Filtern
Erscheinungsjahr
Dokumenttyp
- Beitrag zu einem Tagungsband (132)
- Vortrag (38)
- Zeitschriftenartikel (25)
- Posterpräsentation (4)
- Buchkapitel (3)
- Monografie (1)
- Beitrag zu einem Sammelband (1)
Schlagworte
- Transport (26)
- Radioactive material (18)
- Impact limiter (17)
- Transport packages (14)
- Radioaktive Stoffe (12)
- Fire test (11)
- IAEA (11)
- Wood (10)
- Numerical analysis (9)
- Package (9)
- Safety assessment (9)
- Drop test (7)
- FEM (7)
- Numerische Analyse (7)
- Spent fuel (7)
- Thermal test (7)
- Ageing (6)
- Drop testing (6)
- Pressure build-up (6)
- Shock absorber (6)
- Spent nuclear fuel (6)
- Transport package (6)
- Dual purpose casks (5)
- Fire (5)
- Mechanische Bewertung (5)
- Drop tests (4)
- Dual purpose cask (4)
- Fallprüfungen (4)
- Fuel rods (4)
- High burn-up (4)
- IAEA regulations (4)
- Interim storage (4)
- Leakage rate (4)
- Mechanik (4)
- Package design (4)
- Radioactive materials (4)
- Radioactive waste (4)
- Radioaktives Material (4)
- Seals (4)
- Simulation (4)
- Smouldering (4)
- Spent fuel assessment (4)
- Storage (4)
- Testing (4)
- Transportbehälter (4)
- Acceleration (3)
- Bauartprüfung (3)
- Beförderung (3)
- Cask (3)
- Combustion (3)
- Containment (3)
- Design testing (3)
- Explicit dynamics (3)
- FEA (3)
- Fallprüfung (3)
- Gefahrgut (3)
- Großkomponenten (3)
- IAEA puncture drop test (3)
- Kerntechnische Anlagen (3)
- Mechanical analysis (3)
- Metal seals (3)
- Retention (3)
- Routine conditions of transport (3)
- Rückbau (3)
- Safety (3)
- Similarity (3)
- Smoldering (3)
- Transport conditions (3)
- Typ-B (3)
- Wet content (3)
- Zulassung (3)
- Acceleration values (2)
- Accident transport conditions (2)
- Activity release (2)
- Aging (2)
- Aging management (2)
- Aging mechanisms (2)
- Anerkennung (2)
- Assessment (2)
- Bolt design (2)
- Calculation (2)
- Closure system (2)
- Corrosion (2)
- Crush test (2)
- Cylindrical cask (2)
- Disposal (2)
- Dual Purpose Casks (2)
- Failure (2)
- Finite element methods (2)
- Fracture Mechanics (2)
- Full-scale (2)
- Gas generation (2)
- Heat Flux (2)
- High level waste (2)
- ISO (2)
- Kerntechnik (2)
- Lagerung (2)
- Large scale testing (2)
- Load attachment (2)
- Load cycles (2)
- Material (2)
- Maximum deceleration (2)
- Maximum deformation (2)
- Mechanical assessment (2)
- Moisture content (2)
- Nuclear fuel (2)
- Package testing (2)
- Propane (2)
- Quality assurance (2)
- RAM (2)
- Radioactive (2)
- Radioaktiv (2)
- Regulations (2)
- Scaling (2)
- Secondary impact (2)
- Spent fuel transport cask (2)
- Spruce wood (2)
- Stowage (2)
- Strahlenschutz (2)
- Structural Health Monitoring (2)
- Thermal analysis (2)
- Transport Package (2)
- Transport Packages (2)
- Transport cask (2)
- Transport safety (2)
- Trunnion (2)
- Type-B (2)
- Type-B Package (2)
- Validation (2)
- Valve (2)
- Verification (2)
- Welding (2)
- Wet intermediate level waste (2)
- Zwischenlagerung (2)
- 1-m-Fallprüfung (1)
- 1-m-punch-bar-drop-test (1)
- ACT (1)
- Accident Scenario (1)
- Accident conditions (1)
- Accident conditions of transport (1)
- Ageing Management (1)
- Ageing mechanisms (1)
- Aktivitätsfreisetzung (1)
- Alterung (1)
- Aluminium (1)
- Antragsverfahren (1)
- Appendix IV (1)
- Approved packages (1)
- Assessment method (1)
- Assessment of leak tightness (1)
- B(U) (1)
- BAM-GGR 016 (1)
- BIM (1)
- Bar length (1)
- Basket design (1)
- Belastungsversuch (1)
- Boiled joints (1)
- Bolted flange joints (1)
- Bolted trunnion (1)
- Brennelementverhalten (1)
- Bruchmechanik (1)
- Burn-up (1)
- Calorimeter (1)
- Calorimetric test (1)
- Cask design (1)
- Cesium corrosion (1)
- Chrush (1)
- Cladding (1)
- Cladding alloy (1)
- Cladding failure (1)
- Containment analysis (1)
- Containment compliance (1)
- Content simulation (1)
- Convection (1)
- Criticality (1)
- Criticality analysis (1)
- Criticality safety analysis (1)
- Crush testing (1)
- Decommissioning (1)
- Design approval (1)
- Design assessment (1)
- Design assessment of RAM packages (1)
- Design computations (1)
- Design of the packaging attachment points (1)
- Digital Models (1)
- Dop test (1)
- Drop Tests (1)
- Drop height adaption (1)
- Druckaufbau (1)
- Dry storage (1)
- Ductile cast iron (1)
- Dynamic simulation (1)
- Dynamics (1)
- ENSA (1)
- Electrical resistance method (1)
- Encapsulation (1)
- Encapsulations for damaged spent nuclear fuel (1)
- Endlager (1)
- Entsorgung (1)
- Experience feedback list (1)
- Experimental testing (1)
- Extended storage (1)
- FE mesh refinement (1)
- Fallversuch (1)
- Finite Element Analysis (1)
- Finite Element Simulation (1)
- Finite Elemente Simulation (1)
- Finite element (1)
- Finite element analysis (1)
- Finite element calculation (1)
- Finite element model (1)
- Fire Qualification (1)
- Fire Reference (1)
- Fire Reference Package (1)
- Fire Test Stand (1)
- Fire testing (1)
- Flask (1)
- Fracture initiation (1)
- Friction (1)
- Fuel assemblies (1)
- Fuel rod (1)
- Gap analysis (1)
- Gasket (1)
- Gefahrgutregeln der BAM (1)
- German guideline BAM-GGR 012 (1)
- Großer Fallturm Horstwalde (1)
- Guide (1)
- Heat (1)
- Heat flux (1)
- High-level waste (1)
- Hot cell (1)
- Hot cell testing (1)
- Hydrogen (1)
- Hüllrohr (1)
- IAEA Regu-lations (1)
- IAEA Regulations (1)
- IAEA advisory material TS-G-1.1 (1)
- IAEA fire testing (1)
- IAEA regulations (SSR-6, SSG-26) (1)
- IAEO (1)
- ILW package (1)
- IP-2 (1)
- IP-3 (1)
- Impact (1)
- Impact behavior (1)
- Inspections (1)
- Insulation (1)
- Internal collision (1)
- Internal gaps (1)
- Internal impacts (1)
- Internal shock absorber (1)
- Intumescent material (1)
- Inventaraufprall (1)
- Inventarverhalten (1)
- Kritikalität (1)
- Ladungssicherung (1)
- Lagerbehälter (1)
- Large components (1)
- Large objects (1)
- Lastanschlag (1)
- Leakage mechanism (1)
- Leaktightnes (1)
- Length of puncture bar (1)
- Lid behavior (1)
- Lid/content interaction (1)
- Load cases (1)
- Load cases for transport (1)
- Local and nominal assessment criteria (1)
- Local stress and strain fields (1)
- Log term behavior (1)
- Long-term storage (1)
- Lost cases (1)
- Management (1)
- Management system (1)
- Manufacturing (1)
- Material model (1)
- Material model wood (1)
- Mechanical behavior of wood (1)
- Mechanical behaviour (1)
- Mechanical tests (1)
- Mechanisches Verhalten (1)
- Mechanism (1)
- Metal seals reliability (1)
- Modalanalyse (1)
- Modelling of gaskets (1)
- Moisture metre (1)
- Multi-Modal Transportation Test (1)
- NCT (1)
- New package design (1)
- Non-approved (1)
- Normen (1)
- Nuclear power plant (1)
- Numerical approach (1)
- Numerical calculations (1)
- Numerical modelling (1)
- Numerical simulation (1)
- Operating procedures (1)
- Package assessment (1)
- Package safety (1)
- Packages for radioactive material (1)
- Packaging (1)
- Periodical Review (1)
- Periodical review (1)
- Pressure (1)
- Pressure build up (1)
- Propane gas (1)
- Puncture Bar Drop Test (1)
- Puncture bar drop test (1)
- Puncture bar test (1)
- Puncture drop test (1)
- Quality Management (1)
- Quality management system (1)
- RAM transport package (1)
- Radioactive Material (1)
- Radioactive Materials (1)
- Radioactive material cask (1)
- Radioactive material storage (1)
- Radioactive material transport (1)
- Radioactive materials transport (1)
- Radioactve (1)
- Radioaktive (1)
- Radioaktive Abfälle (1)
- Radioaktive Materialien (1)
- Radiolysis (1)
- Real transport (1)
- Reduced scale packages (1)
- Regeln (1)
- Regulation (1)
- Results from experiments (1)
- Revision of load case data (1)
- Rückbau kerntechnischer Anlagen (1)
- SCO-III (1)
- SNF (1)
- SNL (1)
- SSR-6 (1)
- Safety Analysis (1)
- Scale Models (1)
- Scaled model (1)
- Schwingungsdynamik (1)
- Sea (1)
- Sealed sources (1)
- Sealing (1)
- Sealing behavior (1)
- Ship (1)
- Sicherheit (1)
- Sicherheitstechnische Auslegung (1)
- Similarity theory (1)
- Slap-down (1)
- Spalte (1)
- Special encapsulation (1)
- Special form radioactive material (1)
- Spent Nuclear Fuel (1)
- Spent fuel assemblies (1)
- Spent fuel behavior (1)
- Spent fuel behaviour (1)
- Spent fuel/high-level waste (1)
- Spruce (1)
- Stahldorn (1)
- Stoßdämpfende Bauteile (1)
- Structural analysis (1)
- Surveillance (1)
- System Identification (1)
- Thermal Design (1)
- Thermal Test (1)
- Thermal testing (1)
- Thermal tests (1)
- Thermik (1)
- Thermo-mechanical analyses (1)
- Tie-down and stowage (1)
- Transport and storage cask (1)
- Transport and storage casks (1)
- Transport and storage casks for spent nuclear fuel or high level waste (1)
- Transport casks (1)
- Transport of radaioactive materials (1)
- Transport of radioactive materials (1)
- Transport package design (1)
- Transport packages for radioactive material (1)
- Transportability (1)
- Transportation (1)
- Transportation of radioactive materials (1)
- Trunnion design (1)
- Trunnions (1)
- Ttransport (1)
- Typ (1)
- Typ A (1)
- Typ B(U)-Verpackung (1)
- Typ-B Versandstück (1)
- Type B (1)
- UF6 (1)
- Uranhexaflourid (1)
- Vapourisation (1)
- Verifizierung (1)
- Verpackung (1)
- Verzögerungswerte (1)
- Water (1)
- Wet Content (1)
- Zulassungen (1)
- radioaktives Material (1)
- Überwachung (1)
Organisationseinheit der BAM
Eingeladener Vortrag
- nein (38)
Mechanical Design Assessment Approaches of Actual Spent Fuel and HLW Transport Package Designs
(2010)
Transport casks for radioactive materials have to withstand the 9 m drop test, 1 m puncture drop test and dynamic crush test with regard to the mechanical requirements according to the IAEA regulations. The safety assessment of the package can be carried out on the basis of experimental investigations with prototypes or models of appropriate scale, calculations, by reference to previous satisfactory safety demonstrations of a sufficiently similar nature or a combination of these methods. Computational methods are increasingly used for the assessment of mechanical test scenarios. However, it must be guaranteed that the calculation methods provide reliable results. Important quality assurance measures at BAM are given concerning the preparation, run and evaluation of a numerical analysis with reference to the appropriate guidelines.
Hence, a successful application of the finite element method requires a suitable mesh. An analysis of the 1 m puncture drop test using successively refined finite element meshes was performed to find an acceptable mesh size and to study the mesh convergence using explicit dynamic finite element codes. The finite element model of the cask structure and the puncture bar is described. At the beginning a coarse mesh was created. Then this mesh was refined in two steps. In each step the size of the elements was bisected. The deformation of the mesh and the stresses were evaluated dependent on the mesh size. Finally, the results were extrapolated to an infinite fine mesh or the continuous body, respectively. The uncertainty of the numerical solution due to the discretization of the continuous problem is given. A safety factor is discussed to account for the uncertainty. The calculation results are compared with experimental data from a puncture drop test with a half-scale model of a cylindrical cask.
This paper supports the convergence studies of the Task Group on Computational Modeling for Explicit Dynamics reporting to the ASME BPV Code Working Group on Design Methodology.
Mechanical design assessment approaches of actual spent fuel and HLW transport package designs
(2010)
In the approval procedure of transport packages for radioactive materials, the competent authority mechanical and thermal safety assessment is carried out in Germany by BAM Federal Institute for Materials Research and Testing.
The combination of experimental investigations and numerical calculations in conjunction with materials and components testing is the basis of the safety assessment concept of the BAM.
Among other mechanical test scenarios a 1 meter drop test onto a steel bar has to be considered for hypothetical accident conditions of Type B packages according to IAEA regulations.
Within the approval procedure for the new German package design of the HLW cask CASTOR® HAW 28M, designed by GNS Gesellschaft für Nuklear-Service Germany, a puncture drop test was performed with a half-scale model of the cask at -40°C.
For independent assessment and to control the safety analysis presented by applicant, BAM developed a complex finite element model for a dynamical ABAQUS/ExplicitTM analysis. This paper describes in detail the use of the finite element (FE) method for modeling the puncture drop test within an actual assessment strategy.
At first investigations of the behaviour of the steel bar are carried out. Different friction coefficients and the material law of the bar are analysed by using a 'rigid-body' approximation for the cask body.
In the next step a more detailed FE model with a more realistic material definition for the cask body is developed. Strain verification is possible by results of the strain gauges located at the relevant points of the cask model. The influence of the finite element meshing is described.
Finally, the verified FE half-scale model is expanded to full-scale dimension. Scaling effects are analysed. The model is used for safety assessment of the package to be approved.
Transport of large nuclear power plant components - experiences in mechanical design assessment
(2010)
Mechanical design assessment approaches of actual spent fuel and HLW transport package designs
(2010)
Numerical simulation of 9 meter drop of a transport and storage cask with aluminium impact limiter
(2010)
For the purpose of numerical simulation of 9 meter drop of a transport and storage cask with aluminium impact limiter, an elastic-incremental plastic material model with strain rate hardening acc. to Cowper-Symonds is used for the development of isothermal as well as adiabatic stress-strain relations of aluminium from the compression test at constant ambient temperature. After that, two different simulation strategies are compared. At first, the drop test is calculated fully coupled, i.e. with isothermal stress-strain relations and possible heat generation in the material. Then the drop test is recalculated in a very simplified manner with adiabatic stress-strain relations from the compression test in an isothermal simulation. Both calculation strategies show similar results in the investigated load scenario.
Verification of activity release compliance with regulatory limits within spent fuel transport casks
(2010)
BAM Federal Institute for Materials Research and Testing is the competent authority for mechanical safety assessment of transport packages for radioactive material in Germany. The further development of state-of-the-art technology concerning assessment methods is essential for a qualified work of involved designers and authority experts. The paper gives an example of current development done to improve understanding and modeling capabilities of wood filled impact limiter. In order to reduce the loads applied to the package containment, which result from regulatory drop tests, most packages are protected by energy dissipating impact limiter. Wood, encapsulated by steel sheets, is one of the materials typically used for energy dissipation in these impact limiter. Very often, mechanical safety cases regarding the 9 m drop test are performed computationally, where it is essential to use reliable and verified computational methods and models. In this context, the paper presents an approach for a finite element material model for wood. Thereby, the mechanical behavior of wood under compression loading is the focus of the development work. Additionally, material orientation as well as strain rate, temperature and lateral constraint may vary. A large number of experiments, particularly compression tests, was designed and performed to establish an adequate experimental database for modeling verification. The experimental results enabled the derivation of necessary requirements: The material model has to take into account strain rate and temperature dependencies as well as the anisotropic characteristics of the material, a proper yield criterion, flow rule and hardening law. Such a material model is currently not available in established commercial dynamic finite element codes. Thus it is necessary to create a user-defined material model considering the mentioned requirements. A first step was done by determining a yield surface as well as detecting flow and hardening mechanisms from experimental force-deflection curves. In a next step the LS-DYNA material model MAT_75 was altered according to conclusions of former BAM development work, regarding the modeling of post-peak softening as a function of lateral constraint. Future research will contain the further development, implementation and verification of a material model for wood.
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.
In the approval procedure of transport packages for radioactive materials, the mechanical and thermal safety assessment is carried out in Germany by competent authority BAM. In recent years BAM was involved in several licensing procedures of new spent fuel and HLW package designs, where the cask body was made of Ductile Cast Iron (DCI). According to IAEA regulations package designs have to fulfill requirements for specific conditions of transport. Type B(U) packages must withstand the defined accident conditions of transport. The temperature range from -40°C up to the operational temperature has to be considered. For the cask material DCI, it is necessary to determine the brittle fracture behavior. The German guideline BAM-GGR 007 defines requirements for the fracture mechanics of DCI. Due to complex structure of the cask body and the dynamic loading a fracture mechanical assessment in an analytical kind is not always possible. Experience of recent design approval procedures show that the application of numerical calculations are applicable to determine the fracture mechanical load in the cask body. At the first step a numerical analysis has to be done to identify the loading state at the whole cask body. Secondly an analysis of a detail of the cask body is made considering the displacement boundary conditions of the global model. An artificial flaw is considered in this detailed model to calculate the fracture mechanical loading state. The finite element mesh was strongly refined in the area of flaw. The size of the artificial flaw is characterized by the ultrasonic inspection used for the quality assurance of the package. The applicant developed additional analysis tools for calculation of stress intensity factor and/or J-Integral. The assessment approach by BAM led to the decision to develop own tools to the possibility for independent check of the results.
The paper describes the authority assessment approach for the DCI fracture mechanics analysis. The validation procedure incl. the development of own tools is explained. BAM developed a post-processor called JINFEM to determine the fracture mechanical loads. The regulatory 1 m puncture bar drop test is used to give an example of the assessment procedure.
Basierend auf Fallversuchen mit Transportbehältern für radioaktive Stoffe sowie auf einem Versuchsprogramm mit Holzproben wurden die Energieabsorptionsmechanismen identifiziert und ein Modell für das Verhalten von Fichtenholz bei axialer Belastung entwickelt. Das Modell zieht für die Kompression von Holz die seitliche Dehnungsbehinderung – im kontinuumsmechanischen Zusammenhang wäre das die Mehrachsigkeit des Spannungszustandes im Kontinuum – in Betracht. Die Energie, die vom Holz absorbiert werden kann, ist umso größer, je größer die seitliche Dehnungsbehinderung ist.
Für die Modellierung mit Finite Elemente Methoden wurden verschiedene Modellierungsstrategien untersucht, keine der vorgeschlagenen Modellierungsstrategien war in der Lage, dass Verhalten von Holz bei Druckbeanspruchung und großen Deformationen inkl. der Entfestigung zu modellieren. Bei Verwendung einer entfestigenden Fließkurve zeigt das Modell ausgeprägte Netzabhängigkeiten und numerischen Instabilitäten.
Für die Modellierung der Entfestigung mit Hilfe einer von der Mehrachsigkeit des Spannungszustandes gesteuerten Fließflächenevolution ist kein geeignetes Materialmodell vorhanden.
Anhand der Simulation eines Fallversuchs mit einem Behälterkörper und stoßdämpfenden Bauteilen im Maßstab 1:2 wurde gezeigt, dass zwar eine vollständige Modellierung des Stoßdämpferverhaltens inkl. Entfestigung nicht möglich war, aber das Stoßdämpferverhalten mit einer nicht-entfestigenden Fließkurve sinnvoll modelliert werden konnte. Eine Verifikation des Modellierungsansatzes am real zu modellierenden Bauteil ist zwingend erforderlich. Wenn signifikante Änderungen zwischen Verifikations- und Simulationsobjekt auftreten, ist die Zuverlässigkeit der Rechenergebnis als gering zu bewerten. Nur wenn die auftretenden Kompressionsmechanismen durch eine Analyse des Stoßdämpferholzes bestimmt werden können, ist eine zuverlässige Ermittlung von Stoßdämpferkräften- und verformungen möglich.
In the approval procedure of transport packages for radioactive materials, the competent authority mechanical and thermal safety assessment is carried out in Germany by BAM Federal Institute for Materials Research and Testing. The combination of experimental investigations and numerical calculations in conjunction with materials and components testing is the basis of the safety assessment concept of the BAM. Among other mechanical test scenarios, a 1 metre drop test onto a steel bar has to be considered for the application of the hypothetical accident conditions to Type B packages according to IAEA regulations. Within the approval procedure for the new German package design of the HLW cask CASTOR® HAW 28M, designed by GNS Gesellschaft für Nuklear-Service Germany, a puncture drop test was performed with a half-scale model of the cask at -40°C. For independent assessment and to control the safety analysis presented by the applicant, BAM developed a complex finite element (FE) model for a dynamical ABAQUS/ExplicitTM analysis. This paper describes in detail the use of the FE method for modelling the puncture drop test within an actual assessment strategy. At first, investigations of the behaviour of the steel bar were carried out. Different friction coefficients and the material law of the bar were analysed by using a 'rigid-body' approximation for the cask body. In the next step, a more detailed FE model with a more realistic material definition for the cask body was developed. The validation of calculated strains was carried out by comparison with the results of the strain gauges located at the relevant points of the cask model. The influence of the FE meshing is described. Finally, the validated FE half-scale model was expanded to full-scale dimension. Scaling effects were analysed. The model was used for safety assessment of the package to be approved.