TY - JOUR A1 - Apel, Andreas A1 - Ballheimer, Viktor A1 - Kuschke, Christian A1 - Schubert, Sven A1 - Wille, Frank T1 - Approach for use of acceleration values for packages of radioactive material under routine conditions of transport N2 - The most relevant source of reference for load cases of packages for the transport of radioactive material under routine conditions is Appendix IV of the International Atomic Energy Agency (IAEA) Advisory Material TS-G-1·1. The acceleration values given there leave many questions open and have to be agreed upon with the involved competent authorities. Consequently, the actual load cases applied for a safety analysis may differ widely and could cause problems for international transport. To avoid such difficulties, it seems obvious that the according passages in TS-G-1·1 should be modified with the objective of making the load case data more consistent for a harmonized application in the IAEA member states. Papers pointing out in this direction were discussed at the PATRAM 2010 conference. The way to improve the acceleration data may lie in investigations and measurements considering, for example different types of vehicles and package masses. However, what should be the goal of such kind of surveys? Can such investigation provide values for every worldwide load case possible under routine conditions of transport? In particular, the different designs of vehicles give a reason to doubt that such an aim is realistic. The approach in this paper is to show that a less ambitious aim is more effective. Therefore, an approximate scheme is preferred, which renders better assistance in determining the appropriate acceleration values. KW - Radioactive materials KW - Safety assessment KW - IAEA regulations KW - Load cases KW - Routine conditions of transport KW - IAEA advisory material TS-G-1.1 KW - Appendix IV KW - Revision of load case data KW - Acceleration values PY - 2013 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 24 IS - 2 SP - 55 EP - 59 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-30378 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Apel, Andreas A1 - Ballheimer, Viktor A1 - Kuschke, Christian A1 - Schubert, Sven A1 - Wille, Frank T1 - Approach for the use of acceleration values for packages of radioactive material under routine conditions of transport N2 - The most relevant source of reference for load cases of packages for the transport of radioactive material under routine conditions is Appendix IV of the International Atomic Energy Agency (IAEA) Advisory Material TS-G-1·1. The acceleration values given there leave many questions open and have to be agreed upon with the involved competent authorities. Consequently, the actual load cases applied for a safety analysis may differ widely and could cause problems for international transport. To avoid such difficulties, it seems obvious that the according passages in TS-G-1·1 should be modified with the objective of making the load case data more consistent for a harmonized application in the IAEA member states. Papers pointing out in this direction were discussed at the PATRAM 2010 conference. The way to improve the acceleration data may lie in investigations and measurements considering, for example different types of vehicles and package masses. However, what should be the goal of such kind of surveys? Can such investigation provide values for every worldwide load case possible under routine conditions of transport? In particular, the different designs of vehicles give a reason to doubt that such an aim is realistic. The approach in this paper is to show that a less ambitious aim is more effective. Therefore, an approximate scheme is preferred, which renders better assistance in determining the appropriate acceleration values. 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 - IAEA regulations KW - Lost cases KW - Routine conditions of transport PY - 2012 SP - 1 EP - 8 AN - OPUS4-26747 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Baer, Wolfram T1 - Recent Results on the Investigation of the Master Curve Concept for Ferritic Ductile Cast Iron N2 - Within the current framework for safety assessment of ferritic ductile cast iron (DCI) containers for transport as well as interim and final storage of radioactive materials, the IAEA guidelines SSG 26 apply fracture mechanics principles. Crack initiation in either, stable or unstable modes is generally forbidden. Additionally, for DCI, the ASME-Code, Sect. III, Div. 3, WC-2330, explicitly requires a safety proof regarding dynamic loading conditions. Nevertheless, corresponding information given in the ASME Code does not seem to be sufficient to appropriately perform a dynamic fracture mechanics safety assessment for DCI. To address and improve this status of the dynamic brittle fracture safety assessment framework for DCI, the application of the fracture mechanics master curve (MC) concept to DCI is being investigated in an ongoing joint research project (acronym MCGUSS) between BAM Berlin and MPA Stuttgart. For ferritic DCI, the MCGUSS project addresses the currently lacking systematic review of applicability and potential modifications to the assumptions and the procedure according to ASTM E1921. The aim is to establish a methodology to determine and assess dynamic fracture toughness values of DCI in the ductile-to-brittle transition regime using small samples extracted from a component. The research approach and the planned investigations were outlined in more detail earlier. This paper is focused on the discussion of recent experimental results to establish the dynamic fracture mechanics toughness data base and its MC analyses. MCGUSS fracture mechanics test setups and the dynamic fracture toughness data base achieved at the time of abstract submission is discussed (covering 128 specimens). Current application limits of ASTM E1921 MC to DCI are discussed, and planned investigations to further investigate and modify the MC procedure for DCI are outlined. T2 - ASTM 23rd International ASTM/ESIS Symposium on Fatigue and Fracture Mechanics CY - Atlanta, GA, USA DA - 12.11.2025 KW - Dynamic fracture toughness KW - Ductile cast iron KW - Safety assessment KW - Master curve KW - Statistics PY - 2025 AN - OPUS4-64746 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Baer, Wolfram T1 - Statistische Auswertung der SE(B)-Bruchzähigkeitsdatenbasis und Untersuchungen zum Bruchmechanismus - Neue Ergebnisse zur Untersuchung des Master Curve Konzepts für ferritisches Gusseisen mit Kugelgraphit bei dynamischer Beanspruchung (Projekt MCGUSS) N2 - Die Zielstellung des laufenden Kooperationsprojektes MCGUSS zwischen der BAM Berlin und der MPA Stuttgart ist es, das probabilistische Master Curve (MC)-Konzept hinsichtlich seiner Übertragbarkeit auf ferritisches Gusseisen mit Kugelgraphit (DCI) zu untersuchen. Über Teilergebnisse der Arbeiten wurde bereits auf den Jahrestagungen 2023 bis 2025 des DVM-AK Bruchmechanik und Bauteilsicherheit berichtet. Der vorliegende Beitrag hat zwei Schwerpunkte. Zum einen wurde die Datenbasis der dynamischen Bruchzähigkeit für SE(B)-Proben der Dicken 10 mm, 25 mm und 140 mm auf insgesamt 101 Versuche bei Temperaturen von -40 °C bis -140 °C erweitert, statistisch ausgewertet sowie MC-Analysen unterzogen. Die Ergebnisse zeigen, dass die Daten sich zwar mit einer Weibullverteilung gut beschreiben lassen, die MC-Methode nach ASTM E1921 jedoch nicht ohne Weiteres anwendbar ist, sondern Modifikationen erforderlich sind. Des Weiteren werden neue Ergebnisse zum werkstoffspezifischen Bruchmechanismus bei dynamischer Belastung im unteren Übergangsbereich der Zähigkeit diskutiert. Die fraktographische Datenbank wurde durch REM-Analysen weiterer Bruchflächen von SE(B)25-Proben bei -40 °C, -60 °C und -80 °C ergänzt. Die Ergebnisse unterstreichen die prägende Rolle, die Rissarrestereignissen im Verlauf des dynamischen Sprödbruchversagens bei DCI zukommt. Der in MCGUSS zur Erklärung eines gegenüber Stahl inversen Probengrößeneinflusses vorgeschlagene Mechanismus „Specimen size-dependent arrest of local brittle fractures before global brittle failure by weakest link“ wird dadurch weiter unterstützt. T2 - DVM-Jahrestagung 2026 des Arbeitskreises Bruchmechanik und Bauteilsicherheit CY - Stuttgart, Germany DA - 24.02.2026 KW - Dynamic fracture toughness KW - Ductile cast iron KW - Safety assessment KW - Master curve KW - Statistics PY - 2026 AN - OPUS4-65593 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Baer, Wolfram A1 - Ohm, Katrin A1 - Holzwarth, Marcel T1 - Statistische Auswertung der SE(B)-Bruchzähigkeitsdatenbasis und Untersuchungen zum Bruchmechanismus – neue Ergebnisse zur Untersuchung des Master Curve Konzepts für ferritisches Gusseisen mit Kugelgraphit bei dynamischer Beanspruchung (Projekt MCGUSS) N2 - Die Zielstellung des laufenden Kooperationsprojektes MCGUSS zwischen der BAM Berlin und der MPA Stuttgart ist es, das probabilistische Master Curve (MC)-Konzept hinsichtlich seiner Übertragbarkeit auf ferritisches Gusseisen mit Kugelgraphit (DCI) zu untersuchen. Über Teilergebnisse der Arbeiten wurde bereits auf den Jahrestagungen 2023 bis 2025 des DVM-AK Bruchmechanik und Bauteilsicherheit berichtet. Der vorliegende Beitrag hat zwei Schwerpunkte. Zum einen wurde die Datenbasis der dynamischen Bruchzähigkeit für SE(B)-Proben der Dicken 10 mm, 25 mm und 140 mm auf insgesamt 101 Versuche bei Temperaturen von -40 °C bis -140 °C erweitert, statistisch ausgewertet sowie MC-Analysen unterzogen. Die Ergebnisse zeigen, dass die Daten sich zwar mit einer Weibullverteilung gut beschreiben lassen, die MC-Methode nach ASTM E1921 jedoch nicht ohne Weiteres anwendbar ist, sondern Modifikationen erforderlich sind. Des Weiteren werden neue Ergebnisse zum werkstoffspezifischen Bruchmechanismus bei dynamischer Belastung im unteren Übergangsbereich der Zähigkeit diskutiert. Die fraktographische Datenbank wurde durch REM-Analysen weiterer Bruchflächen von SE(B)25-Proben bei -40 °C, -60 °C und -80 °C ergänzt. Die Ergebnisse unterstreichen die prägende Rolle, die Rissarrestereignissen im Verlauf des dynamischen Sprödbruchversagens bei DCI zukommt. Der in MCGUSS zur Erklärung eines gegenüber Stahl inversen Probengrößeneinflusses vorgeschlagene Mechanismus „Specimen size-dependent arrest of local brittle fractures before global brittle failure by weakest link“ wird dadurch weiter unterstützt. T2 - DVM-Jahrestagung 2026 des Arbeitskreises Bruchmechanik und Bauteilsicherheit CY - Stuttgart, Germany DA - 24.02.2026 KW - Statistics KW - Dynamic fracture toughness KW - Ductile cast iron KW - Master curve KW - Safety assessment PY - 2026 SP - 1 EP - 12 PB - DVM-Verlag CY - Berlin AN - OPUS4-65591 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Becker, Ben T1 - Statistical safety assessment of composite cylinders N2 - Statistical safety assessment of composite cylinders in terms of load cycle and burst testing. Showing the influence of test conditions and parameters on test results. Introduction into BAM – Tool for safety assessment. T2 - Fibremod Training unit #5 CY - Berlin, Germany DA - 05.10.2017 KW - Safety assessment KW - Statistics KW - Composite cylinder PY - 2017 AN - OPUS4-42497 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CHAP A1 - Droste, Bernhard ED - Sorenson, K.B. T1 - Packaging, transport, and storage of high-, intermediate-, and low-level radioactive wastes N2 - Radioactive wastes are generated by research and medicine (e.g., the use of radioisotopes), industrial use of radioisotopes (e.g., for nondestructive materials testing), different activities related to nuclear power plant (NPP) operations (e.g., mining of uranium and thorium ores, manufacturing of fuel assemblies, operational waste generation during NPP Operation), reprocessing of spent nuclear fuel, and dismantling of nuclear installations. KW - Packaging KW - Transport KW - Storage KW - Radioactive waste KW - Safety assessment PY - 2015 SN - 978-1-78242-309-6 SN - 978-1-78242-322-5 N1 - Serientitel: Woodhead publishing series in energy – Series title: Woodhead publishing series in energy IS - 78 SP - Chapter 15, 231 EP - 270 PB - Woodhead Publ. AN - OPUS4-33991 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Komann, Steffen A1 - Wille, Frank A1 - Rolle, Annette A1 - Probst, Ulrich A1 - Schubert, Sven T1 - Considerations of aging mechanisms influence on transport safety and reliability of dual purpose casks for spent nuclear fuel or HLW N2 - When storage of spent nuclear fuel (SNF) or high-level waste (HLW) is done in dual purpose casks (DPC), the effects of aging on safety relevant DPC functions and properties have to be managed in a way that a safe transport after the storage period of several decades is capable, and can be justified and certified permanently throughout that period. The effects of aging mechanisms (like e.g. radiation, different corrosion mechanisms, stress relaxation, creep, structural changes and degradation) on the transport package design safety assessment features have to be evaluated. The consideration of these issues in the DPC transport safety case will be addressed. Special attention is given to all cask components which cannot be directly inspected or changed without opening the cask cavity, what are the inner parts of the closure system and the cask internals, like baskets or spent fuel assemblies. The design criteria of that transport safety case have to consider the operational impacts during storage. Aging is not subject of technical aspects only, but also of 'intellectual' aspects, like changing standards, scientific/ technical knowledge development and personal as well as institutional alterations. Those aspects are to be considered in the management system of the license holders and in appropriate design approval update processes. The paper addresses issues which are subject of an actual IAEA TECDOC draft 'Preparation of a safety case for a dual purpose cask containing spent nuclear fuel'. T2 - PSAM 12 - Probabilistic safety assessment and management CY - Honolulu, Hawaii, USA DA - 22.06.2014 KW - Transport and storage casks for spent nuclear fuel or high level waste KW - Aging mechanisms KW - Corrosion KW - Safety assessment KW - Metal seals KW - Closure system KW - Spent fuel/high-level waste KW - Dual purpose casks KW - Metal seals reliability KW - Cesium corrosion PY - 2014 UR - http://psam12.org/proceedings/paper/paper_180_1.pdf SP - 1 EP - 10 AN - OPUS4-32518 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Komann, Steffen A1 - Wille, Frank A1 - Rolle, Annette A1 - Probst, Ulrich A1 - Schubert, Sven T1 - Consideration of aging mechanism influence on transport safety of dual purpose casks for spent nuclear fuel of HLW N2 - When storage of spent nuclear fuel or high level waste is carried out in dual purpose casks (DPC), the effects of aging on safety relevant DPC functions and properties have to be managed in a way that a safe transport after the storage period of several decades is capable and can be justified and certified permanently throughout that period. The effects of aging mechanisms (e.g. radiation, different corrosion mechanisms, stress relaxation, creep, structural changes and degradation) on the transport package design safety assessment features have to be evaluated. Consideration of these issues in the DPC transport safety case will be addressed. Special attention is given to all cask components that cannot be directly inspected or changed without opening the cask cavity, like the inner parts of the closure system and the cask internals, like baskets or spent fuel assemblies. The design criteria of that transport safety case have to consider the operational impacts during storage. Aging is not the subject of technical aspects only but also of ‘intellectual’ aspects, like changing standards, scientific/technical knowledge development and personal as well as institutional alterations. Those aspects are to be considered in the management system of license holders and in appropriate design approval update processes. The paper addresses issues that are subject of an actual International Atomic Energy Agency TECDOC draft 'Preparation of a safety case for a dual purpose cask containing spent nuclear fuel'. KW - Transport KW - Storage KW - Spent fuel KW - High-level waste KW - Aging KW - Metal seals KW - Transport and storage casks KW - Spent nuclear fuel KW - Aging mechanisms KW - Corrosion KW - Safety assessment PY - 2014 DO - https://doi.org/10.1179/1746510914Y.0000000070 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 25 IS - 3-4 SP - 105 EP - 112 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-33428 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gesell, Stephan T1 - WP8 - RCS standardisation work N2 - The presentation presents a first work premise for the acceptable failrate of a hydrogen pressure vessel. Based on this premise, the basic algorithm for the analysis of given acceptance criteria is presented. T2 - TAHYA PSB Meeting#1 CY - TU Chemnitz, Germany DA - 20.11.2018 KW - FCH JU KW - TAHYA KW - Horizon 2020 KW - Safety assessment PY - 2018 AN - OPUS4-47178 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -