Filtern
Erscheinungsjahr
Dokumenttyp
- Beitrag zu einem Tagungsband (144)
- Zeitschriftenartikel (85)
- Vortrag (33)
- Beitrag zu einem Sammelband (13)
- Forschungsbericht (7)
- Buchkapitel (4)
- Dissertation (1)
- Sonstiges (1)
- Posterpräsentation (1)
Sprache
- Englisch (164)
- Deutsch (124)
- Mehrsprachig (1)
Schlagworte
- Drop test (15)
- Transport (15)
- Safety assessment (13)
- Impact limiter (11)
- Radioactive material (10)
- Ductile iron (8)
- Fracture mechanics (7)
- Container design (5)
- Drop testing (5)
- Drop tests (5)
Organisationseinheit der BAM
Eingeladener Vortrag
- nein (33)
Die sicherheitstechnische Auslegung von Behältern aus duktilem Gusseisen mit erhöhten Reststoffanteilen wird untersucht. Ausgehend von den zu gewährleistenden Anforderungen an Transport- und Lagerbehälter für radioaktive Abfälle werden Referenzbeanspruchungs- situationen definiert. Für einen ausgewählten Referenzfall (bestehend aus der Kombination der Behälterbauart Gusscontainer Typ VI, einem Absturz aus 5 m Höhe auf ein hartes Endlagergestein simulierendes Betonfundament als repräsentativer Störfall und vorgegebenen Werkstoffeigenschaften) wird eine numerische Spannungsanalyse durchgeführt. Die Berechnungen erfolgen mit der Methode der finiten Elemente an dreidimensionalen Modellen, deren numerische Stabilität und Genauigkeit überprüft wird. Zur Berechnung der Behälterbeanspruchungen in Abhängigkeit vom Reststoffanteil werden dynamische Fließkurven für definiert legierte Testabgüsse angegeben.
An zwei mit Flüssiggas (Propan) gefüllten Lagerbehältern mit Brandschutzisolierung wurden Brandversuche über eine Dauer von bis zu 90 Minuten durchgeführt. Für eine Brandschutzisolierung wurde erstmals experimentell die Erfüllung der entsprechenden Brandschutzanforderungen der Technischen Regel Druckbehälter TRB 610 nachgewiesen.
Das Unfallgeschehen beim Straßentransport wird wesentlich von Unfällen dominiert, die sich mit einer bestimmten Bauart von Tanks ergeben haben. Da die erwähnten Tanks weder den entsprechend verwendeten Eisenbahn-Kesselwagen noch Tankcontainern gleichwertig sind, ist somit bereits vorgezeichnet, dass Alternativen zur Erzielung einer gleichwertigen Sicherheit von Straßen- und Schienentransport denkbar sind.
Integrity of the "POLLUX" cask for final disposal: Experimental results of the mechanical tests
(1995)
Practical methods for the safety assessment of postulated crack-like material defects of cubic containers made of ductile cast iron are presented. A formula for the stress intensity factor of a crack in a fillet with a radius from 20 to 200 mm under static load conditions is given. From that, an assessment diagram is derived for the critical depth of a crack in a fillet. The formula may be used to estimate the stress intensity factor of a dynamically loaded crack for special cases. As an application the results of the estimation procedure are compared with the results of a dynamic finite element calculation.
Gußeisen mit Kugelgraphit als Werkstoff für Transport- und Lagerbehälter bestrahlter Brennelemente
(1985)
Der erhöhte Zusatz metallischer Reststoffe aus der Stilliegung und dem Rückbau
kerntechnischer Einrichtungen bei der Herstellung von Behältern aus Gusseisen mit
Kugelgraphit führt einerseits durch das Recycling zu einer Reduzierung der Menge
des endzulagernden radioaktiven Metallschrottes, aber andererseits auch zu einer
nachteiligen Beeinflussung sicherheitsrelevanter Werkstoffeigenschaften. Unter den
hochdynamischen Beanspruchungsbedingungen der nicht mit Stoßdämpfern ausgerüsteten Behälter liegt die Bruchzähigkeit um mehr als die Hälfte unter dem Mindestwert für die bisher genehmigten Werkstoffqualitäten, was eine Anpassung der sicherheitstechnischen Bewertungsmethoden für Behälter aus Gusseisen mit Kugelgraphit an den neuen Werkstoff erfordert. Im ersten Teil des Projektes EBER wurden dazu die Grundlagen erarbeitet. In diesem zweiten Teil wird die Beanspruchungsanalyse der Behälter weiter vervollkommnet. Die Werkstoffdämpfung wird mittels einer Analyse der Ausbreitung von Spannungswellen im Gusseisen berechnet. Die Behälterstruktur wird genauer als bei den bisherigen Berechnungen in den Modellen abgebildet. Im Mittelpunkt steht die Weiterentwicklung des sicherheitstechnischen Bewertungskonzeptes. Zur Bewertung von rissartigen Werkstofffehlern in geometrisch
komplexen Behälterpartien wurden statische und dynamische bruchmechanische nu-
merische Berechnungen eines Risses in einer Hohlkehle und in der Mitte einer Behälterwand durchgeführt. Die Berechnungsergebnisse wurden für spezielle Anwendungsfälle verifiziert, für die bereits Lösungen bekannt sind. Die gewonnenen Erkenntnisse
wurden in einfach zu handhabende Bewertungsdiagramme umgesetzt. Das sicherheitstechnische Bewertungskonzept wurde schließlich bei einem Fallversuch mit einem
rissbehafteten Prototypbehälter definierter Werkstoffqualität überprüft. Eine Minderung
der Beanspruchung infolge konstruktiver Verbesserungen (größere Hohlkehlen, Bodenleiste) durch den Behälterkonstrukteur konnte dabei bestätigt werden.
Drop Test for the Licensing of the "RA-3D" Package in the Transport of BWR Fresh Fuel Assembllies
(2001)
Behälter zur Endlagerung radioaktiver Stoffe - Baumusterprüfung und qualitätssichernde Maßnahmen
(1989)
Fallversuche im Verfahren der Zulassung neuer Behälterbauarten - Neuer Fallversuchsstand der BAM -
(2005)
Fallversuche im Verfahren zur Zulassung neuer Behälterbauarten - Neuer Fallversuchsstand der BAM
(2005)
The majority of transports of radioactive materials are carried out in packages which don’t need a package design approval by a competent authority. Low-active radioactive materials are transported in such packages e.g. in the medical and pharmaceutical industry and in the nuclear industry as well. Decommissioning of NPP’s leads to a strong demand for packages to transport low and middle active radioactive waste. According to IAEA regulations the “non-competent authority approved package types” are the Excepted Packages and the Industrial Packages of Type IP-1, IP-2 and IP-3 and packages of Type A. For these types of packages an assessment by the competent authority is required for the quality assurance measures for the design, manufacture, testing, documentation, use, maintenance and inspection (IAEA SSR 6, § 306). In general a compliance audit of the manufacturer of the packaging is required during this assessment procedure. Their regulatory level in the IAEA regulations is not comparable with the “regulatory density” for packages requiring competent authority package design approval. Practices in different countries lead to different approaches within the assessment of the quality assurance measures in the management system as well as in the quality assurance program of a special package design. To use the package or packaging in a safe manner and in compliance with the regulations a management system for each phase of the life of the package or packaging is necessary. The relevant IAEA-SSR6 § 801 requires documentary verification by the consignor concerning package compliance with the requirements.
Federal Institute for Materials Research and Testing (BAM) is the responsible authority for the
assessment of mechanical and thermal safety as well as quality issues within the licensing procedure
for transport casks for radioactive materials. The assessment includes a brittle fracture analysis of all
relevant cask components.
For cask bodies where a steel bottom is welded to a steel shell, specimens for testing of sufficient
fracture resistance can normally not be extracted directly from the welding seam area of the cask.
Therefore, a methodology has to be developed to ensure compliance with the safety analysis
considerations and the approved design specification. This paper describes such a methodology
including brittle fracture analysis and de-termination of required material properties as well as aspects
of quality assurance during manufacturing.
Transport packages for spent fuel have to meet the International Atomic Energy Agency requirements for different transport conditions. Physical state of spent fuel and fuel rod cladding as well as geometric configuration of fuel assemblies are important inputs for the evaluation of package capabilities under these conditions. In this paper, the mechanical behaviour of high burn-up spent fuel assemblies under transport conditions is analysed with regard to assumptions to be used in the activity release and criticality safety analysis. In particular the different failure modes of the fuel rods (fine cracks or complete breakage), which can cause release of gas, volatiles, fuel particles or fragments have to be properly considered in these assumptions. In view of the complexity of interactions between the fuel rods as well as between fuel assemblies, basket, and cask containment, the exact mechanical analysis of such phenomena is nearly impossible. The gaps in information concerning the material properties of cladding and pellets, especially for the high burn-up fuel, make the analysis more complicated additionally. In this context some practical approaches based on experiences of BAM Federal Institute for Material Research and Testing within safety assessment of packages for transport of spent fuel are discussed.
Ziel dieses Beitrages soll es sein, zum einen das Vorgehen bei der Erlangung einer Anerkennung zur qualitätsgesicherten Herstellung einer Verpackung für prüfpflichtige Versandstücke der zuständigen Behörde im Sinne des ADR Unterabschnittes 1.7.3 'Qualitätssicherung' darzustellen und zum anderen Probleme bei der Umsetzung der rechtsverbindlichen Vorschriften des Gefahrgutrechts aufzuzeigen.
Federal Institute for Materials Research and Testing (BAM) is the competent authority for mechanical and thermal safety assessment of transport packages for spent fuel and high level waste in Germany. In context with package design approval of the new German high level waste cask CASTOR® HAW28M, BAM performed several drop tests with a half scale model of the CASTOR® HAW/TB2. The cask is manufactured by Gesellschaft für Nuklear Service mbH and was tested under accident transport conditions on the 200 tons BAM drop test facility at the BAM Test Site Technical Safety. For this comprehensive test program, the test specimen CASTOR® HAW/TB2 was instrumented at 21 measurement planes with altogether 23 piezo resistive accelerometers, five temperature sensors and 131 triaxial strain gauges in the container interior and exterior respectively. The strains of four representative lid bolts were recorded by four uniaxial strain gauges per each bolt. Helium leakage rate measurements were performed before and after each test in the above noted testing sequence. The paper presents some experimental results of the half scale CASTOR® HAW/TB2 prototype (14 500 kg) and measurement data logging. It illustrates the extensive instrumentation and analyses that are used by BAM for evaluating the cask performance to the mechanical tests required by regulations. Although some of the quantitative deceleration, velocity and strain values cannot be shown because of confidentially issues, they are provided qualitatively to illustrate the types of measurements and methodologies used at BAM.
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.
BAM (Federal Institute for Material Research and Testing) is the competent authority for mechanical and thermal safety assessment of transport packages for spent fuel and high level waste (HLW) in Germany. In context with package design approval of the new German HLW cask CASTOR HAW28M, BAM performed several drop tests with a half-scale model of the CASTOR HAW/TB2. The test model was manufactured by GNS (Gesellschaft fur Nuklear Service mbH) and tested under accident transport conditions on the 200 tons BAM drop test facility at the BAM Test Site Technical Safety. For this comprehensive test program the test specimen CASTOR HAW/TB2 was instrumented at 21 measurement planes with altogether 23 piezo-resistive accelerometers, five temperature sensors and 131 tri-axial strain gauges in the container interior and exterior, respectively. The strains of four representative lid bolts were recorded by four uniaxial strain gauges per each bolt. Helium leakage rate measurements were performed before and after each test in the above noted testing sequence. The paper presents some experimental results of the half-scale CASTOR HAW/TB2 prototype (14,500 kg) and measurement data logging.
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.
An extensive series of large deformation crushing tests with spruce wood specimens was conducted. Material orientation, lateral constraint and loading rate were varied. Regarding material orientation, a reduction in the softening effect and the general force level was observed with a higher fiber-load angle. A comparison with characteristics gained by application of Hankinson's formula showed discrepancies in compression strength and the beginning of the hardening effect. Lateral constraint of the specimens caused a multiaxial stress state in the specimens, which was quantified with the applied measuring method. Further, a higher force level compared to specimens without lateral constraint and significant hardening effect at large deformations resulted. Thus, the influence of a multiaxial stress state on the force level could be determined. An increase in the loading rate led to higher force levels at any displacement value and material orientation.
BAM is the responsible authority in Germany for the assessment of the mechanical and thermal design safety of packages for the transport of radioactive materials. The assessment has to cover the proof of brittle fracture safety for package components made of potentially brittle materials. This paper gives a survey of the regulatory and technical requirements for such an assessment according to BAM's new 'Guidelines for the application of ductile cast iron for transport and storage casks for radioactive materials'. Based on these guidelines, higher stresses than before will be permissible, but it is necessary to put more effort into the safety assessment procedure. The fundamentals of such a proof using the methods of fracture mechanics are presented. The recommended procedure takes into account the guidelines of the IAEA's advisory material which are based on the prevention of crack initiation. Examples of BAM's research and safety assessment practices are given. Recommendations for further developments towards package designs with higher acceptable stress levels will conclude the paper.
Using Scale Model Impact Limiter in the Type Assessment of Transport Casks for Radioactive Material
(2007)
Consequences of drop test parameter limitations for subsequent package design safety analysis
(2007)
Dynamische Analyse eines mit Stoßdämpfern ausgerüsteten Gefahrgutbehälters beim 9 m - Fallversuch
(2006)
Admissible limits for activity release from type B(U) packages for spent fuel transport specified in the International Atomic Energy Agency regulations (10-6 A2 h-1 for normal conditions of transport and A2 per week for accidental conditions of transport) have to be kept by an appropriate function of the cask body and its sealing system. Direct measurements of activity release from the transport casks are not feasible. Therefore, the most common method for the specification of leak tightness is to relate the admissible limits of activity release to equivalent standardised leakage rates. Applicable procedure and calculation methods are summarised in the International Standard ISO 12807 and the US standard ANSI N14·5. BAM as the German competent authority for mechanical, thermal and containment assessment of packages liable for approval verifies the activity release compliance with the regulatory limits. Two fundamental aspects in the assessment are the specification of conservative design leakage rates for normal and accidental conditions of transport and the determination of release fractions of radioactive gases, volatiles and particles from spent fuel rods. Design leakage rates identify the efficiency limits of the sealing system under normal and accidental transport conditions and are deduced from tests with real casks, cask models or components. The releasable radioactive content is primarily determined by the fraction of rods developing cladding breaches and the release fractions of radionuclides due to cladding breaches. The influence of higher burn-ups on the failure probability of the rods and on the release fractions are important questions. This paper gives an overview about methodology of activity release calculation and correlated boundary conditions for assessment.
Test installations for the examination of CASTOR casks at the BAM test centre technical safety
(2008)
BAM as competent German government institute for the mechanical and thermal testing of radioactive material transport and storage containers, operates unique drop and fire test facilities for experimental investigations on an open-air Test Centre Technical Safety.
To be able to perform even drop tests with full-scale spent fuel or HAW casks (i. e. the German CASTOR cask designs; CASTOR in the meantime in synonym for all other spent fuel cask designs) BAM constructed in 2004 a large drop test facility capable to handle 200 tons test objects, and to drop them onto a steel plate covered unyielding target with a mass of nearly 2600 tons. Drop testing of the 181 ton CONSTOR V/TC, the 127 ton MHI-MSF 69BG, a 1:2 scale model (CASTOR HAW TB2) and of cubic containers for radioactive waste disposal will briefly be presented. The experimental BAM drop testing activities can be supported also by drop testing of smaller packages (up to 2 tons) in an in-house test facility, and by dynamic, guided impact testing inside a new drop test machine. In May 2008 a new modern fire test facility was put into operation. The facility provides two test stands fired with liquid Propane. Testing in every case has to be completed by calculational investigations where BAM operates appropriate computer codes, e. g. ABAQUS, LS-Dyna, ANSYS and other analytical tools.
Safety during whole life time: important aspect in safety assessment of sealed radioactive sources
(2008)
Many sealed sources with long halflife isotopes commonly used in industry or medicine have a long working life, up to several decades. Source integrity must be guaranteed in transport and use at any time. On the one hand, safety during the working life has to be ensured by the source design. Its strain has to be tested. On the other hand, source durability depends on the specific operating conditions. BAM as the competent authority in Germany has to assess the suitability of a source design for safe transport and use also for a longer service life for: (a) sources approved as special form radioactive material according to the regulations for the safe transport of radioactive material, (b) sources in approved devices for licence free use according to the Radiation Protection Ordinance, Para 25, and (c) sources with an extended leak test period according to Radiation Protection Ordinance, Para 66. In all these domains BAM has to assess if design and additional arrangements are qualified and guaranteed to prevent a release of radioactive content under the mechanical, chemical and physical operating conditions of the specified working life of a sealed radioactive source. As a result, limits for the duration of validity of the special form status of a source or a type approval of a device are specified and, in many cases, special additional responsibilities for users, such as periodical control and test measurements, have to be specified in approval certificates as binding conditions to satisfy the required safety standards in regulations. This paper presents BAM's experiences and shows which aspects should be considered in assessment of a lifetime limit of sealed sources.