. This could for example be caused by radiolysis of the liquid and must be taken into account for the storage period. If the package is stressed by the total inner pressure, this pressure leads to mechanical loads to the package body, the lid and the lid bolts. Thus, the pressure is the driving force on the gasket system regarding the activity release and a possible loss of tightness. The total pressure in any calculation is the sum of partial pressures of different gases which can be caused by different effects. The pressure build-up inside the package caused by the regulatory thermal test (30 min at 800 deg. C), as part of the cumulative test scenario under accident conditions of transport is discussed primarily. To determine the pressure, the temperature distribution in the content must be calculated for the whole period from beginning of the thermal test until cooling-down. In this case, while calculating the temperature distribution, conduction and radiation as well as evaporation and condensation during the associated process of transport have to be considered. This paper discusses limiting amounts of water inside the cask which could lead to unacceptable pressure and takes into account saturated steam as well as overheated steam. However, the difficulties of assessing casks containing wet content will be discussed. From the authority assessment point of view, drying of the content could be an effective way to avoid the above described pressure build-up and the associated difficulties for the safety assessment T2 - WM2013 Conference CY - Phoenix, Arizona, USA DA - 24.02.2013 KW - Fire test KW - B(U) KW - Thermal test KW - Pressure KW - Water PY - 2013 SN - 978-0-9836186-2-1 SP - 1 EP - 12(?) CY - Phoenix, Arizona, USA AN - OPUS4-27997 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Bletzer, Claus Wilhelm A1 - Nehrig, Marko A1 - Feldkamp, Martin A1 - Wille, Frank A1 - Völzke, Holger T1 - Druckaufbau in Behältern mit feuchtem Inventar N2 - Beim Betrieb von Kernkraftwerken fallen kontaminierte feuchte Abfallstoffe, wie z. B. Ionenaustauscherharze an, die in Transport- und Lagerbehältern der Entsorgung zugeführt werden. In Deutschland ist die BAM die zuständige Behörde für die Bauartprüfung von Typ B-Versandstücken. Im Zulassungsverfahren wird die Einhaltung der Schutzziele solcher Verpackungen überprüft. Basis für die Bewertung sind hierbei nationale und internationale gesetzliche Grundlagen sowie Regularien, welche in direkter Linie auf den IAEA SSR-6 [1] basieren. Die BAM ist ebenfalls im Rahmen einer Verwaltungsvereinbarung durch das BfS mit der Behälterbauartprüfung sowie der Beurteilung der qualitätssichernden Maßnahmen auf Grundlage von Kapitel 7 in [3] beauftragt. Typ-B(U) Verpackungen dienen zur Aufnahme verschiedenster radioaktiver oder radioaktiv kontaminierter Inhalte wie Brennelemente, Core-Bauteile, Rückbaurückstände oder belasteter Reinigungs- und Hilfsstoffe. In den meisten Fällen werden trockene bzw. getrocknete Inhalte verpackt. Potentiell feuchte oder nasse Inhalte wie z.B. Verdampferkonzentrate werden oftmals innerhalb der Verpackung getrocknet und können somit als trockene Inhalte behandelt werden. Beladene Ionenaustauscherharze werden i.d.R. mittels Transportwasser in die Verpackung eingespült und nur entwässert, aber nicht getrocknet. Die BAM war bereits in verschiedenen Zulassungsverfahren für Behälter mit feuchtem radioaktivem Inventar involviert. Bezüglich des Konrad Endlagers sind solche Verpackungen für feuchte, nicht Wärme entwickelnden Inhalte in der Regel als „Störfallfest verpackte Abfälle der Abfallbehälterklasse II [ABK II] mit spezifizierter Leckrate“ klassifiziert. In diesem Beitrag soll direkt Bezug zu den thermischen Prüfungen genommen werden. Im Transportfall sind hierbei die Unfallbeförderungsbedingungen zu unterstellen, die neben den mechanischen Prüfungen ein den Behälter vollständig einhüllendes Feuer von mindestens 800°C über 30 Minuten sowie der notwendigen Abkühldauer vorschreiben. Für eine geplante Endlagerung der Behälter ist im Zuge der Endlager-Bauartprüfung eine Branddauer von 60 Minuten mit nachfolgender 24-stündiger Abkühlphase unter abweichenden Randbedingungen gegenüber den verkehrsrechtlichen Regelwerksanforderungen zu beachten ([2] Kap. 5.3.). Bei einer möglichen Vorgehensweise zur Bestimmung des Druckaufbaus in einem Behälter aus den vorgeschriebenen Feuertests wird zuerst die Temperaturverteilung im Inhalt über den Zeitraum des Brands sowie der Abkühlphase berechnet. Der hier betrachtete Inhalt, der lediglich entwässert, aber nicht getrocknet ist, besteht sowohl aus gesättigtem Ionenaustauscherharz als auch aus einem geringen Anteil an freiem Wasser. Die Verdampfung von Wasser ist dabei ein kritischer Prozess der zum Druckaufbau im Behälter führt. Zur Einschätzung der aus dem thermischen Lastfall resultierenden Beanspruchungen des Behälters bis hin zur Gefährdung seiner Dichtheit und Integrität können sowohl rechnerische, als auch experimentelle Methoden Anwendung finden. Während sich die durch eine Brandbeanspruchung einstellenden Temperaturen in der Verpackung relativ genau berechnen lassen, erweist sich die Bestimmung der Temperatur- und Druckverteilung im Inventar aufgrund des komplexen thermischen und strömungsdynamischen Verhaltens als Herausforderung. Dabei ist der Wärmeübergang von der Behälterinnenwand in das Inventar sowie das thermische Verhalten des Inventars als inhomogen zu erhitzendes Gemisch aus Feststoffen, Fluiden (z.B. Wasser) und Gasen sehr komplex. Diese Vorgänge bestimmen jedoch den resultierenden und für die Sicherheitsbewertung maßgebenden Druckaufbau im Behälterinnenraum. Unter Berücksichtigung von Konvektion, Wärmeleitung und -strahlung werden thermische Zustände für den gewählten generischen Behälter aufgezeigt und die Effekte hinsichtlich Verdampfung und Druckaufbau erklärt. Anschließend werden zwei Ansätze zur Bestimmung des Partialdrucks durch Verdampfung im Behälter aufgezeigt. Para 663 und Para 664 der IAEA SSR-6 [1] der Transportbedingungen besagen, das - je nach Auslegung - der Feuertest bereits mit einem Innendruck von bis zu 700 kPa begonnen wird. Die beim Feuertest entstehenden Überdrücke müssen dann zum max. Auslegungsdruck hinzugefügt werden und der Behälter muss den Nachweis der Integrität mit den durch die Hitze reduzierten Werkstoffkennwerten des Behälters (Körper, Deckel, Verschlusssystem, Dichtung) nach der Vorschädigung durch die mech. Unfalltests erbringen. Bezüglich der Endlagerung besagt die Endlagerungsbestimmung [3] in Kap. 7.1.4.2.4, dass das “…Abfallprodukt so beschaffen sein muss, das bei der gemäß Unterkapitel 7.1.5.6 durchzuführenden thermischen Prüfung der maximal auftretende Innendruck 15 bar beträgt.”. T2 - KONTEC 2013 - 11. Internationales Symposium 'Konditionierung radioaktiverBetriebs- und Stilllegungsabfälle' CY - Dresden, Germany DA - 13.0,3.2013 KW - Druckaufbau KW - Radioaktive Abfälle KW - Endlager PY - 2013 IS - Sektion 4 / Vortrag 031 SP - 1 EP - 11 AN - OPUS4-28094 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Bletzer, Claus Wilhelm A1 - Nehrig, Marko A1 - Feldkamp, Martin A1 - Wille, Frank A1 - Völzke, Holger T1 - Pressure build up in casks containing wet waste T2 - KONTEC 2013 - 11. Internationales Symposium 'Konditionierung radioaktiverBetriebs- und Stilllegungsabfälle' CY - Dresden, Germany DA - 2013-03-13 KW - Pressure build up KW - Radioactive waste KW - Disposal PY - 2013 IS - Sektion 4 / Vortrag 031 SP - 1 EP - 10(?) AN - OPUS4-28095 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Nehrig, Marko A1 - Bletzer, Claus Wilhelm A1 - Wille, Frank T1 - Safety assessment aspects of type B(U) packages containing wet intermediate level waste N2 - In Germany, the mechanical and thermal safety assessment of approved packages for the transport of RAM is carried out by BAM as the competent authority according to the International Atomic Energy Agency regulations. BAM was involved in several approval procedures with ductile cast iron containers containing wet intermediate level waste. These contents, which are not dried, only drained, consist of saturated ion exchange resin and a small amount of free water. Compared to the safety assessment of packages with dry content, attention must be paid to some more specific points. The physical and chemical compatibility of the content itself and of the content with materials of the package must be shown. From the mechanical resistance point of view, the package has to withstand the forces resulting from the freezing liquid. The most interesting point, however, is the pressure build-up inside the package due to vapourisation. This could be caused by radiolysis of the liquid and must be taken into account for the storage period. The paper deals primarily with the pressure build-up inside the package caused by the regulatory thermal test (30 min at 800°C) as part of the cumulative test scenario under accident conditions of transport. To determine the pressure, the temperature distribution in the content must be calculated for the whole period from the beginning of the thermal test until cooling down. In this case, calculating the temperature distribution requires, besides the consideration of conduction and heat radiation, consideration of evaporation and condensation including the associated processes of transport. KW - Type B KW - Wet content KW - Pressure build-up KW - Vapourisation KW - Thermal test KW - Radioactive waste KW - Thermal analysis PY - 2012 DO - https://doi.org/10.1179/1746510913Y.0000000024 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 23 IS - 3-4 SP - 187 EP - 190 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-29935 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko A1 - Bletzer, Claus Wilhelm A1 - Wille, Frank T1 - Safety assessment aspects of type B(U) packages containing wet intermediate level waste N2 - In Germany, the mechanical and thermal safety assessment of approved packages for the transport of RAM is carried out by BAM as the competent authority according to the International Atomic Energy Agency regulations. BAM was involved in several approval procedures with ductile cast iron containers containing wet intermediate level waste. These contents, which are not dried, only drained, consist of saturated ion exchange resin and a small amount of free water. Compared to the safety assessment of packages with dry content, attention must be paid to some more specific points. The physical and chemical compatibility of the content itself and of the content with materials of the package must be shown. From the mechanical resistance point of view, the package has to withstand the forces resulting from the freezing liquid. The most interesting point, however, is the pressure build-up inside the package due to vapourisation. This could be caused by radiolysis of the liquid and must be taken into account for the storage period. The paper deals primarily with the pressure build-up inside the package caused by the regulatory thermal test (30 min at 800°C) as part of the cumulative test scenario under accident conditions of transport. To determine the pressure, the temperature distribution in the content must be calculated for the whole period from the beginning of the thermal test until cooling down. In this case, calculating the temperature distribution requires, besides the consideration of conduction and heat radiation, consideration of evaporation and condensation including the associated processes of transport. T2 - RAMTRANSPORT 2012 - 9th International Conference on the Radioactive Materials Transport and Storage CY - London, UK DA - 22.05.2012 KW - Radioactive materials KW - Safety assessment KW - Pressure build-up KW - Wet intermediate level waste PY - 2012 SP - 1 EP - 7 AN - OPUS4-26314 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -