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)
Packages for the transport of radioactive material are designed to en-dure severe accidents. Packages for the transportation of radioactive material must demonstrate that the package can withstand certain prescribed tests from the IAEA Regulations [1]. In addition to mechanical tests, a thermal test in form of a fire test must be carried out. As packages to be tested at BAM are signifi-cantly larger than previous package designs, BAM has expanded an existing fire test stand. A modular concept is chosen, which means that the arrangement of the burner nozzles can be adapted to the test specimen. The dimensions of the burner rings, the type, the orientation and the number of burner nozzles can be varied depending on the test specimen. In addition, various pumps can be used to set the corresponding mass flow. With the help of a calorimeter test, the fire test stand can be qualified for a specific size of packages regarding the boundary conditions of the IAEA Regulations [1]. Due to the typically wood filled impact limiters in German package designs, a fire test is necessary, as experiments have shown that possible openings that occurred during a mechanical test contributed to the igni-tion of the wood filled impact limiters within the prescribed 30 minutes of the IAEA Regulations [1]. From a series of experiments, two experiments are pre-sented to show the possibilities to obtain different temperatures and temperature rates in the test specimen. In addition to sensor data, the heat flux into the package is calculated to verify that the IAEA boundary conditions are satisfied. In addition to the temperature data, other data such as wind speed and wind direction are also recorded to explain subsequent effects in the measurement data in a comprehen-sible manner.
The consideration of ageing mechanisms is with integration into the IAEA-requirements now obligatory for the design of transport packages. For packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance are required. Therefore, these packages have been maintained during storage in a manner that all requirements specified in the IAEA-requirements and in the applicable certificates of approval have been fulfilled.
BAM is the competent authority in Germany for evaluating the thermal and mechanical design of packages for the transport of radioactive materials. In this context, BAM also evaluates the aging mechanisms and aging effects occurring during the long-term storage period of such transport packages. BAM has developed a guideline for the implementation of ageing assessment and of the measures for ageing management into the approval procedure based on IAEA-requirements.
The goal of the presented paper is to introduce this guideline and the general approach for ageing management requirements and to describe the application to a specific package design. The type and amount of the ageing management not only depend on the use of the packaging, but also on the accessibility of the components that are considered in the ageing assessment. The different operating phases of a packaging are considered for the ageing assessment, such as loading, interim storage or transport.
The implementation of measures for ageing management is divided into three levels – systemic measures, package design related measures and documentation. The systemic measures are attributed to the general management system and define the whole activities for organization of ageing management like structure, responsibilities, documentation, reports and evaluation. The package design related measures are defined in an ageing management plan. These measures shall ensure that the anticipated changes of the package design under consideration of ageing effects still complies with the design approval specification. Therefore, an ageing surveillance program and, if necessary, a gap analysis program shall be developed. The ageing management documentation ensures the continuous documentation of the compliance of a specific package to the approved package design, comprising mainly records resulting from operation and surveillance.
Heavy-weight packages for the safe transport of radioactive material are equippedwith impact limiters often built ofwood-filled steel sheet structures to fulfil the requirements of the International Atomic Energy Agency (IAEA) regulations. The requirements definemechanical tests followed by a thermal test, including criteria ensuring the package design’s ability to withstand severe accidents and provide a high level of technical safety.
Impact limiters are a package component mainly designed for the packages to withstand severe mechanical accident scenarios. In drop tests the impact limiters absorb the kinetic energy during impact of the package. The package must then - with its pre-damaged impact limiters - endure a thermal test defined precisely in the IAEA regulations as a 30-min fully engulfing 800 °C-fire. After the fire, a wood-filled impact limiter may continue to release thermal energy from an ongoing combustion process, defining relevant package temperatures. The energy flow from a possible burning impact limiter to the package is important for the safety evaluation of transport packages. To investigate the combustion behaviour of densely packed layers of spruce wood, encapsulated in pre-damaged cylindrical metal enclosures, a test set-up has been realised. The set-up consists of a combustion chamber to perform these tests under defined boundary conditions. The temperature development of the test specimens will be observed fromoutside with a thermographic imager, with HD-Cameras, and the mass loss will be measured during the entire test. Airflow conditions in the combustion chamber are analysed using Computational Fluid Dynamics (CFD) calculations in OpenFOAM. The planned combustion test setup is described.
Packages for the transport of spent nuclear fuel are designed to endure severe accidents. To obtain approval, these transport packages must adhere to the specification-based criteria of the international transport regulations SSR-6 of the International Atomic Energy Agency (IAEA). To ensure compliance with these requirements, specific mechanical and thermal tests need to be addressed with respect to the package type. Typically, SSR-6 prescribes a mechanical test followed by a thermal fire test as part of different testing scenarios. To approve the latter test of the sequence, BAM performs calorimeter tests in advance with so-called fire reference packages for characterizing the actual fire and its impact on the package to be tested. Packages are designed with different geometry sizes depending on their purpose. For previous tests, the implemented test setups in the fire test stand were sufficiently dimensioned and could cover all requirements in this respect. However, to cover additional testing needs in the future, BAM is expanding the test setup for the purpose of testing significantly larger packages.
In previous test setups one ring burner for propane surrounding the test specimen was sufficient. The limiting size in this configuration was the design height of the transport package to be tested. According to the thermal test of the IAEA-Regulations [1], a 30-minute fully engulfing 800°C pool fire or an equally severe fire, e.g., propane gas fire, must be applied to the transport package. Possible adjustments such as nozzle cross-section and propane mass flow can be adjusted to a certain extent. Further modifications, to cover significantly higher and larger packages all-around with a fully engulfing fire, must be accomplished with an additional, second burner ring. Both burner rings had the same dimensions and were mounted on top of each other at different heights to create a significantly larger volume of fire that completely engulfs the package including its impact limiter.
To meet the IAEA regulatory boundary conditions, the enhanced fire test stand with the second burner ring is tested with a large fire reference package and will then be used for real-size transport packages after all parameters are successfully met. This fire reference package represents the external geometry of a generic transport cask for radioactive material and is equipped with numerous temperature sensors to record temperature curves at the interior wall surfaces.