Dokument-ID Dokumenttyp Autoren/innen Persönliche Herausgeber/innen Haupttitel Abstract Auflage Verlagsort Verlag Herausgeber (Institution) Erscheinungsjahr Titel des übergeordneten Werkes Jahrgang/Band ISBN Veranstaltung Veranstaltungsort Beginndatum der Veranstaltung Enddatum der Veranstaltung Ausgabe/Heft Erste Seite Letzte Seite URN DOI Lizenz Datum der Freischaltung OPUS4-325 Forschungsbericht Droste, Bernhard; Probst, Ulrich Untersuchungen zur Wirksamkeit der Brandschutzisolierung von Flüssiggas-Lagertanks 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. Bremerhaven Wirtschaftsverlag NW Bundesanstalt für Materialprüfung (BAM) 1986 125 978-3-88314-540-8 1 24 urn:nbn:de:kobv:b43-3253 http://www.gesetze-im-internet.de/urhg/index.html 2015-07-02 OPUS4-2325 Beitrag zu einem Tagungsband Wieser, Karol E.; Tobisch, Karl; Probst, Ulrich The Elastomer Gasket - A Black Sheep for Quality Assurance Measures? Springfield, Va. Nuclear Division.*Union Carbide Corp.* 1983 Proceedings of the International Symposium on Packaging and Transportation of Radioactive Materials 2 7th International Symposium on Packaging and Transportation of Radioactive Materials New Orleans, LA, USA 1983-05-15 1983-05-20 4 1366 1369 2016-02-19 OPUS4-1888 Beitrag zu einem Tagungsband Droste, Bernhard; Schulz-Forberg, Bernd; Probst, Ulrich Investigation of a Spent Fuel Cask Beside an Exploding Propane Tank Chicago, Ill. PATRAM 2001 Transportation of radioactive materials - the vital link PATRAM 2001 ; Annual International Symposium on Packaging and Transportation of Radioactive Materials Chicago, IL, USA 2001-09-03 2001-09-07 CD-ROM 2016-02-19 OPUS4-7414 Zeitschriftenartikel Wolff, Dietmar; Probst, Ulrich; Völzke, Holger; Droste, Bernhard; Rödel, Roland Safety aspects of long-term dry interim storage of type-B spent fuel and HLW transport casks Ashford Ramtrans Publ. 2004 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 15 3-4 207 213 2016-02-19 OPUS4-25659 Posterpräsentation Probst, Ulrich Plastische Deformation von Federkern-Metalldichtungen in Abhängigkeit von Temperatur und Zeit 2012 3. RAM-Behältersicherheitstage 2012, BAM 3. RAM-Behältersicherheitstage 2012, BAM Berlin, Germany 2012-03-22 2012-03-23 2016-02-19 OPUS4-26175 Beitrag zu einem Tagungsband Völzke, Holger; Probst, Ulrich; Wolff, Dietmar; Nagelschmidt, Sven; Schulz, Sebastian Seal and closure performance in long term storage 2012 PSAM 11 ESREL 2012 - 11th International probabilistic safety assessment and management conference & The annual european safety and reliability conference (Proceedings) PSAM 11 ESREL 2012 - 11th International probabilistic safety assessment and management conference & The annual european safety and reliability conference Helsinki, Finland 2012-06-25 2012-06-29 1 8(?) 2016-02-19 OPUS4-17540 Zeitschriftenartikel Probst, Ulrich; Hagenow, Peter; Völzke, Holger; Wolff, Dietmar; Wossidlo, Peter; Abbasi, Behboud; Achelpöhler-Schulte, Andreas; Schulz, Sebastian Investigation of seal effects according to axial compression variation of metal seals for transport and storage casks Casks for the transport and storage of heat generating radioactive waste in Germany are normally provided with screwed lid systems, which are in most cases equipped with double jacket metal seals with an inner spring wire to provide long term resistance to the seal compression force. Preservation of the high sealing quality of those seals under operational and accidental stress conditions is essentially important to the safety of those casks. Relative displacements of the lid system surfaces caused by specific impact scenarios cannot be excluded and have to be evaluated with respect to a possible increase in the leakage rate. To get representative data for such metal sealed lid systems, BAM has developed a special conceptualised flange system placed in an appropriate testing machine for relevant mechanical loading of the metal seals under static and cyclic conditions. Furthermore, the flange system enables continuous measurement of the standard helium leakage rate during each test. The primary aim of the investigation is to identify the correlation between variation of installation conditions (axial displacements) caused by external loads and the standard helium leakage rate. An essential parameter in this case is the useable resilience ru of a metal seal under relevant stress conditions. The useable resilience ru is the vertical difference in the cross-section between the seal's assembling status and the point where the leakage rate, by means of external load relieving, exceeds the quality criterion of 10-8 Pa m3 s-1. Load relieving can instantly occur due to modification of the seal groove dimension caused by accident impacts and deformation of the lid system. Furthermore, component specific basis data for the development of finite element calculation models should be collected. In the tests, seals are subjected to static and cyclic loads. All tests are performed at ambient temperature. This paper presents the test configuration, different test series and results of the current experiments. Typical load-displacement-leakage rate correlations are presented and discussed. Ashford Ramtrans Publ. 2008 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 19 1 47 52 10.1179/174651008X278948 2016-02-19 OPUS4-17542 Beitrag zu einem Tagungsband Probst, Ulrich; Hagenow, Peter; Völzke, Holger; Wolff, Dietmar; Wossidlo, Peter; Abbasi, Behboud; Achelpöhler-Schulte, Andreas; Schulz, Sebastian Investigation of seal effects according to axial compression variation of metal seals for transport and storage casks Institute of Nuclear Materials Management 2007 PATRAM 2007 - 15th International symposium on the packaging and transportation of radioactive materials (Proceedings) PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials Miami, Florida, USA 2007-10-21 2007-10-26 1 8 2016-02-19 OPUS4-17518 Posterpräsentation Probst, Ulrich Investigation of seal effects according to axial compression variation of coil spring metal seals 2007 Symposium; Packaging and Transportation of Radioactive Materials (PATRAM) Symposium; Packaging and Transportation of Radioactive Materials (PATRAM) Miami, FL, USA 2007-10-21 2007-10-26 2016-02-19 OPUS4-18430 Beitrag zu einem Tagungsband Goedecke, Thomas; Balke, Christian; Probst, Ulrich Test Facilities on the Open-Air Test Site of the Federal Institute for Materials Research and Testing (BAM) International Safe Transit Association (ISTA) / Institute of Packaging Professionals (IoPP) 2006 Dimensions. 06, The International Forum on Transport Packaging, April 18-21, 2006, San Antonio, Texas, USA Dimensions. 06, The International Forum on Transport Packaging San Antonio, Texas, USA 2006-04-18 2006-04-21 1 7 2016-02-19 OPUS4-29244 Zeitschriftenartikel Rolle, Annette; Droste, Bernhard; Schubert, Sven; Probst, Ulrich; Wille, Frank Verification of activity release compliance with regulatory limits within spent fuel transport cask assessment 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. Ashford Ramtrans Publ. 2012 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 23 3-4 149 152 10.1179/1746510913Y.0000000012 2016-02-20 OPUS4-29661 Beitrag zu einem Sammelband Jaunich, Matthias; Probst, Ulrich; Schulz, Sebastian; Wolff, Dietmar; Stark, Wolfgang Berger, K.-F.; Kiefer, S. Elastomere - Untersuchung des Tieftemperaturverhaltens im Dichtungseinsatz Aufgrund ihrer einfachen und zuverlässigen Anwendung werden Elastomere für viele Dichtungsaufgaben eingesetzt. In vielen Anwendungsbereichen, wie z.B. Verkehr, Luftfahrt und Verfahrenstechnik, können während des Einsatzes tiefe Temperaturen auftreten, bei denen die Funktionsfähigkeit der Dichtung erhalten bleiben muss. Daher ist die Untersuchung des Verhaltens von Elastomerdichtungen bei tiefen Temperaturen wichtig, um ihren Temperatureinsatzbereich nach unten abzugrenzen und dadurch einen verlässlichen Betrieb zu sichern. Ziel dieser Arbeit ist es, den sicheren Einschluss von gefährlichen Gütern unter verschiedenen Umgebungsbedingungen und über lange Zeiten zu ermöglichen bzw. die Materialauswahl entsprechend zu steuern. Mannheim ISGATEC GmbH 2013 Dichtungstechnik Jahrbuch 2014 978-3-9811509-7-1 82 91 2016-02-20 OPUS4-19786 Beitrag zu einem Tagungsband Sterthaus, Jens; Ballheimer, Viktor; Droste, Bernhard; Koch, Frank; Probst, Ulrich; Völzke, Holger; Wille, Frank Analysis of bolted flange joints for lids of packages for radioactive materials New York American Society of Mechanical Engineers 2009 PVP2009 - ASME 2009 Pressure vessels and piping conference (Proceedings) ASME 2009 Pressure vessels and piping conference Prague, Czech Republic 2009-07-26 2009-07-30 PVP2009-77284, 1-8 2016-02-19 OPUS4-19758 Zeitschriftenartikel Probst, Ulrich; Droste, Bernhard; Mallon, Michael; Schön, W. Untersuchungen zur Wirksamkeit der Brandschutzisolierung von Flüssiggas-Lagertanks Villingen-Schwenningen Neckar-Verl. Landesfeuerwehrverband Baden-Württemberg 1987 Brandhilfe - Fachzeitschrift für Feuerwehren und Rettungswesen 9 267 272 2016-02-19 OPUS4-21688 Zeitschriftenartikel Droste, Bernhard; Probst, Ulrich; Wieser, Günter Brennbare Gase sicher lagern - Untersuchungen mit einer Intumeszenz-Brandschutzbeschichtung für Flüssiggastanks Düsseldorf Springer-VDI-Verl. 1991 Technische Überwachung 2 59 66 2016-02-19 OPUS4-21822 Beitrag zu einem Tagungsband Droste, Bernhard; Wieser, Günter; Probst, Ulrich Thermal test requirements and their verification by different test methods This paper describes a new propane - fired test facility and the results of tests with a big vessel calorimeter to demonstrate compliance with the IAEA thermal test requirements. International Atomic Energy Agency 1992 PATRAM ´92 - 10th International symposium on the packaging and transportation of radioactive materials (Proceedings) 3 PATRAM ´92 - 10th International symposium on the packaging and transportation of radioactive materials Yokohama, Japan 1992-09-13 1992-09-18 1263 1272 2016-02-19 OPUS4-21860 Zeitschriftenartikel Droste, Bernhard; Probst, Ulrich CASTOR-Behälter im Explosionsbereich eines Propan-Kesselwagens Die Bundesanstalt für Materialforschung und -prüfung (BAM) führte am 27. April 1999 auf ihrem Prüfgelände in Horstwalde (südlich von Berlin) einen Brandversuch mit einem 45-m³-Kesselwagen, der mit 10 m³ (5,1 t) Propan gefüllt war, durch. Dieser Versuch sollte Erkenntnisse liefern zur Beurteilung des thermischen Verhaltens von Flüssiggastanks in einem Unfallfeuer und Hinweise zur Ableitung von Katastrophenschutzmaßnahmen geben. Über Versuchsaufbau, -durchführung und -ergebnisse bezüglich des Propan-Kesselwagens wurde in dieser Zeitschrift berichtet [1]. Düsseldorf Springer-VDI-Verl. 2001 Technische Überwachung 42 11/12 15 17 2016-02-19 OPUS4-20707 Beitrag zu einem Tagungsband Völzke, Holger; Wolff, Dietmar; Probst, Ulrich Advanced investigations to evaluate spent fuel cask safety for extended storage periods Institute of Nuclear Materials Management (INMM) 2009 50th Annual Meeting of the Institute of Nuclear Materials Management INMM (Proceedings) 50th Annual Meeting of the Institute of Nuclear Materials Management (INMM) Tucson, Arizona, USA 2009-07-12 2009-07-16 1 10 2016-02-19 OPUS4-20708 Zeitschriftenartikel Schubert, Sven; Probst, Ulrich; Winkler, H. P. Behaviour of metallic seals in CASTOR casks under normal and accident conditions of transport: qualification requirements Ashford Ramtrans Publ. 2009 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 20 4 179 182 10.1179/174651009X12555104004055 2016-02-19 OPUS4-26498 Beitrag zu einem Tagungsband Rolle, Annette; Probst, Ulrich; Ballheimer, Viktor; Müller, Karsten; Winkler, H. P. Transport condition effects on the sealing system and activity release within spent fuel transport casks Nuclear institute (ni) 2012 RAMTRANSPORT 2012 - 9th International Conference on the Radioactive Materials Transport and Storage (Proceedings) RAMTRANSPORT 2012 - 9th International Conference on the Radioactive Materials Transport and Storage London, UK 2012-05-22 2012-05-24 1 9(?) 2016-02-19 OPUS4-30136 Beitrag zu einem Tagungsband Völzke, Holger; Wolff, Dietmar; Probst, Ulrich; Nagelschmidt, Sven; Schulz, Sebastian Long-term performance of metal seals for transport and storage casks Dual purpose casks for the transportation and storage of spent nuclear fuel and other radioactive materials require very high leak-tightness of lid closure Systems under accident conditions as well as in the long-term to prevent activity release. For that purpose metal seals of specific types with an inner helical spring and outer metal liners are widely used and have shown their excellent performance if certain quality assurance requirements for fabrication and assembling are satisfied. Well defined surface roughness, clean and dry inert conditions are therefore essential. No seal failure in a loaded cask happened under these conditions until today. Nevertheless, the considered and licensed Operation period is limited and all safety assessments have been performed and approved for this period of time which is 40 years in Germany so far. But in the meantime longer storage periods might be necessary for the future and therefore additional material data will be required. BAM is involved in the qualification and evaluation procedures of those seals from the early beginning. Because long-term tests are always time consuming BAM has early decided to perform additional tests with specific test seal configurations to gain a better understanding of the long-term behavior with regard to seal pressure force, leakage rate and useable resilience which is safety relevant mainly in case of accidental mechanical loads inside a storage facility or during a subsequent transport. Main test parameters are the material of the outer seal jacket (silver or aluminum) and the temperature. This paper presents the BAM test program including an innovative test mock-up and most recent test results. Based on these data extrapolation models to extended time periods are discussed, and also future plans to continue tests and to investigate seal behavior for additional test parameters are explained. Omnipress Institute of Nuclear Materials Management (INMM) 2013 PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials (Proceedings) PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials San Francisco, CA, USA 18.08.2013 23.08.2013 1 13 2016-02-20 OPUS4-28912 Beitrag zu einem Sammelband Probst, Ulrich; Schulz, Sebastian; Jaunich, Matthias; Wolff, Dietmar; Völzke, Holger Berger, K.-F.; Kiefer, S. Langzeituntersuchungen an Metalldichtungen mit innen liegendem Federkern und doppelter Ummantelung In Deutschland werden in Transport- und Lagerbehältern (TLB) wärmeentwickelnde radioaktive Abfälle gegenwärtig über einen Zeitraum von bis zu 40 Jahren zwischengelagert. Aufgrund der Situation der noch nicht abgeschlossenen Endlagersuche werden hier möglicherweise Verlängerungen in Betracht zu ziehen sein. Im Deckeldichtsystem der TLB werden in der Regel Metalldichtungen vom Typ Helicoflex® eines französischen Herstellers verwendet, die aus einem innen liegenden Spiralfederkern und zwei Ummantelungen bestehen. Die Ermittlung der Fliess- und Relaxationseigenschaften der Dichtungskomponenten über den vorgesehenen langen Betriebseitraum sind vor dem Hintergrund des Erhalte eines geforderten hohen Dichtniveaus ein wichtiger Untersuchungsgegenstand. Mannheim ISGATEC GmbH 2013 Dichtungstechnik Jahrbuch 2014 978-3-9811509-7-1 1 11 2016-02-20 OPUS4-56399 Beitrag zu einem Sammelband Goral, Milan; Kömmling, Anja; Probst, Ulrich; Wossidlo, Peter; Jaunich, Matthias; Wolff, Dietmar; Völzke, Holger Langzeitversuche über 10 Jahre an Federkern-Metalldichtungen mit Aluminium- bzw. Silberummantelungen Federunterstützte Metalldichtungen mit Aluminium(Al)- oder Silber(Ag)-Ummantelung werden u.a. in Behältern für Wärme entwickelnde radioaktive Abfälle eingesetzt, da diese Dichtungen eine sehr gute Dichtheit gewährleisten sowie Langlebigkeit und Beständigkeit gegenüber erhöhten Temperaturen und radioaktiver Strahlung aufweisen. Auch wenn die Sicherheit solcher Behälter und der verwendeten Dichtungen vielfach belegt wurde, sind sie Gegenstand andauernder Forschung, etwa im Hinblick auf eine absehbar benötigte verlängerte Zwischenlagerdauer. Aus diesem Grund werden an der Bundesanstalt für Materialforschung und -prüfung (BAM) im Fachbereich 3.4 „Sicherheit von Lagerbehältern" seit über 20 Jahren Versuche an solchen Metalldichtungen durchgeführt. Dabei sollen zusätzliche Erkenntnisse hinsichtlich der Sicherheitsreserven der Dichtungen in unterstellten Störfallszenarien (axiale Bewegung des Deckelsystems bzw. Aufweitung der Nutgeometrie) und insbesondere detailliertere Erkenntnisse zum Langzeitverhalten gewonnen werden. Mannheim ISGATEC GmbH 2023 JAHRBUCH Dichten. Kleben. Polymer. 2023 2023 43 63 2022-11-28 OPUS4-36393 Beitrag zu einem Tagungsband Droste, Bernhard; Hübner, Heinz W.; Probst, Ulrich Qualification and Certification Criteria of Casks for the Intermediate Dry Storage of Spent Fuel in the Federal Republic of Germany 1983 Packaging and transportation of radioactive materials 1 7th International symposium Packaging and Transportation of Radioactive Materials New Orleans, La., USA 15.05.1983 20.05.1983 224 230 2016-06-08 OPUS4-36395 Beitrag zu einem Tagungsband Droste, Bernhard; Hübner, Heinz W.; Probst, Ulrich Selection and certification of materials for casks intended for the transport and intermediate storage of spent fuel 1983 Packaging and transportation of radioactive materials 2 7th International symposium Packaging and Transportation of Radioactive Materials New Orleans, La., USA 15.05.1983 20.05.1983 1048 1054 2016-06-08 OPUS4-32072 Beitrag zu einem Tagungsband Wolff, Dietmar; Jaunich, Matthias; Probst, Ulrich; Nagelschmidt, Sven Understanding the long-term behavior of sealing systems and neutron shielding material for extended dry cask storage In Germany, the concept of dry interim storage in dual purpose metal casks before disposal is being pursued for spent nuclear fuel (SF) and high active waste (HAW) management. However, since there is no repository available today, the initially planned and established dry interim storage license duration of up to 40 years will be too short and its extension will become necessary. For such a storage license extension it is required to assess the long-term performance of SF and all safety related storage system components in order to confirm the viability of extended storage. The main safety relevant components are the thick-walled dual purpose metal casks. These casks consist of a monolithic cask body with integrated neutron shielding components (polymers, e.g. polyethylene) and a monitored double lid barrier system with metal and elastomeric seals. The metal seals of this bolted closure system guarantee the required leak-tightness whereas the elastomeric seals allow for leakage rate measurement of the metal seals. This paper presents an update on running long-term tests on metal seals at different temperatures under static conditions over longer periods of time. In addition, first results of our approach to understand the aging behavior of different elastomeric seals and neutron radiation shielding material polyethylene are discussed. 2014 PSAM 12 - Probabilistic safety assessment and management (Proceedings) PSAM 12 - Probabilistic safety assessment and management Honolulu, Hawaii, USA 22.06.2014 27.06.2014 1 9 2016-02-20 OPUS4-31947 Beitrag zu einem Tagungsband Shirai, K.; Namba, K.; Wataru, M.; Völzke, Holger; Wolff, Dietmar; Probst, Ulrich; Jaunich, Matthias; Schulz, Sebastian Numerical evaluation of the long-term sealing performance of the silver gasket for dual purpose metal cask under high temperature It is important to evaluate the effect of thermal ageing on the sealing performance of metal gaskets under high temperature for long-term usage. Therefore, in order to gain representative data for this kind of metal-sealed lid System, BAM is currently performing laboratory tests of different gasket types with aluminum and silver jackets at three different temperatures under static conditions up to four years so far, using test flanges for gaskets with full scale cross section diameter but much smaller outer diameter. On the other hand, in order to investigate the applicability of the numerical methodology to evaluate the long-term behavior of the metal gaskets, such as a correlation between seal pressure force and holding time, CRIEPI is developing a modeling method including material tests (tensile and creep tests) at high temperature. In this paper, the applicability of the finite element method (ABAQUS) to predict the recovery displacement and residual seal pressure force of the gasket complex was verified by comparing the calculated values with BAM's laboratory test results under the joint research agreement between BAM and CRIEPI. Omnipress Institute of Nuclear Materials Management (INMM) 2013 PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials (Proceedings) PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials San Francisco, CA, USA 18.08.2013 23.08.2013 1 8 2016-02-20 OPUS4-19021 Zeitschriftenartikel Droste, Bernhard; Hübner, Heinz W.; Probst, Ulrich Brandversuche mit Tanks zur oberirdischen Lagerung von Flüssiggas Düsseldorf Springer-VDI-Verl. 1984 Technische Überwachung 25 6 272 276 2016-02-19 OPUS4-19876 Beitrag zu einem Tagungsband Schön, W.; Probst, Ulrich; Droste, Bernhard Experimental investigations of fire protection measures for LPG storage tanks Oslo European Federation of Chemical Engineering Norwegian Society of Chartered Engineers 1989 6th international symposium on loss prevention and safety promotion in the process industries (Proceedings) 4 6th international symposium on loss prevention and safety promotion in the process industries Oslo, Norway 1989-06-19 1989-06-22 51/1 51/17 2016-02-19 OPUS4-21560 Beitrag zu einem Tagungsband Wieser, Günter; Droste, Bernhard; Martens, B.-R.; Probst, Ulrich; Schreiber, D.; Völzke, Holger Droste, B.; Kowalewsky, H. Thermal test of a cubic ductile cast iron container filled with an ion exchanger resin Paris, France Nuclear Technology Publishing International Atomic Energy Agency, the U.S. Department of Energy 1998 PATRAM ´98 - 12th International conference on the packaging and transportation of radioactive materials (Proceedings) 1 PATRAM 98 - 12th International conference on the packaging and transportation of radioactive materials Paris, France 1998-05-10 1998-05-15 429 435 2016-02-19 OPUS4-21555 Zeitschriftenartikel Droste, Bernhard; Probst, Ulrich; Heller, Winfried Impact of an exploding LPG rail tank car onto a CASTOR spent fuel cask Ashford Ramtrans Publ. 1999 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 10 4 231 240 2016-02-19 OPUS4-23890 Zeitschriftenartikel Erhard, Anton; Völzke, Holger; Probst, Ulrich; Wolff, Dietmar Aging management for long-term interim storage casks The aging management system for the mechanical components of nuclear power plants (NPPs) must be established and used by the licensee in such a way that the quality of safety relevant components is guaranteed for the completely designed lifetime of the NPP. This demands an extensive plant life management with special emphases on the knowledge of the degradation in material properties. The basic safety concept in Germany observes this circumstance. Lifetime extension of the German NPPs is an aim of the current valid coalition agreement of the German government. Operational extension of interim storage facilities requires, in comparison to the aging management system for NPP, an aging management system adapted to the Special circumstances of spent fuel storage casks. Extension of interim storage periods for spent fuel casks beyond the designed lifetime requires, in comparison to the components of an NPP, an increasing knowledge of material degradation with potential impact on cask integrity, e.g. leak tightness. Dry interim storage in Germany has been approved for 40 years. After that time, according to the present strategy, a final repository should be available. However, until now, such a final facility still does not exist, and the German exploration and licensing process is heavily delayed. Currently, discussions are continuing regarding further exploration of the Gorleben salt mine. There is willingness to overcome this situation that is clearly described in the available coalition agreement of the federal government. Anyway, however, the prediction is viewed; a repository for heat generating radioactive waste in Germany will not be available in the near future and may not be available when first storage facilities and casks reach their 40 years of approved lifetime, which will occur in ~25 years starting from now. Therefore, the question must be asked: what has to be done with the existing storage casks in the interim facilities? May these casks be fit for continued use, with an extension of the storage period? One option is to have an aging management system, which creates enough information about the technical condition of safety relevant cask properties. This is the basis for safety evaluation for extended storage periods. In the present paper, possible aging mechanisms for high level waste storage casks are discussed, as well as the influence of the time dependent changes of the component properties. Ashford Ramtrans Publ. 2011 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 22 1 46 53 10.1179/1746510910Y.0000000013 2016-02-19 OPUS4-23907 Beitrag zu einem Tagungsband Erhard, Anton; Völzke, Holger; Probst, Ulrich; Wolff, Dietmar Ageing management for long term interim storage casks PATRAM 2010 PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials (Proceedings) PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials London, UK 2010-10-03 2010-10-08 1 17 (Tuesday/T20/61) 2016-02-19 OPUS4-24173 Beitrag zu einem Tagungsband Völzke, Holger; Probst, Ulrich; Wolff, Dietmar; Nagelschmidt, Sven; Schulz, Sebastian Investigations on the long term behavior of metal seals for spent fuel storage casks Metal seals are in common use as an essential component for the leak tight closure of transport and storage casks for spent fuel and vitrified high active waste from reprocessing. They are placed between the massive monolithic cask body made of ductile cast iron or forged steel and the primary and secondary lids, which are fixed with screws around the lid circumference, in order to ensure long term safe enclosure of the radioactive cask inventory. Hereby, long term reliable pressure forces in combination with a tight surface contact are as important as well maintained seal and surface qualities and dry and clean conditions during seal assembly and operation. A few years ago BAM started systematic investigation on the long term seal behavior with re-spect to longer storage periods and seal behavior in accidental cask scenarios with dynamic de-formations of the seal groove geometry or short term drop in pressure force up to lid lifting. BAM has developed test flanges for seals with full scale cross section diameter but much small-er outer diameter to gain representative data for metal-sealed lid systems. They are placed in appropriate testing machines for relevant mechanical loading under static and dynamic condi-tions with the ability to measure the standard helium leakage rate continuously during each test phase. This paper focuses on BAM long term tests of different seal types with aluminum and silver jackets at three different temperatures of +20°C, +100°C and +150°C under static conditions over longer periods of time. Due to creeping effects, a reduction of the pressure force does ap-pear during loading and unloading depending on prior holding times. So far, test results of up to 2 years indicate a clear correlation between seal pressure forces and holding time, temperature and seal type allowing for extrapolating to much longer periods of time. The paper presents basic correlations, test and evaluation procedures as well as important provisional results and gives an outlook on further investigations. Institute of Nuclear Materials Management (INMM) 2011 52nd INMM Annual meeting (Proceedings) 52nd INMM Annual meeting Palm Desert, CA, USA 17.07.2011 21.07.2011 1 9 2016-02-19 OPUS4-19117 Zeitschriftenartikel Droste, Bernhard; Probst, Ulrich; Mallon, Michael; Schön, W. Flüssiggastanks im Unfallfeuer Essen VVA Kommunikation GmbH Hessisches Ministerium des Innern und für Sport 1986 Florian Hessen : Zeitschrift für die Feuerwehren 5 8 9 2016-02-19 OPUS4-19103 Zeitschriftenartikel Droste, Bernhard; Mallon, Michael; Probst, Ulrich; Schön, W. Flüssiggasanlagen - Brandschutz-Wärmedämmung kann die Sicherheit für die Umgebung verbessern Düsseldorf Verl.-Gruppe Handelsblatt 1985 Handelsblatt 41 26 1 2(?) 2016-02-19 OPUS4-21738 Forschungsbericht Probst, Ulrich; Droste, Bernhard Untersuchung von Brandschutzmassnahmen - Instrumentierte Brandversuche an 4850 l-Flüssiggas-Lagertanks mit Wärmeschutz-Isolierung und zwei Sicherheitsventilen im Heizölfeuer Berlin Bundesanstalt für Materialforschung und -prüfung (BAM), Berlin 1988 Ermittlung sicherheitstechnischer Kriterien zur Flüssiggastechnologie und Herleitung geeigneter Sicherheitsstandards Fachband 5.2 Bericht 01501 1 92 2016-02-19 OPUS4-21728 Beitrag zu einem Tagungsband Dreisvogt, H.; Droste, Bernhard; Völzke, Holger; Probst, Ulrich Dry interim spent fuel storage casks - Licensing, evaluation and operational experience Vienna, Austria International Atomic Energy Agency 1995 International symposium on safety and engineering aspects of spent fuel storage (Proceedings) International symposium on safety and engineering aspects of spent fuel storage Vienna, Austria 1994-10-10 1994-10-14 IAEA-SM-335/35 355 368 2016-02-19 OPUS4-21699 Zeitschriftenartikel Droste, Bernhard; Mallon, Michael; Probst, Ulrich Neuartige Brandschutzbeschichtungen für Flüssiggas-Lagertanks Düsseldorf Springer-VDI-Verl. 1990 Technische Überwachung 31 5 219 224 2016-02-19 OPUS4-38039 Beitrag zu einem Tagungsband Nagelschmidt, Sven; Probst, Ulrich; Völzke, Holger; Wolff, Dietmar Long-term investigations of metal seals for storage casks of radioctive materials The Bundesanstalt für Materialforschung und -prüfung (BAM) is a federal institute for materials research and testing in Germany and has been involved in the qualification and safety evaluation procedures of metal seals from the early beginning of the interim storage licensing procedures for radioactive materials, stored in dual purpose casks. Regarding this subject, BAM investigates the long-term behavior of metal seals under the influence of temperature using experimental data and analytical approaches. The development of numerical models is in progress as well. Systematic experimental investigations performed by BAM indicate a continuous decrease of the remaining seal force and the usable resilience considering the leak tightness. Hence, there is a fundamental interest of describing time and temperature dependency to gain predictable values for the long-term behavior and to achieve reliable results with help of short-term tests. The paper gives an overview about the sealing principle, test program and test results of metal seals of the type HELICOFLEX® HN200. The aging effect, respectively the long-term behavior in dependency of time and temperature, are introduced for two different outer liner materials, aluminum and silver. American society of mechanical engineers (ASME) 2016 Pressure Vessels and Piping Conference (PVP) - ASME Conference Proceedings 7 978-0-7918-5045-9 PVP ASME Conference Vancouver, Canada 17.07.2016 21.07.2016 63596-1 63596-5 2016-11-30 OPUS4-32193 Beitrag zu einem Tagungsband Rolle, Annette; Droste, Bernhard; Schubert, Sven; Probst, Ulrich; Wille, Frank Verification of activity release compliance with regulatory limits within spent fuel transport casks PATRAM 2010 PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials (Proceedings) PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials London, UK 2010-10-03 2010-10-08 1 8(?) 2016-02-20 OPUS4-32194 Beitrag zu einem Tagungsband Rolle, Annette; Winkler, H. P.; Probst, Ulrich; Ballheimer, Viktor; Neumeyer, Tino Verification of design leakage rates for activity release calculation 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 sealing system of transport casks for spent fuel and high radioactive waste. Applicants are requested by BAM to provide test programmes for verification of design leakage rates of the sealing system under the possible loads. Two test series initiated to clarify the dependency of the standard leakage rate on dynamic lid displacement as well as the dependency of the useful elastic recovery ru of a metallic seal on temperature and time, are outlined in this paper as examples of present investigations: Sliding tests simulating a lid displacement possible by a horizontal drop of the cask are carried out at the controlled drop test facility of BAM with test flange pairs equipped with metallic Helicoflex seals. For specification of covering values for the useful elastic recovery ru GNS has started a very comprehensive test programme with overall 70 metallic seals installed in test flanges which are stored for a period of one year at three different temperatures up to 150°C. This paper gives an overview about the current approach of BAM in the assessment of cask tightness and informs about the status of the running test series. Omnipress Institute of Nuclear Materials Management (INMM) 2013 PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials (Proceedings) PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials San Francisco, CA, USA 2013-08-18 2013-08-23 1 7 2016-02-20 OPUS4-33428 Zeitschriftenartikel Droste, Bernhard; Komann, Steffen; Wille, Frank; Rolle, Annette; Probst, Ulrich; Schubert, Sven Consideration of aging mechanism influence on transport safety of dual purpose casks for spent nuclear fuel of HLW 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'. Ashford Ramtrans Publ. 2014 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 25 3-4 105 112 10.1179/1746510914Y.0000000070 2016-02-20 OPUS4-32518 Beitrag zu einem Tagungsband Droste, Bernhard; Komann, Steffen; Wille, Frank; Rolle, Annette; Probst, Ulrich; Schubert, Sven Considerations of aging mechanisms influence on transport safety and reliability of dual purpose casks for spent nuclear fuel or HLW 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'. 2014 PSAM 12 - Probabilistic safety assessment and management (Proceedings) PSAM 12 - Probabilistic safety assessment and management Honolulu, Hawaii, USA 22.06.2014 27.06.2014 1 10 2016-02-20 OPUS4-32327 Zeitschriftenartikel Völzke, Holger; Wolff, Dietmar; Probst, Ulrich; Nagelschmidt, Sven; Schulz, Sebastian Long term performance of metal seals for transport and storage casks Dual purpose casks for the transportation and storage of spent nuclear fuel and other radioactive materials require very high leak tightness of lid closure systems under accident conditions as well as in the long term to prevent activity release. For that purpose metal seals of specific types with an inner helical spring and outer metal liners are widely used and have shown their excellent performance if certain quality assurance requirements for fabrication and assembling are satisfied. Well defined surface roughness, clean and dry inert conditions are therefore essential. No seal failure in a loaded cask happened under these conditions until today. Nevertheless, the considered and licensed operation period is limited and all safety assessments have been performed and approved for this period of time which is 40 years in Germany so far. However, in the meantime longer storage periods might be necessary for the future and therefore additional material data will be required. BAM is involved in the qualification and evaluation procedures of those seals from the early beginning. Because long term tests are always time consuming BAM has early decided to perform additional tests with specific test seal configurations to gain a better understanding of the long term behaviour with regard to seal pressure force, leakage rate and useable resilience which is safety relevant mainly in case of accidental mechanical loads inside a storage facility or during a subsequent transport. Main test parameters are the material of the outer seal jacket (silver or aluminium) and the temperature. This paper presents the BAM test program including an innovative test mock-up and most recent test results. Based on these data extrapolation models to extended time periods are discussed, and also future plans to continue tests and to investigate seal behaviour for additional test parameters are explained. Ashford Ramtrans Publ. 2014 Packaging, transport, storage & security of radioactive materials (RAMTRANS) 25 1 8 15 10.1179/1746510914Y.0000000057 2016-02-20 OPUS4-36579 Beitrag zu einem Tagungsband Wieser, Karol E.; Tobisch, Karl; Probst, Ulrich The elastomere gasket - a black sheep for quality assurance measures? 1983 Packaging and transportation of radioactive materials 2 7th International symposium Packaging and Transportation of Radioactive Materials New Orleans, La., USA 15.05.1983 20.05.1983 1366 1369 2015-12-31 OPUS4-45452 Beitrag zu einem Tagungsband Grelle, Tobias; Wolff, Dietmar; Probst, Ulrich; Jaunich, Matthias; Völzke, Holger Component and material investigations on metal seals for high level radioactive waste containers In Germany casks for interim storage of spent nuclear fuel and high level radioactive waste are equipped with Helicoflex® metal seals as main sealing barrier of the double lid system. The long-term behaviour of those seals is investigated at Bundesanstalt für Materialforschung und -prüfung (BAM) in order to evaluate the safety function of the containment at different temperatures over storage periods of 40 years or more in case extended interim storage becomes necessary. Long-term investigations have been done for ageing times of up to 8.5 years at temperatures ranging from room temperature to 150 °C. It was found that the seal force and useable resilience decrease over time, which is mainly caused by creep deformation of the aluminium (or silver) outer jacket of the seals. This effect becomes stronger with increasing temperature. The ageing processes of the seal material and the overall seal behaviour is under investigation in order to derive analytical descriptions for the long-term seal performance. Thus, standardized tests on the basic seal materials, with focus on aluminium, and additional investigations on the seals as a component are conducted. The current investigations include compression and tension creep measurements as well as tensile testing. Furthermore, ageing of seal segments provides information on the development of the contact area width, jacket thickness and microstructural changes in dependence of time and temperature. The obtained data are used for the development of material models and an analytical approach to describe and predict the time and temperature dependent sealing behaviour in the long-term. 2018 11th International Conference on the Transport, Storage and Disposal of radioactive Materials 11th International Conference on the Transport, Storage and Disposal of Radioactive Materials London, UK 15.05.2018 17.05.2018 18535, 1 6 2018-07-12 OPUS4-48206 Zeitschriftenartikel Grelle, Tobias; Wolff, Dietmar; Probst, Ulrich; Jaunich, Matthias; Völzke, Holger Component and material investigations on metal seals for high level radioactive waste containers Long-term investigations performed at BAM look to extend the state of knowledge on safety-related components of interim storage containers. Metal seals act as the primary sealing barrier in the bolted double lid closure system of the containers. The behaviour of metal seals has been investigated for ageing times up to 8.5 years and for various temperatures. The main cause for reduction in useable resilience overtime was due to creep deformation of the outer jacket of the seal. London Nuclear Institute 2018 Nuclear future 32 34 2019-06-14 OPUS4-30821 Beitrag zu einem Tagungsband Nagelschmidt, Sven; Herbrich, Uwe; Probst, Ulrich; Wolff, Dietmar Van Breugel, K.; Koenders, E.A.B. Evaluation of test results with regard to ageing mechanisms of metal seals in casks for dry storage of spent nuclear fuel Metal seals are widely used for extreme applications, e.g. in dual-purpose casks for dry interim storage of spent nuclear fuel in Germany. Due to the fact that interim storage must be safe at least for the approved period of 40 years there is a major interest to investigate the long-term behaviour and ageing mechanisms of metal seals. Experimental analyses indicate a time and temperature dependency of seal characteristics. This dependency was researched with a time- and temperature parameterization based up on Larson-Miller. The paper describes the derivation of the material parameter C from test results and the applicability of the Larson-Miller-Relationship for those metal seals in principle. Overall a constant material parameter C was not. Nevertheless, an approach comparable to the Larson-Miller-Parameter was developed. TU Delft 2014 AMS 14 - Ageing of materials & structures - Proceedings of the 1st ageing of materials & structures 2014 conference 978-94-6186-313-3 1st Ageing of materials & structures 2014 conference Delft, The Netherlands 26.05.2014 28.05.2014 126 133 2016-02-20 OPUS4-49019 Beitrag zu einem Tagungsband Grelle, Tobias; Probst, Ulrich; Wolff, Dietmar; Jaunich, Matthias; Völzke, Holger Investigations on the long-term behavior of metal seals for dual purpose casks In Germany, spent nuclear fuel and high active waste from reprocessing is stored in transport and storage containers with double lid systems that are equipped with metal seals completing the primary sealing barrier. The tasks of the Bundesanstalt für Materialforschung und -prüfung (BAM) within the interim storage licensing procedures ruled by the German Atomic Energy Act include the long-term safety evaluation of the container design regarding the permanently safe enclosure of the inventory. In order to generate a knowledge base for the safety evaluation, research regarding the long-term behavior of the critical components is performed. So far, the containers are licensed for an interim storage period of 40 years. However, due to significant delays in establishing a final repository, the required time span for interim storage is expected to increase significantly. Thus, a widespread investigation program is run to gain systematic data on the long-term behavior of the seals and to develop prediction models. Long-term seal investigations consider the development of their restoring seal force, their useable resilience and their achievable leakage rate caused by aging at temperatures ranging from room temperature up to 150 °C. This year, the total time span of the tests reaches 10 years. Furthermore, seal segments are aged at the selected temperatures for up to 300 days. From these segments additional information on the sealing behavior, changes of the seal contact and the material behavior is gained. This contribution deals with the current results of the long-term seal investigations at BAM. Furthermore, insights of the more in-depth component and material investigations of the metal seals with focus on the seal contact development are discussed and the ongoing work aiming for an analytical description of the thermo-mechanical aging effects on metal seals are presented. 2019 Proceedings of the 19th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 2019 19th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 2019 New Orleans, LA, USA 04.08.2019 1 6 2019-09-20 OPUS4-43418 Beitrag zu einem Tagungsband Grelle, Tobias; Wolff, Dietmar; Probst, Ulrich; Jaunich, Matthias; Völzke, Holger Investigation programme for evaluation and prediction of the long-term behaviour of Helicoflex® metal seals In Germany, for the transport and storage of spent nuclear fuel, casks with double closure lid systems are used, which are equipped with Helicoflex® metal seals. The original interim storage period for these casks was planned to be 40 years. However, recent political developments indicate that a storage time of more than 80 years might be necessary. Therefore, the current storage licenses have to be renewed in due course, which requires extended knowledge of the long-term behaviour of all cask components. At the Bundesanstalt für Materialforschung und -prüfung (BAM), metal seals have been investigated after ageing at temperatures between room temperature and 150 °C for up to 7 years. At regular intervals the seals have been tested for leakage rate as well as for their mechanical behaviour. From these tests pronounced influence of ageing could be shown which results in the decrease of the seal force and the useable resilience. The main reason attributed to these performance changes is the increasing permanent deformation of the outer layer of the seal due to creep. So far, an explicit analytical description of the long-term behaviour that could be used for predictions exceeding the tested ageing times and temperatures was not suitable. In addition to the component tests that were already conducted, a comprehensive investigation programme has been started to describe the mechanical behaviour of the individual seal components. The individual seal components are tested regarding different material characteristics including creep, deformation and microstructural properties. The comparability of the material characterization is ensured by comparing the basic raw material of the specimen with the actual component material. Furthermore, detailed investigations of the time and temperature dependent deformation behaviour are realized by ageing seal segments at multiple temperatures for different periods of time and employing standardized tests. By analysing the acquired data in combination with the ongoing long-term component tests a dataset for analytical prediction of the long-term behaviour of the seals is intended for an extended period of time under a certain temperature regime. INFORUM Verlags- und Verwaltungsgesellschaft mbH 2017 48th Annual Meeting on Nuclear Technology (AMNT 2017) Proceedings 48th Annual Meeting on Nuclear Technology (AMNT 2017) Berlin, Germany 16.05.2017 17.05.2017 1 7 2018-02-19 OPUS4-45844 Beitrag zu einem Tagungsband Grelle, Tobias; Probst, Ulrich; Jaunich, Matthias; Skrotzki, Birgit; Wolff, Dietmar Creep investigations on aluminum seals for application in radioactive waste containers In Germany spent nuclear fuel and high level radioactive waste is 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. The used metal seals consist of three components as can be seen in the cross-sectional view in Figure 1. The innermost part is a helical spring that is surrounded by an inner jacket made of stainless steel. The outer jacket that is made of a softer material which in case of assembly in the aforementioned storage containers is silver or aluminum (i.e. Al 99.5). During application the seal is compressed and due to the restoring force of the helical spring, the outer jacket is plastically deformed and adapts to the sealing surface. Hence, leakage paths are closed and the sealing function is generated. In Germany the above-mentioned containers are licensed for up to 40 years of interim storage, which in case extended storage becomes necessary before a final repository is available will have to be extended to even longer periods. Therefore, the evaluation of the long-term behavior of the seals is necessary, taking into account storage conditions, decay heat and possible mechanical loads as well. At Bundesanstalt für Materialforschung und -prüfung (BAM) long-term investigations are being conducted in which seals are assembled in test flanges and aged at temperatures ranging from room temperature to 150°C for accelerated aging. The aged seals are tested semi-annually (after the first 6 months in which the seals are tested more frequently) regarding the sealing performance, the remaining seal force, and the useable resilience upon decompression. Results of these investigations have been published over the past years (e.g. Grelle, Wolff, Probst, Jaunich, & Völzke, 2017; Völzke, Wolff, Probst, Nagelschmidt, & Schulz, 2014). It was found that the seal force and the useable resilience decrease with time and temperature, which is in agreement with the result of other studies (Sassoulas et al., 2006; Wataru et al., 2016) as well. Geometry change of the outer jacket has been identified as the main reason for this seal behavior. At the prevailing operating temperatures and stresses the aluminum is subjected to creep deformation leading to a thinning of the outer jacket. Since the seal groove depth remains unchanged the helical spring expands, which in turn leads to a decrease of the generated spring and seal force. Although the main reason for the change of seal parameters over time and temperature is known, a detailed characterization of the seal behavior and a reliable prediction of the parameter development for aging times that exceed the experimental time frame have not been possible, yet. For deeper understanding of the aging processes, an Investigation program, which is covered in this contribution, is conducted at Bundesanstalt für Materialforschung und -prüfung (BAM) that focusses on the behavior of the aluminum jacket and its influence on the long-term sealing performance. The program investigates properties of material samples as well as the behavior of the seal as a component. Original sheet material of the same aluminum that is used for manufacturing of the seals is investigated in compression creep tests. For this, a DMA (dynamic mechanical analysis) machine is employed (here used for static tests) that allows for a measurement of the specimens deformation under forces of up to 500 N. The advantage of this method is that the original material can be tested in the same shape as used for the seals which is 0.5 mm thick sheet material. For investigation of tensile creep standard specimens are used, that were machined from surrogate material of the same composition and annealing condition. Furthermore, aluminum seals that are cut into smaller segments are assembled in flanges and placed in heating chambers at temperatures ranging from 23°C to 150°C. After different periods of time from 3 days to 300 days the segments are taken out of the flanges and are investigated, thus giving information on different states of aging. Measurements of the development of the seal contact width and the aluminum jacket thickness are done with an optical microscope. Further investigations on the segments will include metallography and hardness measurements. From the detailed material and component behavior including the results of the long-term seal force and useable resilience investigations a better understanding of the overall seal behavior can be gained. The aim is to contribute to the development of material models and analytical approaches for the prediction of the sealing behavior in dependence of time and temperature. 2018 Proceedings of the International Conference on Aluminum Alloys 2018 978-1-926872-41-4 International Conference on Aluminum Alloys Montreal, Canada 17.06.2018 1 2 2018-09-05 OPUS4-40611 Beitrag zu einem Tagungsband Grelle, Tobias; Wolff, Dietmar; Probst, Ulrich; Jaunich, Matthias; Völzke, Holger Material investigation and long-term sealing behavior of Helicoflex® metal seals used in containers for spent nuclear fuel In Germany spent nuclear fuel is stored and transported in casks that possess bolted lid systems equipped with double jacket metal seals of Helicoflex® type in order to enable safe enclosure of the radioactive inventory. A dry interim storage period of 40 years was planned and the casks are licensed for that time span. However, due to political reasons and delayed disposal projects this time span is expected to increase significantly. It is therefore necessary to evaluate the long-term sealing behavior of the casks exceeding 40 years of operating time. In this paper, we discuss our approach to investigate the aging behavior of such metal seals, and to predict the long-term sealing behavior. Accelerated aging component tests with seals are performed at temperatures up to 150°C to investigate the course of seal force, useable resilience and leakage rate. Even though these tests have already shown a significant decrease in seal force and useable resilience after aging times of less than 1 year, for most seals the leakage rate stayed better than the specified value. However, observation of the leakage rate has to be continued to determine the aging effect on the seal properties. As a main influence on the seal long-term behavior the increasing permanent deformation of the outer jacket has been recognized. It is made of aluminum or silver which means that the temperatures that are relevant for the aforementioned application in casks lead to creep deformation. For further investigation of seal behavior a comprehensive research program concerning the material characteristics and aging behavior of the individual seal components, with an emphasis on the outer jacket material, has been launched. The aim is to get a better understanding of the time and temperature dependent creep mechanisms and deformation. The examinations are separated into tests on seal segments and tests on standardized specimen. In order to be able to study the aging process, seal segments are compressed in flanges and stored at temperatures ranging from room temperature to 150°C. After defined time intervals the segments are analyzed by using standardized tests including structure investigation and creep tests. The results are compared with the behavior of the specimen basic raw material. This is done to ensure comparability of the thin jacket material and additional sheet material used for standardized tests. Thus, the prediction of component changes after different aging times at different temperatures can be made. As a result forecasts on the long term seal behavior are intended. 2017 Waste Management Symposia 2017 Proceedings 978-0-9828171-6-2 Waste Management Symposia Phoenix, AZ, USA 05.03.2017 Article 17135, 1 8 2017-06-16 OPUS4-41841 Beitrag zu einem Tagungsband Weber, Mike; Kömmling, Anja; Jaunich, Matthias; Wolff, Dietmar; Zencker, Uwe; Völzke, Holger; Schulze, Dietmar; Probst, Ulrich Testing and Numerical Simulation of Elastomers - From Specimen Tests to Simulation of Seal Behavior under Assembly Conditions Due to delays in the siting procedure to establish a deep geological repository for spent nuclear fuel and high level radioactive waste as well as in construction of the already licensed Konrad repository for low and intermediate level radioactive waste, extended periods of interim storage become more relevant in Germany. BAM is involved in most of the cask licensing procedures and especially responsible for the evaluation of cask-related long-term safety issues. The long-term performance of elastomer seals for lid systems of transport and storage casks, whether used as auxiliary seals in spent fuel casks or as primary seals for low and intermediate level waste packages, is an important issue in this context. The polymeric structure of these seals causes a complex mechanical behavior with time-dependent sealing force reduction. The results of a comprehensive purpose-designed test program consisting of basic compression and tension tests as well as relaxation tests on unaged specimens of representative types of elastomers (fluorocarbon rubber (FKM) and ethylene propylene diene rubber (EPDM)) at different temperatures and strain rates are presented. They were used to identify the constitutive behavior and to obtain parameters for finite element material models provided by the computer code ABAQUS®. After estimating the influence of uncertainties such as Poisson's ratio and friction coefficient by sensitivity analyses, the chosen parameters had to prove their suitability for the finite element simulation of the specimen tests themselves. Based on this preliminary work the simulation of a specific laboratory test configuration containing a typical elastomer seal with circular cross section is presented. The chosen finite element material model and the implemented parameters had to show that they are able to represent not only the specimen behavior under predominantly uniaxial load but also the more complex stress states in real components. Deviations between the measured and calculated results are pointed out and discussed. For the consideration of long-term effects in the simulation of elastomer behavior, test results of aged specimens are needed. First information about a new test program, started recently and planned to provide these data, are given. American society of mechanical engineers (ASME) 2017 Proceedings-CD, ASME 2017 Pressure Vessels & Piping Conference (PVP2017) 7 978-0-7918-5802-8 ASME 2017 Pressure Vessels & Piping Conference (PVP2017) Waikoloa, Hawaii, USA 16.07.2017 20.07.2017 Article UNSP V007T07A035, 1 8 2017-09-06 OPUS4-46110 Beitrag zu einem Tagungsband Grelle, Tobias; Wolff, Dietmar; Probst, Ulrich; Jaunich, Matthias; Völzke, Holger Investigation of the time and temperature dependent behavior of metal seals in radioactive waste containers The Bundesanstalt für Materialforschung und -Prüfung (BAM) runs an investigation program on the long-term behavior of multi-component metal seals. Such seals are used in a wide area of applications including transport and storage casks for spent nuclear fuel and high level radioactive waste. The seal function is mainly based on the compression of the inner helical spring, which generates the necessary seal force to keep the sealing surfaces in close contact. This in turn leads to a plastic deformation of the outer jacket of the seal, comprised of highly ductile aluminum or silver that adapts to the sealing surfaces of cask body and bolted lid, thus providing high Level leak tightness. In Germany, those casks are licensed for Interim storage periods of up to 40 years or more if extended Interim storage would become necessary before a final repository is available. Thus, the sealing performance has to be evaluated, including factors like elevated temperature due to decay heat or mechanical loads due to transport under normal as well as accident conditions. Long-term investigations at BAM have been running over the last nine years to identify and evaluate the seal performance by measuring the remaining seal force, the useable resilience and the leakage rate after various time intervals at temperatures ranging from room temperature up to 150 °C. It was found that the seal force and useable resilience decrease with time and temperature, caused by creep deformation of the outer jacket. In order to obtain an analytical description for the seal behavior and to achieve more information on the material behavior under application conditions a comprehensive investigation program with Focus on aluminum as outer jacket material was launched. The program includes material investigations such as compression and tension creep tests with representative basic materials. An additional test setup allows for the continuous measurement of the remaining seal force at temperatures of up to 150 °C. Furthermore, seal segments are compressed and stored in heating chambers, thus producing segments at different stages of the aging process. The segments are investigated regarding the development of the contact area width, jacket thickness and microstructural changes. This data will be used to develop material models and an analytical description of the time and temperature dependent long-term sealing behavior. This paper explains the current status of gained test results and modelling approaches and closes with an outlook to the future Project plans. 2018 Proceedings of the ASME 2018 Pressure Vessels an piping Conference ASME 2018 Pressure Vessels and Piping Conference Prague, Czech Republic 15.07.2018 20.07.2018 PVP2018-84584, 1 6 2018-10-02