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 - 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 - Bletzer, Claus Wilhelm T1 - Severe fire scenarios for radioactive waste storage packages T2 - Fire Science Workshop CY - Berlin, Germany DA - 2013-11-29 PY - 2013 AN - OPUS4-30974 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 - Bletzer, Claus Wilhelm T1 - Strategie zur Bestimmung von Temperaturen von Transport- und Lagerbehältern für radioaktive Stoffe T2 - Jahrestagung Kerntechnik 2010 CY - Berlin, Germany DA - 2010-05-04 PY - 2010 AN - OPUS4-21320 LA - deu 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 - Koch, Frank A1 - Bletzer, Claus Wilhelm A1 - Wieser, Günter T1 - Consideration of asymmetrical heat transmission and distribution using numerical methods T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 KW - Temperaturverteilung KW - CFD KW - FEA KW - Transportbehälter KW - Wärmeübergang PY - 2007 SP - 1 EP - 8 PB - Institute of Nuclear Materials Management AN - OPUS4-16131 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 - 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 T1 - Pressure Build Up in Casks Containing Wet Waste T2 - KONTEC 2013, 11. Internationales Symposium "Konditionierung radioaktiver Betriebs- und Stilllegungsabfälle" CY - Dresden, Germany DA - 2013-03-13 PY - 2013 AN - OPUS4-28014 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 - 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 -