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- 3 Gefahrgutumschließungen; Energiespeicher (24) (entfernen)
After restarting the site selection process for a final repository for spent nuclear fuel (SNF) and heat-generating radioactive waste, all areas with one of the three potential host rock formations considered in Germany – salt, clay and crystalline rock – are under review. The project “KoBrA“, run by BGE TECHNOLOGY and BAM, collects and reviews requirements, criteria and proposals for final disposal container concepts complying with the current safety standards, taking into consideration international experience in the field of high-level nuclear waste (HLW) management.
The mechanical and thermal loadings associated with the routine, normal and accident conditions of transport can have a significant effect on the leak tightness of the containment system of transport casks for spent fuel and high radioactive waste. The containment systems of such transport casks usually include bolted lids with metallic or elastomeric seals.
Scaled cask models are often used for providing the required mechanical and thermal tests series. Leak tests have been conducted on those models.
It is common practice to use scaled component tests to investigate the influence of deformations or displacements of the lids and the seals on the standard leakage rate as well as to study the temperature and time depending alteration of the seals.
In this paper questions and open points of the transferability of scaled test results to the fullscale design of the containment system will be discussed.
Commodities and rail damage
(2018)
The normalized contact-mechanics fourth-power law approach for the
dynamic loads, suggest: worst railway use situation (double deck at 65 km/h) is 350 times that of the less rail damage situation (flat car at 45 km/h).
The normalized dispersion approach for the dynamic loads (Dynamic Load Coefficient), suggest that the worst railway use situation (double deck at 65 km/h) is about 4 times that of the less rail damage Situation (flat car at 45 km/h).
The potential effect of the different types of cars on the railway fatigue life could be significant, as a function of the vehicle speed.
The experimental validation of these outputs will be carried out as a continuation of this research effort. In addition to that, it should be mentioned that the associated simplified model could be used to analyze some other situations, related with the transport safety of different products.
Fachinformationssystem Datenbank GEFAHRGUT - Jetzt auch Hilfe bei der Kennzeichnung der Umweltgefahr
(2018)
Um Gefahrgutumschließungen richtig kennzeichnen zu können ist es erforderlich zu wissen, ob ein Stoff umweltgefährdende Eigenschaften hat. Als Informationsquelle hierfür kann sowohl die Rechercheanwendung der Datenbank GEFAHRGUT als auch die Daten des Gefahrgutdatenservices im BAM-Nummern-System als auch im UN-Nummern-Systems verwendet werden.
Fachinformationssystem Datenbank GEFAHRGUT - Jetzt auch Hilfe bei der Kennzeichnung der Umweltgefahr
(2018)
Um Gefahrgutumschließungen richtig kennzeichnen zu können ist es erforderlich zu wissen, ob ein Stoff umweltgefährdende Eigenschaften hat. Als Informationsquelle hierfür kann sowohl die Rechercheanwendung der Datenbank GEFAHRGUT als auch die Daten des Gefahrgutdatenservices im BAM-Nummern-System als auch im UN-Nummern-Systems verwendet werden.
Tanks for heating oil made of polyethylene grades have been on the market since the early 1970s in Germany. Tank manufacturers recommend the replacement of the tanks after a period of 30 years due to guarantee safety. Polyethylene grades are subject to ageing by alteration of the properties during their life cycle. The degree of ageing and the nature of the degradation process mainly depend on the chemical degradation of the polyethylene, the wall thickness of the tank and the environmental conditions. There are no results available on the long-term behavior of the polyethylene grades, especially after a service life of more than 30 years. The aim of this investigation was the determination of the factual degree of damage in comparison to the uncontaminated polyethylene grades. Material data of the used polyethylene grades are available because the BAM was the competent authority for the tests and expert reports for the approval of these tanks until the middle of the 1990s.
The determination of the Melt Flow Rate (MFR) and the Fourier Transmission IR Spectroscopy (FTIR) of tank sections from the bottom, the shell and the roof of 10 segregated heating oil storage tanks produced of polyethylene grades A and B were used as tests methods.
The MFR measurements of the tank sections showed differences in the values depending on the weight which was used (5 kg or 21.6 kg). A reduction of the MFR values was measured for most of the sections of tanks made of polyethylene grade B after a service life of the tanks of more than 30 years. This grade is mainly subject to the internal ageing by cross-linkages, increased degree of branched molecules and loss of the plasticizer, and to a lesser extent by oxidative degradation. The FTIR analysis, especially of tank sections of the bottom and the shell showed that the intensity of the CH2 asymmetric and symmetric stretching vibrations in the range: 2800 - 2900 cm-1 and the CH2 bending deformation vibration at 1400 cm-1 increased due chain scissions. The intensity of the carbonyl stretching vibration C=O at 1740 cm-1 is low. The carbonyl index characterizes the degree of oxidation.
In Germany spent nuclear fuel (SNF) and high level radioactive waste (HLW) are stored in interim storage containers with double lid systems. Those lids are equipped with metal seals (e.g. Helicoflex®) that ensure the safe enclosure of the inventory. Being licensed for up to 40 years of interim storage the evaluation of the long-term behavior of the seals is necessary, taking into account storage conditions, decay heat and possible mechanical loads.
The developed fibre-break model from Mines-ParisTech requires an improvement in terms of calculation time for analysing real-scale model. By implementing the proposed method, the number of representative volume element and monte-carlo run can be optimised to obtain certain confidence level of the results. By reducing this level, faster computation can be done. This approach has given us a positive insight that it can be used for studying real-scale model of composite pressure vessels.
Verbundvorhaben "KoBrA"
(2018)
Im Verbundvorhaben "KoBrA" sollen systematisch Randbedingungen, Anforderungen und Konzepte für BE/HLW-Endlagerbehälter in den potentiellen Wirtsgesteinen Kristallin, Ton und Salz gesammelt, zusammengetragen und ausgewertet werden. Am Ende sollen generische Behälteranforderungen und -Konzepte für mögliche endlagerfähige Behälter in Deutschland erarbeitet werden. Hier wird ein Überblick über das gemeinsam mit unseren Partnern von der DBE TEC (jetzt BGE TEC) bearbeitete Gesamtvorhaben mit allen Arbeitspaketen gegeben.
Im Vorhaben "KoBrA" sollen aus bestehenden Anforderungen für endlagerfähige Behälter und aus internationalen Erfahrungen ein aktueller Stand auf dem Gebiet der Behälterforschung für HLW/SF-Behälter ermittelt und generische Vorschläge für einen deutschen HLW/BE-Endlagerbehälter in den drei potentiellen Wirtsgesteinen (Kristallin, Ton oder Salz) erarbeitet werden. Im Arbeitspaket 1 wird dafür eine umfassende Literaturrecherche zu internationalen Behälterkonzepten durchgeführt, deren erste Ergebnisse hier präsentiert werden.
Im Vorhaben "KoBrA" sollen aus bestehenden Anforderungen für endlagerfähige Behälter und aus internationalen Erfahrungen ein aktueller Stand auf dem Gebiet der Behälterforschung für HLW/SF-Behälter ermittelt und generische Vorschläge für HLW/BE-Endlagerbehälterkonzepte in den drei potentiellen Wirtsgesteinen (Kristallin, Ton oder Salz) erarbeitet werden.
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.
Assessment of Quality Management for Transport Packages not requiring Authority Design Approval
(2018)
The poster presents the german approach for the assessment of quality management systems for transport packages for radioactive material not requiring authority design approval. As legal basis the IAEA regulations, the ADR as well as the GGVSEB are highlighted and examples for these transport packages are given. The GGR 016 is mentioned, main duties and responsibilities as well as the manufacturing and quality surveillance system are described.
BAM is the German Federal Institute for Materials Research and Testing and the competent authority for mechanical and thermal safety assessment of transport packages for spent fuel and high level waste. In context with safety assessment of RAM packages BAM performed numerous drop tests in the last decades. The tests were mostly accompanied by extensive and various measurement techniques especially by instrumented measurements with strain gages and accelerometers.
The procedure of drop testing and the resulting measurement analysis are the main methods to evaluate the safety against mechanical test conditions. Measurement techniques are dedicated to answer questions in regard to the structural integrity of a RAM package, the mechanical behavior of the prototype as well as of its content under impact conditions.
Test results like deceleration-time functions constitute a main basis for the validation of assumptions in the safety analysis and for the evaluation of numerical calculations. In this context the adequate selection of accelerometers and measurement systems for the performance of drop tests is important. Therefore it is not only necessary to find suitable positions for the accelerometers at the test specimens, but also to consider technical boundary conditions as e.g. temperature.
For transport operations according IAEA regulations SSR-6, the package shall be securely stowed and the package shall be capable to withstand specific effects, e.g. accelerations, during routine transport conditions. The supporting IAEA Advisory Material SSG-26 provides information how to do that. General information and detailed load factors for use in safety demonstrations are provided.
Up to now package designers in different countries use other load factors for the design of attachment points than those specified in the IAEA guidance material. In particular the acceleration factors vary between different countries and lead to difficulties during the validation of foreign approval certificates. The background of the existing guidance including specified load values was not clear enough. The application of specified values and the boundary conditions, i.e. transport conditions, seemed to be improvable.
The IAEA started a discussion process to review the existing guidance text. An international working group was constituted in 2013. Representatives came from different stakeholders, e.g. transport operators, competent authorities and modal organizations. The discussions concluded especially on the transport conditions which has to be considered for stowage design, including on the one hand the relevance of the load factors used for strength and fatigue analysis and, on the other hand the criteria which have to be considered for the attachment points. In addition, complementary questions relative to the operational aspects were discussed. Revised load values for different transport modes were proposed. The values are derived from standards and include safety factors now.
As a result of those discussions, the international working group wrote new guidance material for stowage in transport, addressing all the previously quoted topics.