TY - RPRT A1 - Zencker, Uwe A1 - Völzke, Holger A1 - Droste, Bernhard T1 - Stilllegung und Rückbau kerntechnischer Einrichtungen: Entwicklung von Beurteilungsmethoden für Transport- und Lagerbehälter mit erhöhten metallischen Reststoffanteilen (EBER) N2 - 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. T3 - BAM Forschungsberichtreihe - 240 PY - 2002 U6 - http://nbn-resolving.de/urn/resolver.pl?urn:nbn:de:kobv:b43-2109 SN - 978-3-89701-523-4 SN - 0938-5533 VL - 240 SP - 1 EP - 71 PB - Wirtschaftsverlag NW CY - Bremerhaven AN - OPUS4-210 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - RPRT A1 - Droste, Bernhard A1 - Probst, Ulrich T1 - Untersuchungen zur Wirksamkeit der Brandschutzisolierung von Flüssiggas-Lagertanks N2 - 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. T3 - BAM Forschungsberichtreihe - 125 KW - Lagertank KW - Flüssiggas KW - Isolierstoff KW - Brandschutzisolierung KW - Technische Sicherheit KW - Sicherheitstechnische Kriterien KW - Brandversuche KW - Temperatur- und Druckmessungen PY - 1986 U6 - http://nbn-resolving.de/urn/resolver.pl?urn:nbn:de:kobv:b43-3253 SN - 978-3-88314-540-8 SN - 0938-5533 VL - 125 SP - 1 EP - 24 PB - Wirtschaftsverlag NW CY - Bremerhaven AN - OPUS4-325 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - RPRT A1 - Droste, Bernhard A1 - Ludwig, Jörg A1 - Schulz-Forberg, Bernd T1 - Höherwertige Transporttechnik und ihre Konsequenzen für die Beförderung gefährlicher Güter N2 - 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. T3 - BAM Forschungsberichtreihe - 173 KW - Transporttanks KW - Beförderung gefährlicher Güter KW - Verkehrsträger KW - Abhängige Transportsicherheit KW - Höherwertige Transporttechnik KW - Riikobewertung KW - Alternativbetrachtungen PY - 1990 U6 - http://nbn-resolving.de/urn/resolver.pl?urn:nbn:de:kobv:b43-2778 SN - 978-3-88314-999-3 SN - 0938-5533 VL - 173 SP - 1 EP - 61 PB - Wirtschaftsverlag NW CY - Bremerhaven AN - OPUS4-277 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gogolin, Bernd A1 - Droste, Bernhard A1 - Quercetti, Thomas T1 - Drop-test program with the German "POLLUX" cask for final disposal of spent fuel T2 - PATRAM ´95 - 11th International Conference on the packaging and transportation of radioactive materials CY - Las Vegas, Nevada, USA DA - 1995-12-03 KW - Container KW - Brennelement KW - Endlagerung KW - Abfall, radioaktiv PY - 1995 VL - 1 SP - 159 EP - 166 AN - OPUS4-610 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rödel, Roland A1 - Droste, Bernhard A1 - Buhlemann, Lothar A1 - Hübner, Heinz W. T1 - Compliance assurance aspects for Type-A and industrial packages T2 - PATRAM ´95 - 11th International Conference on the packaging and transportation of radioactive materials CY - Las Vegas, Nevada, USA DA - 1995-12-03 KW - Verpackung PY - 1995 VL - 1 SP - 294 EP - 298 AN - OPUS4-611 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zeisler, Peter A1 - Droste, Bernhard A1 - Rödel, Roland A1 - Rehmer, Birgit T1 - Current approval procedures for type-B packages in Germany: Overview T2 - PATRAM ´95 - 11th International Conference on the packaging and transportation of radioactive materials CY - Las Vegas, Nevada, USA DA - 1995-12-03 KW - Gefahrgutumschließung KW - Zertifizierung PY - 1995 VL - 1 SP - 496 EP - 503 AN - OPUS4-613 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Droste, Bernhard A1 - Wieser, Günter A1 - Gogolin, Bernd T1 - Extended brittle fracture safety demonstrations of cubic ductile cast iron containers T2 - PATRAM ´95 - 11th International Conference on the packaging and transportation of radioactive materials CY - Las Vegas, Nevada, USA DA - 1995-12-03 KW - Container KW - Sprödbruch PY - 1995 VL - 3 SP - 1356 EP - 1363 AN - OPUS4-614 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Quercetti, Thomas A1 - Gogolin, Bernd A1 - Droste, Bernhard T1 - Integrity of the "POLLUX" cask for final disposal: Experimental results of the mechanical tests T2 - PATRAM ´95 - 11th International Conference on the packaging and transportation of radioactive materials CY - Las Vegas, Nevada, USA DA - 1995-12-03 KW - Container KW - Gefahrgutumschließung KW - Integrität PY - 1995 VL - 3 SP - 1091 EP - 1098 AN - OPUS4-616 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Zencker, Uwe A1 - Qiao, Linan A1 - Droste, Bernhard T1 - Dynamic Fracture Mechanical Safety Assessment of Cask Designs PY - 2002 SN - 0957-476X VL - 13 IS - 3-4 SP - 291 EP - 296 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-2807 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Qiao, Linan A1 - Droste, Bernhard T1 - Assessment of dynamically loaded cracks in fillets N2 - 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. T2 - 15th European Conference of Fracture CY - Stockholm, Sweden DA - 2004-08-11 KW - Ductile cast iron KW - Container design KW - Safety assessment KW - Fracture mechanics KW - Dynamic load conditions PY - 2004 UR - http://www.structuralintegrity.eu/pdf/esis/Documents/Conference/ECF/15/Zencker%20U%20et%20al.pdf SP - 1 EP - 8(?) CY - Stockholm AN - OPUS4-3763 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Wieser, Karol E. A1 - Droste, Bernhard A1 - Helms, Rolf A1 - Ziebs, Josef A1 - Hemptenmacher, Jörg T1 - Gußeisen mit Kugelgraphit als Werkstoff für Transport- und Lagerbehälter bestrahlter Brennelemente PY - 1985 SN - 0340-7551 VL - 15 IS - 1 SP - 4 EP - 18 PB - Bundesanstalt für Materialprüfung CY - Berlin AN - OPUS4-2328 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - RPRT A1 - Zencker, Uwe A1 - Qiao, Linan A1 - Droste, Bernhard T1 - Entwicklung von Beurteilungsmethoden für Transport- und Lagerbehälter mit erhöhten metallischen Reststoffanteilen - Weiterführende Untersuchungen (EBER II) N2 - 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. KW - Duktiles Gusseisen KW - Transportbehälter KW - Lagerbehälter KW - Fallversuch KW - Spannungsanalyse KW - Sicherheitsbewertung KW - Dynamische Belastung PY - 2002 SP - 1 EP - 70 PB - Bundesanstalt für Materialprüfung CY - Berlin AN - OPUS4-3475 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Ridder, K. A1 - Cosack, M. A1 - Droste, Bernhard T1 - Castor & Co. auf dem Prüfstand. Wie sicher sind Radioaktivtransporte? PY - 2001 SN - 0941-6080 IS - 6 SP - 8 EP - 10 PB - Verl. TÜV Rheinland CY - Köln AN - OPUS4-1882 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Millan, P. A1 - Vaughan, C. A1 - Gogolin, Bernd A1 - Droste, Bernhard T1 - Drop Test for the Licensing of the "RA-3D" Package in the Transport of BWR Fresh Fuel Assembllies T2 - PATRAM 2001 ; Annual International Symposium on Packaging and Transportation of Radioactive Materials CY - Chicago, IL, USA DA - 2001-09-03 PY - 2001 IS - CD-ROM PB - PATRAM CY - Chicago, Ill. AN - OPUS4-1884 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Schulz-Forberg, Bernd A1 - Probst, Ulrich T1 - Investigation of a Spent Fuel Cask Beside an Exploding Propane Tank T2 - PATRAM 2001 ; Annual International Symposium on Packaging and Transportation of Radioactive Materials CY - Chicago, IL, USA DA - 2001-09-03 PY - 2001 IS - CD-ROM PB - PATRAM CY - Chicago, Ill. AN - OPUS4-1888 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Qiao, Linan A1 - Droste, Bernhard T1 - Assessment of dynamically loaded surface cracks in cubic containers T2 - 13th International Conference on Packaging and Transportation of Radioactive Materials ; PATRAM 2001 CY - Chicago, IL, USA DA - 2001-09-03 PY - 2001 IS - CD-ROM PB - PATRAM CY - Chicago, Ill. AN - OPUS4-1889 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gogolin, Bernd A1 - Droste, Bernhard A1 - Millan, P. T1 - Results of the Drop Tests with the "RA-3D"Shipping Container for the Transport of Fresh BWR-Fuel Elements T2 - PATRAM 2001 ; Annual International Symposium on Packaging and Transportation of Radioactive Materials CY - Chicago, IL, USA DA - 2001-09-03 PY - 2001 IS - CD-ROM PB - PATRAM CY - Chicago, Ill. AN - OPUS4-1943 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Zencker, Uwe A1 - Qiao, Linan A1 - Droste, Bernhard T1 - Entwicklung von Beurteilungsmethoden für Transport- und Lagerbehälter mit erhöhten metallischen Reststoffanteilen - Abschließende Untersuchungen (EBER III) T2 - 6. KONTEC ; 6. Internationales Symposium "Konditionierung Radioaktiver Betriebs- und Stilllegungsabfälle" ; 6th International Symposium "Conditioning of Radioactive Operational & Decommissioning Wastes" CY - Berlin, Deutschland DA - 2003-03-19 PY - 2003 SN - 3-9806415-6-2 VL - 6 SP - 623 EP - 630 CY - Hamburg AN - OPUS4-2398 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wieser, Karol E. A1 - Droste, Bernhard T1 - Die Prüfung und Begutachtung von Behältern aus Sphäroguß T2 - Seminar der Bundesanstalt für Materialforschung und -prüfung (BAM) CY - Berlin, Deutschland DA - 1987-06-09 PY - 1987 VL - 13 SP - 55 EP - 66 PB - Bundesanstalt für Materialforschung und -prüfung CY - Berlin AN - OPUS4-2333 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Wieser, Karol E. A1 - Droste, Bernhard ED - Warnecke, E. ED - Giller, H. T1 - Behälter zur Endlagerung radioaktiver Stoffe - Baumusterprüfung und qualitätssichernde Maßnahmen T2 - 85. PTB-Seminar CY - Braunschweig, Deutschland DA - 1989-07-17 PY - 1989 SN - 3-88314-942-X SN - 0721-0892 N1 - Serientitel: PTB-Bericht – Series title: PTB-Bericht VL - 25 IS - SE-25 SP - 151 EP - 166 PB - Wirtschaftsverl. CY - Bremerhaven AN - OPUS4-2336 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Völzke, Holger A1 - Wieser, Günter A1 - Qiao, Linan T1 - Safety Margins of Spent Fuel Transport and Storage Casks Considering Aircraft Crash Impacts PY - 2002 SN - 0957-476X VL - 13 IS - 3-4 SP - 313 EP - 316 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-2697 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Lange, F. A1 - Hörmann, E. A1 - Schwarz, G. A1 - Droste, Bernhard A1 - Völzke, Holger A1 - Wieser, Günter T1 - Spent Fuel Transport and Storage Casks under Extreme Accidents T2 - 10th International High-Level Radioactive Waste Management Conference (IHLRWM-10) CY - Las Vegas, NV, USA DA - 2003-03-30 PY - 2003 SN - 0-89448-669-1 SP - 465 EP - 470 PB - American Nuclear Society CY - La Grange Park, Ill. AN - OPUS4-2698 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Wolff, Dietmar A1 - Probst, Ulrich A1 - Völzke, Holger A1 - Droste, Bernhard A1 - Rödel, Roland T1 - Safety aspects of long-term dry interim storage of type-B spent fuel and HLW transport casks KW - Transport casks KW - Interim storage KW - Leak tightness KW - KOBAF PY - 2004 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 15 IS - 3-4 SP - 207 EP - 213 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-7414 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Völzke, Holger A1 - Wieser, Günter A1 - Qiao, Linan T1 - Safety Margins of Spent Fuel Transport and Storage Casks Considering Aircraft Crash Impacts T2 - 6th International Conference on Radioactive Materials Transport - 2002 CY - Edinburgh, Scotland DA - 2002-11-05 PY - 2002 AN - OPUS4-5737 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Ballheimer, Viktor A1 - Droste, Bernhard A1 - Wieser, Günter A1 - Qiao, Linan T1 - Spent fuel transport associated with other dangerous goods in regular train units - assessment of hypothetical explosion impacts T2 - 14th International Symposium on the Packaging and Transportation of Radioactive Materials, September 20-24, 2004, Berlin CY - Berlin, Germany DA - 2004-09-20 KW - Transport spent fuel cask KW - Accident KW - Blast wave KW - Finite element analysis PY - 2004 IS - 235 SP - 1 EP - 7(?) PB - BAM CY - Berlin AN - OPUS4-11906 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - König, S. A1 - Diersch, R. A1 - Lührmann, A. A1 - Müller, Karsten A1 - Neumann, Martin A1 - Quercetti, Thomas A1 - Droste, Bernhard T1 - Full-Scale Drop Testing of the CONSTOR®, V/TC Package Program, and Preliminary Results KW - Drop test KW - Package KW - Spent fuel cask KW - Transport PY - 2005 SN - 0893-6188 VL - 33 IS - 3 SP - 4 EP - 10 PB - Institute of Nuclear Materials Management CY - Northbrook, Ill. AN - OPUS4-12269 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Müller, Karsten A1 - Quercetti, Thomas T1 - Full-Scale Drop Testing of Spent Fuel Transport and Storage Casks - Experiences of BAM and new Developments - T2 - 46th INMM Annual Meeting CY - Phoenix, AZ, USA DA - 2005-06-10 PY - 2005 AN - OPUS4-7607 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Fallversuche im Verfahren der Zulassung neuer Behälterbauarten - Neuer Fallversuchsstand der BAM - T2 - 4. Symposium "Lagerung und Transport radioaktiver Stoffe - Stand der BE-Entsorgung" CY - Hanover, Germany DA - 2005-06-15 PY - 2005 AN - OPUS4-7608 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Müller, Karsten A1 - Quercetti, Thomas T1 - Full-scale Drop Testing of Spent Fuel Transport and Storage Casks: experiences of BAM and new Developments T2 - 46th Annual Meeting of the Institute for Nuclear Materials Management CY - Phoenix, AZ, USA DA - 2005-07-10 KW - Drop tests KW - Spent fuel transport packages PY - 2005 SP - 6 pages PB - Institute for Nuclear Materials Management CY - Phoenix AN - OPUS4-7614 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Fallversuche im Verfahren zur Zulassung neuer Behälterbauarten - Neuer Fallversuchsstand der BAM T2 - 4. Symposium "Lagerung und Transport radioaktiver Stoffe - Stand der BE-Entsorgung CY - Hannover, Deutschland DA - 2005-05-14 KW - Mechanische Prüfung KW - Transportbehälter für radioaktive Stoffe KW - Fallversuche PY - 2005 SP - 18 Seiten PB - TÜV CY - Hannover AN - OPUS4-7615 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Müller, Karsten A1 - Minack, Mathias T1 - New BAM 200 ton drop test facility - construction and operation experiences KW - Drop testing KW - Full scale spent fuel casks KW - Unyielding target KW - Impact limiter KW - Safety margin PY - 2006 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 17 IS - 3 SP - 131 EP - 135 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-13709 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Müller, Karsten A1 - Ballheimer, Viktor A1 - Droste, Bernhard A1 - Rödel, Roland A1 - Völzke, Holger A1 - Zencker, Uwe T1 - Die Anwendung der Bruchmechanik im Sicherheitsnachweis von Transportbehältern für die Beförderung radioaktiver Stoffe T2 - 36. Tagung des DVM-Arbeitskreises Bruchvorgänge CY - Köln, Deutschland DA - 2004-02-17 KW - Gusseisen mit Kugelgraphit KW - Bruchmechanischer Sicherheitsnachweis KW - Stoßbeanspruchung KW - Transportbehälter KW - Radioaktive Stoffe KW - Ductile iron KW - Fracture mechanics safety assessment KW - Mechanical impact KW - Transport casks KW - Radioactive material PY - 2004 SN - 0943-3473 IS - 236 SP - 225 EP - 238 PB - DVM CY - Berlin AN - OPUS4-5336 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Müller, Karsten A1 - Quercetti, Thomas A1 - Wille, Frank A1 - Kuschke, Christian T1 - Full-Scale drop testing of spent fuel transport packages T2 - Seminar on Complex Technical Issues on Transport of Radioactive Material, IAEA CY - Vienna, Austria DA - 2006-01-11 PY - 2006 AN - OPUS4-11795 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Müller, Karsten A1 - Droste, Bernhard T1 - Die BAM nimmt neuen Prüfstand in Betrieb KW - Fallversuche KW - Transport- und Lagerbehälter für radioaktive Stoffe PY - 2004 SN - 1434-9728 SN - 1436-4948 SN - 0372-2457 SN - 0376-1185 VL - 45 IS - 10 SP - 7 PB - Springer-VDI-Verl. CY - Düsseldorf AN - OPUS4-4833 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Ballheimer, Viktor A1 - Droste, Bernhard A1 - Wieser, Günter A1 - Qiao, Linan T1 - Spent fuel transport associated with other dangerous goods in regular train units - assessment of hypothetical explosion impacts KW - Transport spent fuel cask KW - Accident KW - Blast wave KW - Finite element analysis PY - 2004 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 15 IS - 3-4 SP - 239 EP - 245 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-11975 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Müller, Karsten A1 - Minack, Mathias T1 - The New BAM 200 Ton Drop Test Facility - Construction and Operation Experiences T2 - 7th International Conference on Radioactive Materials Transport - 2005 CY - Cambridge, England, UK DA - 2005-09-27 KW - Drop test KW - Drop tower KW - Radioactive material transport packages PY - 2005 SP - 6 pages PB - The Institution of Nuclear Engineers (INucE) CY - Cambridge AN - OPUS4-12044 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Gröke, Carsten A1 - Droste, Bernhard T1 - Assessment of quality assurance measures for radioactive material transport packages not requiring competent authority design approval N2 - 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. T2 - WM2013 Conference CY - Phoenix, Arizona, USA DA - 24.02.2013 PY - 2013 SN - 978-0-9836186-2-1 SP - 1 EP - 8 CY - Phoenix, Arizona, USA AN - OPUS4-28504 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin A1 - Günther, U. A1 - Ballheimer, Viktor A1 - Linnemann, Konrad A1 - Wille, Frank A1 - Droste, Bernhard T1 - Experiences by German authority with safety case approach for welding seams as part of SNF transport package containments N2 - 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. T2 - RAMTRANSPORT 2012 - 9th International Conference on the Radioactive Materials Transport and Storage CY - London, UK DA - 2012-05-22 PY - 2012 IS - Session 4.2 RAM 18 SP - 1 EP - 6 AN - OPUS4-26344 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Rolle, Annette A1 - Droste, Bernhard T1 - Mechanical behaviour of high burn-up SNF under normal and accident transport conditions - present approaches and perspectives N2 - 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. T2 - ASME 2012 Pressure vessels & piping division conference CY - Toronto, Ontario, Canada DA - 15.07.2012 KW - Fuel rods KW - High burn-up KW - Mechanical behaviour KW - Transport conditions PY - 2012 SP - PVP2012-78302, 1-7 PB - American Society of Mechanical Engineers CY - New York AN - OPUS4-26320 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Development of an IAEA Guidance for an Integrated Safety Case for Spent Nuclear Fuel Transport and Storage Casks T2 - RAMTRANSPORT 2012 Radioactive Materials Transport and Storage Conference, Royal Geographical Society CY - London, England DA - 2012-05-23 PY - 2012 AN - OPUS4-26329 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Gröke, Carsten T1 - Verpackungen Bestandsaufnahme - Pflichten und Vorschriften bei schwach radioaktiven Stoffen PY - 2012 SN - 0944-6117 IS - 6 SP - 20 EP - 25 PB - Vogel CY - München AN - OPUS4-26362 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Überblick über das BAM-Testgelände Technische Sicherheit T2 - 3. RAM-Behältersicherheitstage, BAM/TTS CY - Baruth, Germany DA - 2012-03-22 PY - 2012 AN - OPUS4-26330 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Transport nach langer Zwischenlagerung; Regelwerksentwicklung bei der IAEA T2 - 3. RAM-Behältersicherheitstage, BAM CY - Berlin, Germany DA - 2012-03-22 PY - 2012 AN - OPUS4-26331 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard T1 - Transport nach langer Lagerung KW - Brennelement-Transportbehälter KW - Transport nach langer Zwischenlagerung KW - Alterungsmanagement KW - Transportbehälter-Zwischenlager Gorleben und Ahaus KW - CASTOR-Behälter PY - 2013 SN - 0944-6117 VL - 4 SP - 26 EP - 28 PB - Vogel CY - München AN - OPUS4-27906 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Gröke, Carsten T1 - Qualitätssicherung und -überwachung bei Verpackungen für prüfpflichtige Versandstücke zur Beföderung radioaktiver Stoffe N2 - 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. T2 - Jahrestagung Kerntechnik 2013 CY - Berlin, Germany DA - 14.05.2013 PY - 2013 IS - Sektion 5: Entsorgung radioaktiver Abfälle, Lagerung SP - 1 EP - 6 AN - OPUS4-28653 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Kuschke, Christian A1 - Neumeyer, Tino A1 - Wille, Frank A1 - Droste, Bernhard T1 - Mechanical/thermal package design safety assessment and manufacturing quality assurance of spent fuel transport cask NCS 45 T2 - WM2010 - 36th Annual radioactive waste management symposium CY - Phoenix, Arizona, USA DA - 2010-03-07 KW - Package design KW - Spent fuel transport cask KW - Safety assessment PY - 2010 SN - 978-0-9828171-0-0 SP - 1 EP - 13 CY - Tempe, AZ, USA AN - OPUS4-24344 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Musolff, André A1 - Quercetti, Thomas A1 - Müller, Karsten A1 - Droste, Bernhard A1 - Komann, Steffen T1 - Drop test program with half scale model CASTOR HAW/TB2 N2 - 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. KW - IAEA drop testing KW - Half scale model KW - Experimental test PY - 2011 U6 - https://doi.org/10.1179/1746510911Y.0000000013 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 22 IS - 3 SP - 154 EP - 160 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-25293 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Eisenacher, Germar A1 - Scheidemann, Robert A1 - Neumann, Martin A1 - Wille, Frank A1 - Droste, Bernhard T1 - Approach for a finite element material model for wood for application in mechanical safety cases of transport packages N2 - 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. T2 - 52nd INMM Annual meeting CY - Palm Desert, CA, USA DA - 17.07.2011 KW - Impact limiter KW - Material model wood KW - Transport package PY - 2011 SP - 1 EP - 8 AN - OPUS4-24236 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Musolff, André A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Müller, Karsten A1 - Quercetti, Thomas T1 - Drop test program with a HLW cask model - performance, measurements and results N2 - 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. T2 - 52nd INMM Annual meeting CY - Palm Desert, CA, USA DA - 17.07.2011 KW - Drop test results KW - Spent fuel transport cask KW - Impact limiter KW - Measurement methods KW - Drop test program PY - 2011 SP - 1 EP - 9 AN - OPUS4-24245 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Nehrig, Marko A1 - Wille, Frank A1 - Quercetti, Thomas A1 - Masslowski, Jörg-Peter A1 - Droste, Bernhard A1 - Pope, R. T1 - Historical view and experiences with crush test for light weight packages N2 - 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. KW - Package testing KW - Crush testing KW - Regulations PY - 2011 U6 - https://doi.org/10.1179/1746510911Y.0000000016 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 22 IS - 3 SP - 125 EP - 129 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-25349 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Eisenacher, Germar A1 - Scheidemann, Robert A1 - Neumann, Martin A1 - Droste, Bernhard A1 - Völzke, Holger T1 - Dynamic crushing characteristics of spruce wood under large deformations N2 - 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. KW - Crushing test KW - Dynamic crushing characteristics KW - Spruce wood KW - Lateral constraint KW - Multiaxial stress state KW - Hankinson's formula PY - 2013 U6 - https://doi.org/10.1007/s00226-012-0508-5 SN - 0043-7719 SN - 1432-5225 VL - 47 IS - 2 SP - 369 EP - 380 PB - Springer CY - Berlin AN - OPUS4-27743 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Maitra, A. N. A1 - Hecht, A. A1 - Feiler, H. G. T1 - Das anodische Verhalten von Nickel bei Zusatz von Thioharnstoff und Dicyandiamid PY - 1979 SN - 0026-0797 SN - 0043-2792 VL - 33 IS - 3 SP - 112 EP - 120 PB - IGT, Informationsges. Technik CY - München AN - OPUS4-9049 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Zencker, Uwe A1 - Müller, Karsten A1 - Droste, Bernhard A1 - Rödel, Roland A1 - Völzke, Holger T1 - The Application of Fracture Mechanics to the Safety Assessment of Transport Casks for Radioactive Materials N2 - 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. KW - Ductile iron KW - Cask design KW - Safety assessment KW - Fracture mechanics KW - BAM GGR 007 PY - 2004 U6 - https://doi.org/10.1179/174650904775295847 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 15 IS - 3-4 SP - 191 EP - 198 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-11553 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Qiao, Linan A1 - Droste, Bernhard T1 - Entwicklung von Beurteilungsmethoden für Transport- und Lagerbehälter mit erhöhten metallischen Reststoffanteilen - Ein zusammenfassender Überblick T2 - 7. Internationales Symposium "Konditionierung radioaktiver Betriebs- und Stilllegungsabfälle" (KONTEC 2005) CY - Berlin, Deutschland DA - 2005-04-20 KW - Duktiles Gusseisen KW - Behälterdesign KW - Sicherheitstechnische Bewertung KW - Bruchmechanik KW - Dynamische Belastungsbedingungen PY - 2005 SP - 797 EP - 804 PB - KONTEC CY - Hamburg AN - OPUS4-11550 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Zencker, Uwe A1 - Qiao, Linan A1 - Droste, Bernhard T1 - Development of assessment methods for transport and storage containers with a higher content of recycled metal KW - Ductile iron KW - Container design KW - Safety assessment KW - Fracture mechanics KW - Dynamic loading conditions PY - 2004 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 15 IS - 3-4 SP - 215 EP - 221 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-11551 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Sicherheit in der Kerntechnik - Der Beitrag der BAM - T2 - Symposium "Beiträge der Ressortforschung zur Sicherheit", Paul-Ehrlich-Institut CY - Langen (Hesse), Germany DA - 2005-10-18 PY - 2005 AN - OPUS4-11536 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Müller, Karsten A1 - Minack, Mathias T1 - The new BAM 200 Ton Drop Test Facility - Construction and Operation Experiences - T2 - 7th International Conference on Radioactive Materials Transport 2005, Churchill College, Cambridge University CY - Cambridge, England DA - 2005-09-27 PY - 2005 AN - OPUS4-11537 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Wille, Frank A1 - Ballheimer, Viktor A1 - Droste, Bernhard T1 - Suggestions for correct performance of IAEA 1 m puncture bar drop test with reduced scale packages considering similarity theory aspects T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 KW - Similarity theory KW - Puncture bar drop test KW - Reduced scale packages KW - Drop height adaption PY - 2007 U6 - https://doi.org/10.1179/174651007X191233 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 18 IS - 2 SP - 111 EP - 116 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-15891 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin A1 - Droste, Bernhard A1 - Wille, Frank T1 - Using Scale Model Impact Limiter in the Type Assessment of Transport Casks for Radioactive Material T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 KW - Impact limiter KW - Similarity KW - Scaling PY - 2007 IS - (Abstract # 86) SP - 1 EP - 8 PB - Institute of Nuclear Materials Management AN - OPUS4-17495 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Neumann, Martin A1 - Wille, Frank A1 - Droste, Bernhard T1 - Scale model impact limiter in type assessment of radioactive material transport packages KW - Impact limiter KW - Shock absorber KW - Scaling KW - Radioactive KW - Material KW - Transport KW - Cask PY - 2008 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 19 IS - 1 SP - 53 EP - 57 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-17498 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Müller, Karsten A1 - Droste, Bernhard A1 - Rödel, Roland A1 - Völzke, Holger T1 - The application of fracture mechanics to the safety assessment of transport casks for radioactive materials T2 - 14th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Berlin, Germany DA - 2004-09-20 KW - Ductile iron KW - Cask design KW - Safety assessment KW - Fracture mechanics KW - BAM GGR 007 PY - 2004 UR - http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/37/088/37088572.pdf IS - 235 SP - 1 EP - 7(?) PB - BAM CY - Berlin AN - OPUS4-11477 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Qiao, Linan A1 - Droste, Bernhard T1 - Development of Assessment Methods for Transport and Storage Containers with Higher Content of Metallic Recycling Material T2 - 14th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Berlin, Germany DA - 2004-09-20 KW - Ductile iron KW - Container design KW - Safety assessment KW - Fracture mechanics KW - Dynamic loading conditions PY - 2004 UR - http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/37/088/37088594.pdf IS - 235 SP - 1(?) EP - 7(?) PB - BAM CY - Berlin AN - OPUS4-11478 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Experiences and perspectives of package testing under hypothetical accident conditions T2 - PATRAM 2007 The 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, FL, USA DA - 2007-10-21 PY - 2007 AN - OPUS4-16012 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Droste, Bernhard A1 - Koch, Frank A1 - Komann, Steffen T1 - Design assessment of spent fuel and HLW Transport Casks T2 - 49th INMM Annual Meeting, July 13-17, 2008 CY - Nashville, USA DA - 2008-07-13 KW - Safety Analysis KW - Transport Packages KW - Drop tests KW - Finite Element Analysis KW - Thermal Design KW - Containment KW - Quality Management PY - 2008 SP - 1 EP - 8 AN - OPUS4-17780 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Wille, Frank A1 - Rittscher, D. T1 - Mechanical assessment of large nuclear power plant components in transport licensing T2 - 49th INMM Annual Meeting CY - Nashville, TN, USA DA - 2008-07-13 KW - Rückbau KW - Kerntechnische Anlagen KW - Großkomponenten KW - Transport KW - Mechanik PY - 2008 SP - 1 EP - 8 AN - OPUS4-18440 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Qiao, Linan A1 - Weber, Mike A1 - Kovacs, Oliver A1 - Droste, Bernhard T1 - Application limits of low-ductile cast iron for radioactive waste containers T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 KW - Ductile iron KW - Container design KW - Safety assessment KW - Fracture mechanics KW - Dynamic loading conditions PY - 2007 IS - Session B, Paper #97 SP - 1 EP - 8 PB - Institute of Nuclear Materials Management AN - OPUS4-18399 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Qiao, Linan A1 - Wieser, Günter A1 - Zencker, Uwe A1 - Droste, Bernhard T1 - Dynamic finite element analyses of a HLW transport cask with polyurethane impact limiters in 9m drop tests T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 KW - Ductile iron KW - Cask design KW - Safety assessment KW - Impact limiter KW - Dynamic loading conditions PY - 2007 IS - Session E, Paper #60 SP - 1 EP - 7 PB - Institute of Nuclear Materials Management AN - OPUS4-18400 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard T1 - Testing of type B packages in Germany to environments beyond regulatory test standards KW - Type B packages KW - Drop testing KW - Large height drop tests KW - Explosion impacts KW - Extended fire test KW - Real target drop calculation KW - Aircraft crash simulation PY - 2007 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 18 IS - 2 SP - 73 EP - 85 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-15714 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Ballheimer, Viktor T1 - Experimental Investigations of the Behavior of High-Burnup Fuel Rods under Mechanical Accident Loads (BMU/GRS Research Project) T2 - US NRC/BAM-Meeting CY - Washington, D.C., USA DA - 2007-10-18 PY - 2007 AN - OPUS4-16230 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Noack, Volker A1 - Rittscher, D. A1 - Schmidt, H. T1 - German support for utilization of nuclear submarines in Russia T2 - International Workshop and Technical Meeting on Design and Assessment of Packages for Radioactive Waste CY - Bergen, Netherlands DA - 2006-11-21 PY - 2006 AN - OPUS4-14107 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Müller, Karsten A1 - Quercetti, Thomas A1 - Droste, Bernhard T1 - Measurement techniques and preliminary results of drop tests with full scale spent fuel transport and storage casks KW - Drop testing KW - Full scale spent fuel cask KW - Deceleration KW - Strain PY - 2006 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 17 IS - 4 SP - 191 EP - 195 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-14431 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Wieser, Günter A1 - Qiao, Linan A1 - Völzke, Holger A1 - Wolff, Dietmar A1 - Droste, Bernhard T1 - Safety analysis of casks under extreme impact conditions KW - Aircraft crash KW - Impact load KW - Simulation KW - Lid-seal system KW - Storage cask KW - Metallic seal KW - Leakage rate PY - 2004 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 15 IS - 2 SP - 141 EP - 147 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-14441 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Qiao, Linan A1 - Weber, Mike A1 - Kovacs, Oliver A1 - Droste, Bernhard T1 - Sicherheitstechnische Analyse von Transport- und Lagerbehältern aus Gusseisen mit erhöhten metallischen Reststoffanteilen mittels Fallversuchen T2 - KONTEC 2007 CY - Dresden, Deutschland DA - 2007-03-21 KW - Behälterdesign KW - Bruchmechanik KW - Duktiles Gusseisen KW - Dynamische Belastungsbedingungen KW - Sicherheitstechnische Bewertung PY - 2007 SP - 869 EP - 875 PB - Gesellschaft für technische Kommunikation mbH / Kerntechnische Gesellschaft CY - Dresden AN - OPUS4-14712 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Koch, Frank A1 - Droste, Bernhard A1 - Krietsch, Torsten T1 - Consequences of drop test parameter limitations for subsequent package design safety analysis T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 KW - Transportbehälter KW - Fallprüfung KW - Sicherheitsbericht KW - Parameter KW - Assessment Cube PY - 2007 SP - 1 EP - 7 PB - Institute of Nuclear Materials Management AN - OPUS4-16129 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Ballheimer, Viktor A1 - Droste, Bernhard T1 - Suggestions for correct performance of IAEA 1 m puncture bar drop test with reduced-scale packages considering similarity theory aspects T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 KW - Similarity KW - Puncture Bar Drop Test KW - Scale Models KW - IAEA Regulations PY - 2007 IS - CD-ROM SP - 1 EP - 8 PB - Institute of Nuclear Materials Management AN - OPUS4-16104 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Droste, Bernhard A1 - Koch, Frank A1 - Schubert, Sven A1 - Komann, Steffen T1 - State-of-the-art assessment of package design safety analyses T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 KW - Transportation of radioactive materials KW - Safety KW - Design assessment KW - Mechanical tests KW - Thermal tests KW - Drop tests KW - Numerical calculations KW - Quality assurance PY - 2007 SP - 1 EP - 8 PB - Institute of Nuclear Materials Management AN - OPUS4-16105 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Musolff, André A1 - Müller, Karsten A1 - Neumann, Martin A1 - Kadji, Arsène Brice A1 - Droste, Bernhard T1 - Drop Test Results of the Full-scale CONSTOR V/TC Prototype T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 PY - 2007 IS - Abstract #65 SP - 1 EP - 7 PB - Institute of Nuclear Materials Management AN - OPUS4-17838 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - König, S. A1 - Diersch, R. A1 - Lührmann, A. A1 - Müller, Karsten A1 - Neumann, Martin A1 - Quercetti, Thomas A1 - Droste, Bernhard T1 - Full-scale Drop Testing of the CONSTOR V/TC Package - Program and Preliminary Results KW - Fallversuche KW - Transportbehälter für radioaktive Stoffe PY - 2005 SN - 0893-6188 VL - 33 IS - 3 SP - 4 EP - 10 PB - Institute of Nuclear Materials Management CY - Northbrook, Ill. AN - OPUS4-6875 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rolle, Annette A1 - Droste, Bernhard A1 - Dombrowski, H. T1 - Type testing of devices with inserted radioactive sources T2 - 2nd European IRPA Congress on Radiation Protection CY - Paris, France DA - 2006-05-15 KW - Radiation protection KW - Type approval PY - 2006 SP - 1(?) EP - 6(?) PB - IRPA CY - Paris AN - OPUS4-12815 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Qiao, Linan A1 - Wieser, Günter A1 - Zencker, Uwe A1 - Droste, Bernhard T1 - Dynamische Analyse eines mit Stoßdämpfern ausgerüsteten Gefahrgutbehälters beim 9 m - Fallversuch T2 - 18. ABAQUS-Benutzerkonferenz 2006 CY - Erfurt, Deutschland DA - 2006-09-18 KW - Gefahrgutbehälter KW - Fallversuch KW - Finite-Elemente-Methoden PY - 2006 SP - 1 EP - 11(?) PB - ABAQUS CY - Aachen AN - OPUS4-13207 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Rolle, Annette A1 - Droste, Bernhard A1 - Schubert, Sven A1 - Probst, Ulrich A1 - Wille, Frank T1 - Verification of activity release compliance with regulatory limits within spent fuel transport cask assessment N2 - 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. KW - Containment compliance KW - Seals KW - Regulations KW - Activity release PY - 2012 U6 - https://doi.org/10.1179/1746510913Y.0000000012 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 23 IS - 3-4 SP - 149 EP - 152 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-29244 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Müller, Karsten T1 - Test installations for the examination of CASTOR casks at the BAM test centre technical safety N2 - 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. T2 - 5th International Seminar on Radioactive Waste Products (RADWAP 2008) CY - Würzburg, Germany DA - 2008-10-27 KW - Drop tests KW - Fire tests KW - Finite element calculations KW - Radioactive waste packages KW - CASTOR casks KW - BAM test centre technical safety PY - 2008 SP - 1 EP - 8 AN - OPUS4-18781 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Rolle, Annette A1 - Droste, Bernhard T1 - Safety during whole life time: important aspect in safety assessment of sealed radioactive sources N2 - 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. KW - Radioactive KW - Sealed sources KW - Aging PY - 2008 U6 - https://doi.org/10.1179/174651008X344458 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 19 IS - 3 SP - 151 EP - 154 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-18741 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rolle, Annette A1 - Droste, Bernhard T1 - Safety during whole life time - An important aspect in safety assessment of sealed radioactive sources T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 PY - 2007 IS - (Abstract # 53) SP - 1 EP - 7 PB - Institute of Nuclear Materials Management AN - OPUS4-18742 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Günther, B. A1 - Kowalewsky, Helmut T1 - The lid closure system of casks for the interim storage of spent fuel T2 - International seminar on spent fuel storage - safety, engineering and environmental aspects CY - Vienna, Austria DA - 1990-10-08 PY - 1990 SP - 1 EP - 19 PB - International Atomic Energy Agency CY - Wien AN - OPUS4-19232 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Vorstellung der Versuchseinrichtungen des BAM Testgeländes Technische Sicherheit (TTS) T2 - 1. RAM-Behältersicherheitstage 2009 CY - Berlin-Horstwalde, Germany DA - 2009-03-26 PY - 2009 AN - OPUS4-19176 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Die Bauartprüfung im verkehrsrechtlichen Zulassungsverfahren T2 - 1. RAM-Behältersicherheitstage 2009 CY - Berlin-Horstwalde, Germany DA - 2009-03-26 PY - 2009 AN - OPUS4-19177 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Ballheimer, Viktor A1 - Koch, Frank A1 - Kuschke, Christian A1 - Droste, Bernhard T1 - Similarity aspects for closure systems in small scale package drop testing T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 KW - Scale model KW - Closure system KW - Drop tests PY - 2007 SP - 1 EP - 8 PB - Institute of Nuclear Materials Management AN - OPUS4-19654 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Zur Wirksamkeit von Wasserberieselungsvorrichtungen T2 - Zum Stand der Sicherheitstechnik bei der Flüssiggaslagerung CY - Wolfsburg, Deutschland DA - 1988-04-19 PY - 1988 SP - 1 EP - 4 PB - CongressPark CY - Wolfsburg AN - OPUS4-19753 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Bleve in kunststoffverarbeitendem Betrieb T2 - Zum Stand der Sicherheitstechnik bei der Flüssiggaslagerung CY - Wolfsburg, Deutschland DA - 1988-04-19 PY - 1988 SP - 1 EP - 2 PB - CongressPark CY - Wolfsburg AN - OPUS4-19754 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Safety evaluation of dry spent fuel storage casks T2 - Soviet-West German Seminar on Experience and Prospective Methods of Spent Fuel Storage and Transport CY - Leningrad, Soviet Union DA - 1988-06-27 PY - 1988 SP - 1 EP - 30 PB - All Union Scientific Research and Design Institute for Complex Energy Technologies - VNIPIET CY - Leningrad AN - OPUS4-19755 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Sterthaus, Jens A1 - Ballheimer, Viktor A1 - Droste, Bernhard A1 - Koch, Frank A1 - Probst, Ulrich A1 - Völzke, Holger A1 - Wille, Frank T1 - Analysis of bolted flange joints for lids of packages for radioactive materials T2 - ASME 2009 Pressure vessels and piping conference CY - Prague, Czech Republic DA - 2009-07-26 KW - Bolted flange joints KW - FEA KW - Modelling of gaskets KW - Assessment of leak tightness KW - Results from experiments PY - 2009 SP - PVP2009-77284, 1-8 PB - American Society of Mechanical Engineers CY - New York AN - OPUS4-19786 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Die Wasserberieselung als Brandschutzmaßnahme für Flüssiggaslagertanks T2 - Fortbildungsprogramm "Immissionsschutz", Kurs 841 "Flüssiggaslagerung", Landesanstalt für Immissionsschutz des Landes Nordrhein-Westfalen CY - Essen, Deutschland DA - 1988-11-10 PY - 1988 SP - 1 EP - 5 PB - Landesanstalt für Immissionsschutz des Landes Nordrhein-Westfalen CY - Essen AN - OPUS4-19778 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Die Wasserberieselung als Brandschutzmaßnahme für Flüssiggaslagertanks T2 - Fortbildungsprogramm "Immissionsschutz", Kurs 941 "Flüssiggaslagerung" CY - Essen, Deutschland DA - 1989-03-09 PY - 1989 SP - 1 EP - 5 PB - Landesanstalt für Immissionsschutz des Landes Nordrhein-Westfalen CY - Essen AN - OPUS4-19779 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard ED - Riede, R. ED - Wefers, H. T1 - Zur Wirksamkeit von Wasserberieselungsvorrichtungen T2 - Seminar Nr. S-70-401-091-9 "Flüssiggaslagerung" CY - Essen, Deutschland DA - 1989-04-05 PY - 1989 SP - 1 EP - 6 PB - Haus d. Technik CY - Essen AN - OPUS4-19780 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Probst, Ulrich A1 - Droste, Bernhard A1 - Mallon, Michael A1 - Schön, W. T1 - Untersuchungen zur Wirksamkeit der Brandschutzisolierung von Flüssiggas-Lagertanks PY - 1987 SN - 0006-906X IS - 9 SP - 267 EP - 272 PB - Neckar-Verl. CY - Villingen-Schwenningen AN - OPUS4-19758 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard ED - Schulz-Forberg, Bernd ED - Droste, B. ED - Zeisler, Peter T1 - Die Beurteilung der Sicherheit von Behältern für die trockene Zwischenlagerung abgebrannter Brennelemente T2 - 1. Deutsch-Sowjetisches Seminar Erfahrungen und zukunftsträchtige Verfahren auf dem Gebiet der Lagerung und des Transportes von abgebrannten Kernbrennstoffen CY - Leningrad, Sowjetunion DA - 1988-06-27 PY - 1998 SP - 76 EP - 108 PB - Bundesanstalt für Materialforschung und -prüfung CY - Berlin AN - OPUS4-19765 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Probst, Ulrich A1 - Wieser, Günter T1 - Brennbare Gase sicher lagern - Untersuchungen mit einer Intumeszenz-Brandschutzbeschichtung für Flüssiggastanks PY - 1991 SN - 1434-9728 SN - 1436-4948 SN - 0372-2457 SN - 0376-1185 VL - 2 SP - 59 EP - 66 PB - Springer-VDI-Verl. CY - Düsseldorf AN - OPUS4-21688 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard T1 - Ingenieure suchen nach optimalem Brandschutz für Flüssiggasbehälter - Verschiedene Möglichkeiten auf dem Prüfstand PY - 1991 SN - 0005-8866 SN - 1436-4875 VL - 5 SP - 18 EP - 25 PB - Wiederspahn CY - Wiesbaden AN - OPUS4-21689 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CHAP A1 - Droste, Bernhard T1 - Die Verträglichkeit von metallischen Behälterwerkstoffen und wassergefährdenden Flüssigkeiten PY - 1991 IS - Kurs SW 27 / Kap. 8.2 SP - 1 EP - 36 AN - OPUS4-21690 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Schulz-Forberg, Bernd A1 - Droste, Bernhard T1 - Tankbau - was, wie und warum PY - 1991 SN - 0016-5808 VL - 36 IS - 11 SP - 506 EP - 512 PB - Storck CY - Hamburg AN - OPUS4-21691 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Brandschutz von Flüssiggaslagerbehältern T2 - Internationales Seminar "Gefährliche Stoffe beim Feuerwehreinsatz" CY - Neuherberg, Deutschland DA - 1991-03-19 PY - 1991 VL - I SP - 1 EP - 16 AN - OPUS4-21692 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Gutachterliche Stellungnahmen zu Fragen des Brand- und Explosionsschutzes bei Flüssiggasanlagen T2 - BPU-Seminar "Anwendung der Störfall-Verordnung (12. BImSchV)" CY - Berlin, Deutschland DA - 1991-07-01 PY - 1991 SP - 1 EP - 12(?) CY - Berlin AN - OPUS4-21693 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Droste, Bernhard ED - Steen, H. T1 - Die Bewertung der Sicherheit von Umschließungen zur Lagerung von Flüssiggas T2 - 5. Kolloquium über Fragen der chemischen Sicherheitstechnik CY - Berlin, Deutschland DA - 1990-05-14 PY - 1990 SN - 389429-070-6 SP - 83 EP - 101 PB - Wirtschaftsverlag NW - Verlag für neue Wissenschaft GmbH CY - Bremerhaven AN - OPUS4-21694 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Mallon, Michael T1 - Eine gezielte Auswertung von Unfällen beim Umgang mit Flüssiggas (LPG) PY - 1990 SN - 0343-3560 VL - 3 SP - 41 EP - 49 PB - Thiekötter CY - Münster AN - OPUS4-21695 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Droste, Bernhard T1 - Testing and licensing of radioactive waste containers T2 - 3rd International Seminar on Radioactive Waste Products CY - Würzburg, Germany DA - 1997-06-23 PY - 1997 SN - 3-89336-225-8 SN - 1433-5522 N1 - Serientitel: Schriften des Forschungszentrums Jülich - Reihe Energietechnik / Energy Technology – Series title: Schriften des Forschungszentrums Jülich - Reihe Energietechnik / Energy Technology VL - 2 SP - 173 EP - 180 AN - OPUS4-21657 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Ballheimer, Viktor A1 - Zeisler, Peter A1 - Tso, C.F. A1 - Donelan, P. A1 - Hüggenberg, R. ED - Droste, B. ED - Kowalewsky, H. T1 - Evaluation of safety of casks impacting different types of targets T2 - PATRAM 98 - 12th International conference on the packaging and transportation of radioactive materials CY - Paris, France DA - 1998-05-10 PY - 1998 VL - 3 SP - 1343 EP - 1351 PB - Nuclear Technology Publishing CY - Paris, France AN - OPUS4-21658 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Völzke, Holger A1 - Droste, Bernhard T1 - Entwicklung von Beurteilungsmethoden für Transport- und Lagerbehälter mit erhöhten metallischen Reststoffanteilen (EBER) - FEM-Berechnungen zum Aufprall kubischer Gußcontainer T2 - V. Stilllegungskolloquium Hannover und 4. Statusbericht "Stilllegung und Rückbau kerntechnischer Anlagen" CY - Hannover, Deutschland DA - 1997-06-24 PY - 1997 SP - 264 EP - 275 AN - OPUS4-21659 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Zeisler, Peter A1 - Droste, Bernhard A1 - Rödel, Roland T1 - Current approval status and test procedures for large type B packages in Germany PY - 1997 SN - 0957-476X VL - 8 IS - 1 SP - 53 EP - 62 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21663 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Völzke, Holger A1 - Wieser, Günter A1 - Zencker, Uwe A1 - Droste, Bernhard T1 - Mechanical and thermal safety analyses and demonstrations for cubic DCI multipurpose containers PY - 1997 SN - 0957-476X VL - 8 IS - 3-4 SP - 247 EP - 252 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21664 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Völzke, Holger A1 - Wieser, Günter A1 - Zencker, Uwe A1 - Droste, Bernhard T1 - Mechanical and thermal safety analyses and demonstrations for cubic DCI - multi-purpose containers T2 - 4th International conference on transportation for the nuclear industry CY - Bournemouth, Dorset, UK DA - 1997-05-13 PY - 1997 IS - Session 2, Paper 5 SP - 1 EP - 13 AN - OPUS4-21665 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zeisler, Peter A1 - Droste, Bernhard A1 - Rödel, Roland A1 - Rehmer, Birgit T1 - Current approval procedures for type-B packages in Germany: Selected topics T2 - PATRAM ´95 - 11th International Conference on the packaging and transportation of radioactive materials CY - Las Vegas, Nevada, USA DA - 1995-12-03 PY - 1995 SP - 488 EP - 495 AN - OPUS4-21638 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CHAP A1 - Droste, Bernhard T1 - Safety measures PY - 1995 SN - 3-527-20138-6 N1 - Serientitel: Ullmann´s Encyclopedia of industrial chemistry – Series title: Ullmann´s Encyclopedia of industrial chemistry VL - B8 IS - Chapter 4 SP - 517 EP - 523 PB - VCH Verl.-Ges. AN - OPUS4-21639 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Völzke, Holger T1 - EBER - Entwicklung von Beurteilungsmethoden für Transport- und Lagerbehälter mit erhöhten metallischen Reststoffanteilen T2 - IV. Stilllegungskolloquium Hannover und 3. Statusbericht "Stilllegung und Rückbau kerntechnischer Anlagen" CY - Bad Dürkheim, Deutschland DA - 1995-11-08 PY - 1995 SP - 425 EP - 435 AN - OPUS4-21640 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Zeisler, Peter A1 - Völzke, Holger A1 - Rödel, Roland T1 - Development and evaluation of containers for radioactive waste disposal T2 - Developments in the transport of radioactive waste CY - Vienna, Austria DA - 1994-02-21 PY - 1994 SN - 1011-4289 IS - IAEA-TECDOC-802 SP - 233 EP - 238 AN - OPUS4-21641 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Gogolin, B. A1 - Rödel, R. A1 - Völzke, Holger A1 - Kowalewsky, Helmut T1 - Die sicherheitstechnische Prüfung von Tranport- und Lagerbehältern für abgebrannte Kernbrennstoffe T2 - Jahrestagung Kerntechnik `98 CY - München, Deutschland DA - 1998-05-26 PY - 1998 SN - 0720-9207 SP - 279 EP - 282 PB - Inforum AN - OPUS4-21607 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Völzke, Holger A1 - Zencker, Uwe A1 - Wieser, Günter A1 - Droste, Bernhard T1 - Testing and licensing of radioactive waste containers for disposal in Germany T2 - DisTec `98 - International conference on radioactive waste disposal CY - Hamburg, Germany DA - 1998-09-09 PY - 1998 VL - 2 SP - 431 EP - 436 PB - KONTEC CY - Hamburg AN - OPUS4-21608 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Wieser, Günter A1 - Probst, Ulrich T1 - Thermal test requirements and their verification by different test methods N2 - 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. T2 - PATRAM ´92 - 10th International symposium on the packaging and transportation of radioactive materials CY - Yokohama, Japan DA - 1992-09-13 PY - 1992 VL - 3 SP - 1263 EP - 1272 AN - OPUS4-21822 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Gogolin, Bernd A1 - Quercetti, Thomas A1 - Rittscher, D. T1 - Drop test of a cubic DCI container for radioactive wastes T2 - PATRAM ´92 - 10th International symposium on the packaging and transportation of radioactive materials CY - Yokohama, Japan DA - 1992-09-13 PY - 1992 VL - 3 SP - 1435 EP - 1442 AN - OPUS4-21823 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schulz-Forberg, Bernd A1 - Zeisler, Peter A1 - Droste, Bernhard A1 - Kondratiev, A. A1 - Kozlov, J. A1 - Tichinov, N. T1 - Soviet-German cooperation in safety improvements of spent fuel transport casks N2 - The paper gives a survey of the Soviet (Russian) -German activities which started in 1988 with the objective of creating a long-term scientific-technical cooperation in the field of transport and storage casks for spent nuclear fuel. The first step, i.e., the step of informing each other about the state of development is done. The more complicated second phase with concerted common activities of both the Russian and German competent authorities and industrial enterprises is intended to start in the near future. T2 - PATRAM ´92 - 10th International symposium on the packaging and transportation of radioactive materials CY - Yokohama, Japan DA - 1992-09-13 PY - 1992 VL - 1 SP - 343 EP - 350 AN - OPUS4-21824 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wieser, Günter A1 - Droste, Bernhard T1 - Full-scale versus small-scale fire testing of fire protection materials for LPG storage vessels N2 - This paper presents test results of different fire test series with full-scale fire engulfment (4.85m³ propane vessels protected with an intumescent coating, rock wool or two cementitious fire protection materials based on vermiculite and Portland cement). Furthermore, the correlation of these tests with furnace plate tests and/or numerical calculations are discussed. It is our aim to present a method or way for the usefulness of small-scale fire tests. This method has to be quantified and statistically proved. The paper is a revision and amplification of /13/. T2 - 7th International symposium on loss prevention and safety promotion in the process industries CY - Taormina, Italy DA - 1992-05-04 PY - 1992 IS - Paper 75 SP - 1 EP - 20 AN - OPUS4-21825 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wieser, Günter A1 - Droste, Bernhard T1 - Full-scale and small-scale fire protection matials for vessels containing pressurised inflammable gases N2 - This paper will present test results of different fire test series with full-scale fire engulfment tests (4.85 m³ propane tanks protected with an intumescent coating, rock wool or a heat insulator based on vermiculite and Portland cement). Furthermore, the correlation of these tests with furnace plate tests and/or numerical calculations will be discussed. T2 - IMEKO/GESA Symposium - Risk minimization by experimental mechanics PY - 1992 SP - 345 EP - 356 PB - VDI-Verl. AN - OPUS4-21826 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Musolff, André A1 - Müller, Karsten A1 - Quercetti, Thomas T1 - Drop and fire testing of spent fuel and HLW transport casks at "BAM test site technical safety" - 10079 T2 - WM2010 - 36th Annual radioactive waste management symposium CY - Phoenix, Arizona, USA DA - 2010-03-07 KW - transport packages of radioactive materials KW - Safety KW - Mechanical tests KW - Thermal tests KW - Drop test facility KW - Fire test facilities KW - Numerical calculations PY - 2010 SN - 978-0-9828171-0-0 SP - 1 EP - 11 CY - Tempe, AZ, USA AN - OPUS4-21830 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Völzke, Holger A1 - Droste, Bernhard A1 - Rödel, Roland T1 - Experiences and status in safety assessment methods within the scope of licensing procedures for multi-purpose flasks in Germany PY - 2000 SN - 0957-476X VL - 11 IS - 1-2 SP - 39 EP - 43 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21856 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Zencker, Uwe A1 - Zeisler, Peter A1 - Droste, Bernhard T1 - Dynamic fracture mechanics assessments for cubic ductile cast iron containers PY - 2000 SN - 0957-476X VL - 11 IS - 1-2 SP - 113 EP - 118 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21857 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Quercetti, Thomas A1 - Gogolin, Bernd T1 - Test facilities for radioactive materials transport packagings (BAM, Germany) PY - 2001 SN - 0957-476X VL - 12 IS - 2/3 SP - 105 EP - 113 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21858 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Ballheimer, Viktor A1 - Probst, Axel A1 - Droste, Bernhard T1 - Numerical assessment of spent fuel casks impacting on real targets PY - 2000 SN - 0957-476X VL - 11 IS - 1-2 SP - 45 EP - 51 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21859 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Probst, Ulrich T1 - CASTOR-Behälter im Explosionsbereich eines Propan-Kesselwagens N2 - 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]. PY - 2001 SN - 1434-9728 SN - 1436-4948 SN - 0372-2457 SN - 0376-1185 VL - 42 IS - 11/12 SP - 15 EP - 17 PB - Springer-VDI-Verl. CY - Düsseldorf AN - OPUS4-21860 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Wie sicher sind CASTOR-Behälter? T2 - Praxisseminar "Radioaktive Stoffe - Recht, Umgang und Beförderung von Gütern der Klasse 7" CY - München, Deutschland DA - 2001-12-10 PY - 2001 IS - 069.01 SP - 1 EP - 15 PB - Moderne Industrie AG & Co. KG CY - Landsberg AN - OPUS4-21861 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Versuche mit unterschiedlichen Brandschutzmaterialien für die Erstellung von Prüfungszeugnissen T2 - Brandschutzarten in Lägern für druckverflüssigte, brennbare Gase (Seminar S-72-303-096-2) CY - Essen, Deutschland DA - 1992-03-25 PY - 1992 SP - 1 EP - 8(?) CY - Essen AN - OPUS4-21797 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Sicherheitsabstände und Möglichkeiten zu deren Verringerung T2 - Seminar "Flüssiggaslagerung: Neueste technische und rechtliche Vorschriften-Anwendung" CY - Berlin, Deutschland DA - 1992-03-12 PY - 1992 SP - 1 EP - 18(?) CY - Berlin AN - OPUS4-21798 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard T1 - Fire protection of LPG tanks with thin sublimation and intumescent coatings PY - 1992 SN - 0015-2684 SN - 1572-8099 VL - 28 IS - 3 SP - 257 EP - 269 PB - Kluwer Academic CY - Norwell, Mass. AN - OPUS4-21799 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Package testing T2 - Joint IAEA/EC course on the safe transport of radioactive material CY - Mol, Belgium DA - 1996-10-07 PY - 1996 IS - Chapter 15 SP - 197 EP - 209 CY - Vienna, Austria AN - OPUS4-21800 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Quercetti, Thomas A1 - Gogolin, Bernd A1 - Droste, Bernhard T1 - Nachweis der mechanischen Integrität eines "POLLUX" Transport- und Endlagerbehälters: Instrumentierte Freifallprüfungen T2 - GESA-Symposium - Experimentelle Beanspruchungsanalyse, Neue Entwicklungen und Anwendungen CY - Schliersee, Deutschland DA - 1996-10-10 PY - 1996 SP - 1 EP - 3(?) CY - Düsseldorf AN - OPUS4-21801 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Zulassungen und Prüfungen von Transport- und Lagerbehältern T2 - GRS Workshop "Genehmigung der Zwischenlagerung bestrahlter Brennelemente und Abfälle in Behältern" CY - Berlin, Deutschland DA - 1996-05-06 PY - 1996 N1 - Sprachen: Deutsch/Russisch - Languages: German/Russian IS - Kap. 2.4 SP - 1 EP - 23 CY - Berlin AN - OPUS4-21802 LA - mul AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Passive containment, monitoring and heat removal of spent fuel and HLW in multi-purpose metal casks T2 - Post-SMiRT 14 - International Seminar 18 - Passive safety features in nuclear installations CY - Pisa, Italy DA - 1997-08-25 PY - 1997 SP - C 2.25 EP - C 2.31 CY - Pisa, Italy AN - OPUS4-21803 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Musolff, André A1 - Droste, Bernhard A1 - Quercetti, Thomas A1 - Müller, Karsten T1 - Durchführung experimenteller Fallprüfungen im Rahmen der mechanischen Bauartprüfung von Transportbehältern für radioaktive Stoffe T2 - Jahrestagung Kerntechnik 2010 CY - Berlin, Deutschland DA - 2010-05-04 PY - 2010 SP - 1 EP - 7 CY - Berlin AN - OPUS4-22770 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Musolff, André A1 - Quercetti, Thomas A1 - Müller, Karsten A1 - Droste, Bernhard A1 - Komann, Steffen T1 - Drop test program with the half-scale model CASTOR HAW/TB2 T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Spent fuel transport cask KW - Drop test KW - Impact limiter KW - Measurement procedure PY - 2010 SP - 1 EP - 8 AN - OPUS4-22771 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard T1 - Eine Fallstudie KW - Transport radioaktiver Stoffe KW - Gefahrgutrechtliche Bauartprüfung KW - Fallversuche KW - Finite-Elemente-Berechnungen PY - 2010 SN - 0944-6117 IS - 02 SP - 26 EP - 28 PB - Vogel CY - München AN - OPUS4-20879 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Wille, Frank T1 - Transport of large nuclear power plant components: experiences in mechanical design assessment N2 - In the course of decommissioning of power plants in Germany large nuclear components (steam generator, reactor pressure vessel) must be transported over public traffic routes to interim storage facilities, where they are dismantled or stored temporarily. Since it concerns surface contaminated objects or low specific activity materials, a safety evaluation considering the IAEA transport regulations mainly for industrial packages (type IP-2) is necessary. For these types of industrial packages the requirements from normal transport conditions are to be covered for the mechanical proof. For example, a free drop of the package from a defined height, in dependence of its mass, onto an unyielding target, and a stacking test are required. Since physical drop tests are impossible generally due to the singularity of such 'packages', a calculation has to be performed, preferably by a complex numerical analysis. The assessment of the loads takes place on the basis of local stress distributions, also with consideration of radiation induced brittleness of the material and with consideration of recent scientific investigation results. Large nuclear components have typically been transported in an unpackaged manner, so that the external shell of the component provides the packaging wall. The investigation must consider the entire component including all penetration areas such as manholes or nozzles. According to the present IAEA regulations the drop position is to be examined, which causes the maximum damage to the package. In the case of a transport under special arrangement a drop only in an attitude representing the usual handling position (administratively controlled) is necessary. If dose rate values of the package are higher than maximum allowable values for a public transport, then it is necessary that additional shielding construction units are attached to the large component. KW - Radioactive material KW - Large components KW - Decommissioning KW - Nuclear power plant KW - Mechanical assessment KW - Numerical analysis PY - 2009 U6 - https://doi.org/10.1179/174650909X12543085665266 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 20 IS - 4 SP - 149 EP - 153 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-20820 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Aktuelle Entwicklungen auf dem Gebiet der verkehrsrechtlichen Behälterbauartprüfung T2 - 2. RAM-Behältersicherheitstage, BAM CY - Berlin, Germany DA - 2010-03-18 PY - 2010 AN - OPUS4-20967 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Ballheimer, Viktor A1 - Koch, Frank A1 - Kuschke, Christian A1 - Droste, Bernhard T1 - Similarity aspects for closure systems in reduced scale package drop testing KW - Transport cask KW - Drop test KW - Scale model KW - Closure system KW - Bolted joints PY - 2010 U6 - https://doi.org/10.1179/174650909X12603543809800 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 21 IS - 1 SP - 31 EP - 36 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-21178 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Wille, Frank T1 - Transport von Großkomponenten aus der Stilllegung kerntechnischer Anlagen - Erfahrungen bei der mechanischen Bewertung T2 - Jahrestagung Kerntechnik 2010 CY - Berlin, Deutschland DA - 2010-05-04 KW - Kerntechnische Anlagen KW - Rückbau KW - Mechanische Bewertung KW - Großkomponenten KW - Numerische Analyse PY - 2010 IS - Sektion 7 / 706 SP - 1 EP - 5 CY - Berlin AN - OPUS4-21239 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Neumann, Martin A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Weber, Mike A1 - Qiao, Linan A1 - Droste, Bernhard T1 - Static and dynamic calculation approaches for mechanical design assessment of type B packages for radioactive material transport - 10193 T2 - WM2010 Conference CY - Phoenix, Arizona, USA DA - 2010-03-07 KW - Mechanische Bewertung KW - Radioaktives Material KW - Numerische Analyse KW - Typ B(U)-Verpackung PY - 2010 SP - 1 EP - 9 AN - OPUS4-21240 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Droste, Bernhard A1 - Zencker, Uwe A1 - Komann, Steffen T1 - Reflektion der verkehrsrechtlichen Bauartprüfung des CASTOR HAW 28M aus Sicht der zuständigen Behörde BAM T2 - Jahrestagung Kerntechnik 2010 CY - Berlin, Deutschland DA - 2010-05-04 KW - Bauartprüfung KW - Fallprüfungen KW - Transportbehälter KW - FEM PY - 2010 SP - 1 EP - 5 CY - Berlin AN - OPUS4-21241 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Ulrich, Armin A1 - Borch, Jörg-Peter T1 - Brandnew Fire Test facilities at "BAM Test Site Technical Safety" T2 - 16th International Symposium on the Packaging and transportation of Radioactive Materials PATRAM CY - London, England DA - 2010-10-03 PY - 2010 AN - OPUS4-22129 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schön, Wolfgang A1 - Droste, Bernhard T1 - Wasserberieselung im Brandversuch T2 - Seminar Nr. S-70-001-096-8 Wasserberieselung CY - Essen, Deutschland DA - 1988-12-05 PY - 1988 SP - 1 EP - 12 PB - Haus d. Technik CY - Essen AN - OPUS4-22130 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Musolff, André A1 - Müller, Karsten A1 - Quercetti, Thomas T1 - Drop and Fire Testing of spent Fuel and HLW Transport Casks at "BAM Test Site Technical safety" T2 - Waste Management Conference !M 2010 CY - Phoenix, AZ, USA DA - 2010-03-07 PY - 2010 AN - OPUS4-22131 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Wolff, Dietmar A1 - Völzke, Holger A1 - Wille, Frank T1 - Overview on long term storage of spent nuclear fuel and high active waste in transport casks in Germany T2 - Concultant Service Meeting "Working Group on the Evaluation of a Safety Case for the Cual Use Cask for Spent Nuclear Fuel", IAEA CY - Vienna, Austria DA - 2010-11-01 PY - 2010 AN - OPUS4-22262 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Weber, Mike A1 - Qiao, Linan A1 - Droste, Bernhard A1 - Völzke, Holger T1 - Mechanical safety analyses of cast iron containers for the KONRAD repository N2 - Within the last years BAM has carried out numerous drop tests with prototype casks made of ductile cast iron onto targets according to the requirements for final disposal of non-heat generating waste in the German KONRAD repository. The results have shown that the target specifications in the acceptance criteria have to be defined more accurately to get reproducible test results with high precision. Hence, a suitable test stand foundation was developed with much effort. The integrity of the upper concrete layer of this target must be preserved during a test. Recently the geometrical properties of a tested cubic cast iron container led to a concentration of the impact forces beneath the container walls. The target was damaged strongly with the consequence of inadmissible reduction of cask stresses. For that reason the target construction was modified. However, the basic design was not changed. A prefabricated concrete slab was still joined by a mortar layer to the IAEA target of the BAM drop test facility. In the course of the optimization of the test stand foundation the concrete slab dimensions and the reinforcement were enlarged. During the drop test repetition the target kept intact. Additionally, the mechanical behavior of the cast iron container and the target was analyzed by finite element calculations. This improved target construction is suggested as a reference target for drop tests with casks whose mass and base area are covered by the container types VI or VII respectively according to the KONRAD repository acceptance criteria. The measurements during the drop tests with cast iron casks have provided the strains on the cask surface at selected positions. This allows the verification of finite element simulations of drop tests which show the stress distribution also inside the component. In September 2008 a drop test was carried out with a cylindrical cast iron cask containing an artificial material defect which was designed under consideration of critical stress states in the cask body. This drop test could demonstrate the safety against failure by fracture of a cask made of a special cast iron with reduced fracture toughness. T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Ductile iron KW - Container design KW - Safety assessment KW - Fracture mechanics KW - Dynamic loading conditions PY - 2010 SP - 1 EP - 8 (Session T28 / Paper 220) AN - OPUS4-23844 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Musolff, André A1 - Müller, Karsten A1 - Quercetti, Thomas T1 - Drop and fire testing of spent fuel and HLW transport casks at 'BAM test site technical safety' N2 - BAM, as a 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 the open air BAM Test Site 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), BAM constructed in 2004 a large drop test facility capable to handle 200 ton test objects, and to drop them onto a steel plate covered unyielding target with a mass of nearly 2600 ton. Drop test campaigns of the 181 ton GNS CONSTOR V/TC, the 129 ton MHI MSF-69BG and a 1:2 scale model of the GNS CASTOR HAW28M (CASTOR HAW/TB2) have been performed since then. The experimental BAM drop testing activities can be supported also by drop testing of smaller packages (up to 2 ton) in an in-house test facility and by dynamic, guided impact testing of package components and material specimen 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 computational investigations, where BAM operates appropriate finite element modelling on appropriate computer codes, e.g. ABAQUS, LS-DYNA, ANSYS and other analytical tools. KW - Package testing KW - Drop testing KW - Fire testing KW - Regulations PY - 2011 U6 - https://doi.org/10.1179/1746510912Y.0000000002 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 22 IS - 4 SP - 200 EP - 205 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-26691 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Ulrich, Armin A1 - Borch, Jörg-Peter T1 - Brand new fire test facilities at 'BAM test site technical safety' N2 - Fire testing is an essential part of the hypothetical, cumulative mechanical and thermal accident test conditions that shall guarantee package safety in severe accidents. Not only for radioactive material transport packages but also for other containments of dangerous goods, international standards require specific thermal load specifications. Following the guideline ‘Safety in technology and chemistry' BAM, as a scientific and technical German federal government institute, operates a 12 km² large open air test facility for experimental investigations of dangerous goods and their containments. On an area beside the well-known 200-ton drop test facility, BAM has put into operation a new fire test facility. This facility provides two fire test stands that utilise liquid propane as fuel from a central, earth-covered 60m³ LPG storage tank. From that storage the propane is pumped via pipelines to the test stands where the gas is released from nozzles, and ignited by ignition burners. The fire exposure test facility areas are 12×8 m. Fire test facility B (with gas release nozzles submerged in a water pool) is designed for fire testing of containers that may burst during the test. Fire test facility A (with ring burner systems) is designed for heavy test objects up to 200 tons, e.g. for full-scale spent fuel casks. This paper presents a detailed description of the facility, insight into first tests performed, and results of calorimeter fire tests, using containers of various sizes, to verify the absorbed heat fluxes, demonstrating that regulatory fire test conditions are met, and that the propane fire is equivalent to a kerosene or heating oil pool fire. KW - Thermal testing KW - Fire testing KW - Regulations PY - 2011 U6 - https://doi.org/10.1179/1746510911Y.0000000011 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 22 IS - 4 SP - 195 EP - 199 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-26688 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nakagami, M. A1 - Quercetti, Thomas A1 - Komatsuki, S. A1 - Fujisawa, K. A1 - Nishio, T. A1 - Musolff, André A1 - Müller, Karsten A1 - Droste, Bernhard T1 - Waste container drop tests onto a concrete target N2 - The paper presents technical details of the drop test performance as well as some experimental results of tests carried out with the Japanese 'Yoyushindo-disposal' waste container for intermediate depth disposal. The tests were accompanied by various metrology to collect data as basis for safety assessment. T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Waste container KW - Drop test KW - Concrete target PY - 2010 SP - 1 EP - 8 (Paper 367) AN - OPUS4-27045 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Komann, Steffen A1 - Neumann, Martin A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Weber, Mike A1 - Qiao, Linan A1 - Droste, Bernhard T1 - Mechanical assessment within type B packages approval: application of static and dynamic calculation approaches N2 - This paper demonstrates exemplarily how numerical and experimental approaches can be combined reasonably in mechanical assessment of package integrity according to the IAEA regulations. The paper also concentrates on the question about how static mechanical approaches can be applied, and what their problems are in relation to dynamic calculation approaches. Under defined impact tests, which represent accident transport conditions, the package has to withstand impact loading, e.g. resulting from a 9 m free drop onto an unyielding target in sequence with a 1 m puncture drop test. Owing to the local character of the interaction between the puncture bar and the cask body, it is possible to develop a dynamic numerical model for the 1 m puncture drop which allows an appropriate simulation of the interaction area. Results from existing experimental drop tests with prototype or small scale cask models can be used for verification and validation of applied analysis codes and models. The link between analysis and experimental drop testing is described exemplarily by considering a regulatory 1 m puncture bar drop test onto the cask body of a recently approved German high level waste transport package. For the 9 m drop test of the package, it is difficult to develop a dynamic numerical model of the package due to the complexity of the interaction between cask body, impact limiters and unyielding target. Dynamic calculations require an extensive verification with experimental results. The simulation of a 9 m drop of a package with impact limiters is thereby often more complex than the simulation of a 1 m puncture drop onto the cask body. A different approximation method can be applied for the consideration of dynamic effects on the impact loading of the package. In a first step, maximum impact force and rigid body deceleration of the cask body during the impact process can be calculated with simplified numerical tools. This rigid body deceleration can subsequently be applied on a verified static numerical model. Dynamic effects, which cannot be covered by the static numerical analysis, have therefore to be considered by using an additional dynamic factor. The paper describes this approach exemplarily for a 9 m horizontal drop of a typical spent fuel cask design. KW - Package assessment KW - Package KW - Packaging KW - Structural analysis PY - 2011 U6 - https://doi.org/10.1179/1746510911Y.0000000012 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 22 IS - 4 SP - 179 EP - 183 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-26448 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Untersuchungen zur Sicherheit von Transport- und Lagerbehältern von radioaktiven Stoffen T2 - Kerntechnisches Kolloquium CY - Aachen, Germany DA - 2013-11-19 PY - 2013 AN - OPUS4-29756 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - A Survey on 35 Years of Packaging, Transport and Storage of Radioactive Materials T2 - 17th International Symposium on the Packaging and Transportation of Radioactive Materias (PATRAM 2013) CY - San Francisco, CA, USA DA - 2013-08-18 PY - 2013 AN - OPUS4-29757 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Wille, Frank T1 - Maintenance of Package Design Safety Report Effectiveness of SNF/HLW Dual Purpose Casks T2 - 17th international Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2013) CY - San Francisco, CA, USA DA - 2013-08-18 PY - 2013 AN - OPUS4-29761 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Wolff, Dietmar A1 - Droste, Bernhard A1 - Völzke, Holger A1 - Baden, M. T1 - German approach and experience feedback of transport ability of SNF packages after interim storage N2 - In Germany the concept of dry interim storage of spent fuel in dual purpose metal casks is implemented, currently for periods of up to 40 years. The casks being used have an approved package design in accordance with the international transport regulations. The license for dry storage is granted on the German Atomic Energy Act with respect to the recently revised “Guidelines for dry interim storage of irradiated fuel assemblies and heat-generating radioactive waste in casks” by the German Waste management Commission (ESK). For transport on public routes between or after long term interim storage periods, it has to be ensured that the transport and storage casks fulfil the specifications of the transport approval or other sufficient properties which satisfy the proofs for the compliance of the safety objectives at that time. In recent years the validation period of transport approval certificates for manufactured, loaded and stored packages were discussed among authorities and applicants. A case dependant system of 3, 5 and 10 years was established. There are consequences for the safety cases in the Package Design Safety Report including evaluation of long term behavior of components and specific operating procedures of the package. Present research and knowledge concerning the long term behavior of transport and storage cask components have to be consulted as well as experiences from interim cask storage operations. Challenges in the safety assessment are e.g. the behavior of aged metal and elastomeric gaskets under IAEA test conditions to ensure that the results of drop tests can be transferred to the compliance of the safety objectives at the time of transport after the interim storage period. T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 18.08.2013 KW - Storage KW - Transport KW - Lagerung KW - Verpackung KW - Radioactive material PY - 2013 SP - 1 EP - 9 PB - Omnipress AN - OPUS4-30159 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Erhard, Anton A1 - Völzke, Holger A1 - Droste, Bernhard A1 - Wolff, Dietmar A1 - Wille, Frank T1 - Nuclear power plant waste management strategy in Germany T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 2013-08-18 PY - 2013 SP - 1 EP - 11(?) PB - Omnipress AN - OPUS4-30135 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - A survey on 35 years of packaging, transport and storage of radioactive material T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 2013-08-18 PY - 2013 SP - 1 EP - 10(?) PB - Omnipress AN - OPUS4-30137 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Wille, Frank T1 - Maintenance of package design safety report effectiveness of SNF and HWL dual purpose casks T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 2013-08-18 PY - 2013 SP - 1 EP - 9(?) PB - Omnipress AN - OPUS4-30138 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Kumano, Y. A1 - Droste, Bernhard A1 - Hirose, M. A1 - Harvey, J. A1 - Reiche, I.. A1 - Wolff, Dietmar A1 - McConnell, P. A1 - Varley, K. T1 - Overview of the IAEA's joint working group on integrated safety case for dual purpose casks T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 2013-08-18 PY - 2013 SP - 1 EP - 9(?) PB - Omnipress AN - OPUS4-30140 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Komann, Steffen A1 - Wille, Frank A1 - Droste, Bernhard T1 - Transport von Großkomponenten aus der Stilllegung kerntechnischer Anlagen in Deutschland-Erfahrungen bei der mechanischen Intergritätsbewertung N2 - Im Zuge des Rückbaus kerntechnischer Anlagen in Deutschland müssen u. a. Großkomponenten (Dampferzeuger, Reaktordruckbehälter) über öffentliche Verkehrswege in Zwischenlager transportiert werden, in denen sie zerlegt bzw. zwischengelagert werden. Da es sich hierbei um aktivierte und/oder oberflächenkontaminierte Objekte handelt, ist eine Begutachtung unter Berücksichtigung der Gefahrgutbeförderungsvorschriften notwendig. In den meisten Fällen handelt es sich um oberflächenkontaminierte Gegenstände, welche als Industrieversandstücke des Typs IP-2 zu befördern sind. KW - Zwischenlagerung KW - Entsorgung KW - Kerntechnik KW - Radioaktive Stoffe PY - 2016 SN - 0005-6650 VL - Mai 2016 IS - Band 91 SP - 188 EP - 192 PB - Springer VDI Verlag CY - Düsseldorf AN - OPUS4-36852 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard T1 - Sichere Zwischenlagerung von ausgebrannten Kernbrennstoffen PY - 1983 SN - 0722-8562 VL - 83 IS - 24 SP - 733 PB - Umschau Verl. Breidenstein CY - Frankfurt, M. AN - OPUS4-36376 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Hübner, Heinz W. A1 - Probst, Ulrich T1 - Qualification and Certification Criteria of Casks for the Intermediate Dry Storage of Spent Fuel in the Federal Republic of Germany T2 - 7th International symposium Packaging and Transportation of Radioactive Materials CY - New Orleans, La., USA DA - 15.05.1983 PY - 1983 VL - 1 SP - 224 EP - 230 AN - OPUS4-36393 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Hübner, Heinz W. A1 - Probst, Ulrich T1 - Selection and certification of materials for casks intended for the transport and intermediate storage of spent fuel T2 - 7th International symposium Packaging and Transportation of Radioactive Materials CY - New Orleans, La., USA DA - 15.05.1983 PY - 1983 VL - 2 SP - 1048 EP - 1054 AN - OPUS4-36395 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Quercetti, Thomas A1 - Ballheimer, Viktor A1 - Droste, Bernhard A1 - Müller, Karsten T1 - Internal cask content collisions during drop test of transport casks for radioactive materials N2 - In transport casks for radioactive materials, significantly large axial and radial gaps between cask and internal content are often present because of certain specific geometrical dimensions of the content (e.g. spent fuel elements) or thermal reasons. The possibility of inner relative movement between content and cask will increase if the content is not fixed. During drop testing, these movements can lead to internal cask content collisions, causing significantly high loads on the cask components and the content itself. Especially in vertical drop test orientations onto a lid side of the cask, an internal collision induced by a delayed impact of the content onto the inner side of the lid can cause high stress peaks in the lid and the lid bolts with the risk of component failure as well as impairment of the leak tightness of the closure system. This paper reflects causes and effects of the phenomenon of internal impact on the basis of experimental results obtained from instrumented drop tests with transport casks and on the basis of analytical approaches. Furthermore, the paper concludes the importance of consideration of possible cask content collisions in the safety analysis of transport casks for radioactive materials under accident conditions of transport. KW - Drop test KW - Cask KW - Internal collision KW - Transport KW - Radioactive material PY - 2013 U6 - https://doi.org/10.1179/1746510913Y.0000000032 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 24 IS - 2 SP - 75 EP - 82 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-31306 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Wille, Frank T1 - Dicht und sicher abgeschirmt N2 - BAM-GGR Transportverpackungen für radioaktive Stoffe müssen den BAM-Gefahrgutregeln entsprechen. Ein kurzer Einblick in die Richtlinien. PY - 2014 SN - 0944-6117 VL - 3 SP - 18 EP - 20 PB - Vogel CY - München AN - OPUS4-30487 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Eisenacher, Germar A1 - Scheidemann, Robert A1 - Neumann, Martin A1 - Wille, Frank A1 - Droste, Bernhard T1 - Crushing characteristics of spruce wood used in impact limiters of type B packages T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 2013-08-18 KW - Spruce wood KW - Crush test KW - Impact limiter PY - 2013 SP - 1 EP - 10(?) PB - Omnipress AN - OPUS4-30219 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Auster, Jürgen A1 - Neumeyer, Tino A1 - Müller, Karsten A1 - Droste, Bernhard T1 - Leakage testing during lateral displacement of metallic seals under mechanical accident impact T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 2013-08-18 PY - 2013 SP - Paper 168, 1 EP - 6 PB - Omnipress AN - OPUS4-30282 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wolff, Dietmar A1 - Völzke, Holger A1 - Wille, Frank A1 - Droste, Bernhard T1 - Extended storage after long-term storage N2 - Existing spent nuclear fuel (SF) and high active waste (HAW) management policies and practices worldwide are the result of past presumptions that sufficient reprocessing and/or disposal capacity would be available in the near term. Consequently, in the past many countries have developed specific solutions for different periods of time due to their individual national nuclear policies. In Germany the concept of dry interim storage in dual purpose metal casks before disposal is being pursued for SF and HAW management and transport and storage licenses have been issued accordingly. The current operation licenses for existing storage facilities have been granted for a storage period of up to 40 years. This concept has demonstrated its suitability for over 20 years so far. Relevant safety requirements haven been assessed for the short-term as well as for the long-term for site-specific operational and accidental storage conditions. But in the meantime significant delays in the national repository siting procedure occured which will make extended storage periods necessary in the future. This paper describes the current situation in Germany with regard to dry cask storage and focuses on current perspectives considering regulatory, technical, and scientific aspects for storage license renewal. Since there is one case of a storage license limitation to only 20 years due to administrative reasons, first experience is currently gathered in case of an expiring storage license. Subsequent license options have been pursued intensively including the extension of the initial storage license as well as shipping all casks to another storage facility considering an extended storage period at that storage facility as well. All safety relevant aspects have to be reviewed on basis of the current state-of-the-art which might be different from the initial safety demonstrations. That includes new safety assessment standards as well as improved knowledge base. Major issues are e.g. improved accident scenario analyses, assessment methods, and consideration of aging effects from previous operation periods. Inspection programs with respect, e.g. to bolts and seals to verify leak-tightness and lid screw pre-stress have been initiated to demonstrate proper cask conditions for extended storage as well as transportation to another storage facility. T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 18.08.2013 KW - Extended storage KW - Long-term storage KW - Dual purpose cask PY - 2013 SP - Paper 184, 1 EP - 12 PB - Omnipress AN - OPUS4-30242 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin A1 - Wille, Frank A1 - Linnemann, Konrad A1 - Schubert, Sven A1 - Ballheimer, Viktor A1 - Sterthaus, Jens A1 - Droste, Bernhard T1 - Reflection on BAM mechanical design assessment of TN®24E spent fuel transport package N2 - TN®24 E, a new package design, was developed and applied for by Areva TN for German transport approval certificate. The certificate was issued by BfS, Federal Office for Radiation Protection, on 24th of July 2013. The package is designed as a dual purpose cask for transport and storage of up to 21 PWR spent fuel assemblies from German NPPs. BAM is the German competent authority responsible for the design assessment of RAM packages regarding mechanical and thermal safety cases, activity release analysis and all issues of quality assurance during manufacturing and operation of packages. Certain assessment experiences as well as new developments resulting from the BAM TN®24E approval procedure are presented. The mechanical safety case of the TN®24E is based mainly on finite element calculations, which were verified by the TN®81 1/3 scale drop test program performed at BAM. Thermal analyses rely upon calculations, while the activity release criterion is based upon leakage rate results of TN®81 drop tests. The BAM-GGR 012 guideline for the analysis of bolted lid and trunnion systems has been fully implemented. Due to requirements by BAM, AREVA TN developed a new assessment strategy for fracture mechanical evaluation of welding seams. The material qualification and documentation is also an important aspect of BAM assessment; the qualification of borated aluminum basket material, the determination of strength values for thermal aged hardened aluminum alloys for the basket or consideration of high burn-up fuel assemblies are remarkable issues in this context. In addition, the consideration of the material compatibility, especially taking into account a transport after 40 years of dry interim storage in German facilities, has gained significant importance in the licensing process of the TN®24E. Next to obvious mechanical issues such as the assessment of shell ovalization under 9 m drop test scenario and its impact on basket load, thermo-mechanical interactions had to be addressed in the safety case. Due to BAM requirements, AREVA TN performed a full thermo-mechanical analysis of the cask behavior under fire test conditions. T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 18.08.2013 KW - Transport KW - RAM KW - Radioactive material cask KW - Nuclear fuel PY - 2013 SP - 1 EP - 12 PB - Omnipress AN - OPUS4-30270 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Scheidemann, Robert A1 - Kasparek, Eva Maria A1 - Qiao, Linan A1 - Müller, Karsten A1 - Droste, Bernhard A1 - Völzke, Holger T1 - Dynamic penetration tests on shock absorbing damping concrete T2 - WM2014 Conference CY - Phoenix, Arizona, USA DA - 2014-03-02 KW - Drop test KW - Dynamic KW - Penetration KW - Damping concrete PY - 2014 SN - 978-0-9836186-3-8 SP - Paper 14166, 1 EP - 9 AN - OPUS4-31948 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Müller, Karsten A1 - Quercetti, Thomas A1 - Musolff, André A1 - Droste, Bernhard T1 - Quality assurance requirements for mechanical test campaigns of packagings N2 - A management system based on international, national or other standards acceptable to the competent authority shall be established and implemented for all activities including design, manufacture, testing, documentation, use, maintenance, inspection in accordance with IAEA SSR-6. Hereby, quality assured testing and documentation can substantially contribute to the demonstration of package design compliance with the regulations. Nowadays, a drop test campaign within the approval process of packages for radioactive materials can be a very complex and extensive project including various test and measurement techniques. On this basis of procedures and documents the experimental tests of packages and containers are performed with quality proofed results and a high reliability. A complete traceability and direct transferability of package design test results can give particular importance to the type approval procedure. T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 18.08.2013 KW - Quality assurance KW - Packaging KW - Drop test PY - 2013 SP - Paper 181, 1 EP - 7 PB - Omnipress AN - OPUS4-30493 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Überblick über 36 Jahre Transport und Lagerung radioaktiver Stoffe T2 - 4. RAM-Behältersicherheitstage, BAM CY - Berlin, Germany DA - 2014-03-26 PY - 2014 AN - OPUS4-31548 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Overwiew of Preparation of a Safety Case for a Dual Purpose Cask for Storage and Transport of Spent Fuel ans Recommendations to WASSC and TRANSSC from WASSC/TRANSSC Working Group T2 - International Workshop on the Developement and Application of a Safety Case for Dual Purpose Casks for Nuclear Spent Fuel CY - Vienna, Austria DA - 2014-05-19 PY - 2014 AN - OPUS4-31549 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Wille, Frank A1 - Komann, Steffen T1 - Gap Analysis Examples from Periodical Reviews of Transport Package Design Safety Reports of SNF/HLW Dual Purpose Casks T2 - 12th International Conference on Probabilisic Safety Assesment an Management PSAM 12 CY - Honolulu, HI, USA DA - 2014-06-22 PY - 2014 AN - OPUS4-31550 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Komann, Steffen A1 - Wille, Frank A1 - Rolle, Annette A1 - Probst, Ulrich A1 - Schubert, Sven T1 - Consideration of Aging Mechanisms Indluence on Transport Safety and Rliability of Dual Purpose Casks for Spent Nuclear Fuel or HLW T2 - 12th International Conference on Probabilistics Safety Assessment and Management PSAM 12 CY - Honolulu, HI, USA DA - 2014-06-22 PY - 2014 AN - OPUS4-31551 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Eisenacher, Germar A1 - Wille, Frank A1 - Droste, Bernhard A1 - Neumann, Martin T1 - Modeling of wood filled impact limiters for transport packages - 14111 N2 - Packages for the transport of SNF and HLW are usually equipped with impact limiters to reduce the loads that result from the regulatory 9 m drop test. A common impact limiter design in Germany is a welded steel sheet structure filled with wood. The material wood is the main energy absorber, while the steel sheet provides the integrity of the impact limiter. The IAEA allows mechanical safety cases of transport packages to be carried out computationally, as long as the models used are reliable. In this context, a Finite Element (FE) modeling approach for wood and its application to impact limiters in the calculation of a 9 m drop test is presented. A user material model for wood was developed for the dynamic FE-Code LS-DYNA. Its features are based on a series of crush tests with spruce wood specimens. The model considers wood as a material with transversely isotropic properties, i.e. in the directions parallel and perpendicular to the fiber. The plastic material behavior depends on the state of stress. This has shown to be important to account for the lateral constraint of wood in impact limiters resulting from steel sheet encapsulation. Lateral constraint or respectively, a multiaxial stress state, increases the compression strength level of wood, limits the softening effect and increases the hardening effect. Lateral constraint also increases volumetric and reduces deviatoric deformation. The wood material model considers various hardening and softening characteristics via input flow curves. It considers effects of temperature and strain rate on strength as well. The development of a multi-surface yield criterion and a plastic potential that enables the user input of plastic Poisson's ratios were the challenges during the development of material model. A dynamic FE calculation of a horizontal drop test with an 18,000 kg test package was performed. The wood material model was used to model the wooden impact limiter inlays. The impact limiter deformation and the package deceleration were compared to the experimental drop test results to rate the performance of the wood material model. T2 - WM2014 Conference CY - Phoenix, Arizona, USA DA - 02.03.2014 KW - Transport package KW - Radioactive material KW - Spruce wood KW - Impact limiter KW - Material model KW - Finite element PY - 2014 SN - 978-0-9836186-3-8 SP - 1 EP - 10 AN - OPUS4-30653 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Scheidemann, Robert A1 - Kasparek, Eva Maria A1 - Müller, Karsten A1 - Droste, Bernhard A1 - Völzke, Holger T1 - Model-sized and full-scale dynamic penetration tests on damping concrete N2 - Mechanical loading conditions of transport and storage casks for radioactive materials in accidental scenarios are highly affected by the behavior of both: the impact limiters and the footing materials. To minimize potential damages during the handling of casks, a so called damping concrete is frequently used for the footings in interim nuclear facilities. It obtains its shock absorbing properties through admixing of polymer cells. For a comprehensive mechanical evaluation of casks, advanced material models are also needed for damping concrete. In order to characterize the mechanical properties and to develop numerical material models, penetration tests were carried out at different test facilities of BAM. The tests contain static and dynamic penetration tests on cubic specimen with an edge length of 100 mm as well as mortared specimen with a size of 240 x 240 x 50 cm³. Indenters with different geometries and diameters were used for these model-sized penetration tests. Subsequently a full-scale cylindrical cast-iron indenter with a diameter of 110 cm was dropped of 5 m height on a realistic damping concrete footing. T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 18.08.2013 KW - Drop test KW - Dynamic KW - Penetration KW - Damping concrete PY - 2013 SP - 1 EP - 10 PB - Omnipress AN - OPUS4-30233 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Musolff, André A1 - Quercetti, Thomas A1 - Müller, Karsten A1 - Droste, Bernhard A1 - Gründer, Klaus-Peter T1 - Experimental testing of impact limiters for RAM packages under drop test conditions N2 - In context with new cask designs and their approval procedure, the experimental testing of impact limiters under drop test conditions becomes more and more important in order to assess the damage mechanics behaviour and safety margins for validation reasons. In recent years, various designs of impact limiters have been tested by the Federal Institute for Materials Research and Testing within specific component testing and particularly with regard to type B package design approval procedures. The paper focuses on the experimental realisation of impact limiter tests and presents implemented measurement techniques to determine the amount of deformation and to explain the impact behaviour by means of photogrammetric metrology and three-dimensional fringe projection method, high speed motion analysis and adjusted deceleration measurements. T2 - PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials CY - San Francisco, CA, USA DA - 18.08.2013 KW - Drop test KW - Impact limiters KW - RAM packages KW - Measurement methods PY - 2013 SP - 1 EP - 9 PB - Omnipress AN - OPUS4-31040 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Musolff, André A1 - Quercetti, Thomas A1 - Droste, Bernhard A1 - Müller, Karsten A1 - Gründer, Klaus-Peter T1 - Experimental investigation of RAM packages impact limiters - 14256 N2 - In context with new cask designs and their approval procedure the experimental testing of impact limiters under drop test conditions becomes more and more important in order to assess the damage mechanics behavior and safety margins for validation reasons. In recent years various designs of impact limiters have been tested by the Federal Institute for Materials Research and Testing (BAM) within specific component testing and particularly with regard to type B package design approval procedures. The paper focuses on the experimental realization of impact limiter tests and presents implemented measurement techniques to determine the amount of deformation and to explain the impact behavior by means of photogrammetric metrology and 3-d fringe projection method, high-speed motion analysis and adjusted deceleration measurements. T2 - WM2014 Conference CY - Phoenix, Arizona, USA DA - 02.03.2014 KW - Drop test KW - Impact limiters KW - RAM packages KW - Measurement methods PY - 2014 SN - 978-0-9836186-3-8 SP - Paper 14256, 1 EP - 10 AN - OPUS4-31050 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Hübner, Heinz W. A1 - Probst, Ulrich T1 - Brandversuche mit Tanks zur oberirdischen Lagerung von Flüssiggas PY - 1984 SN - 1434-9728 SN - 1436-4948 SN - 0372-2457 SN - 0376-1185 VL - 25 IS - 6 SP - 272 EP - 276 PB - Springer-VDI-Verl. CY - Düsseldorf AN - OPUS4-19021 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schulz-Forberg, Bernd A1 - Droste, Bernhard A1 - Charlett, H. T1 - Failure mechanisms of propane-tanks under thermal stresses including fire engulfment T2 - Transport and storage of LPG and LNG CY - Bruges, Belgium DA - 07.05.1984 PY - 1984 IS - 1 SP - 295 EP - 305 PB - Koninklijke Vlaamse Ingenieursvereniging CY - Antwerpen AN - OPUS4-19022 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard T1 - Brandschutzausrüstungen von Flüssiggaslagertanks PY - 1988 SN - 0340-7551 VL - 18 IS - 1 SP - 18 EP - 24 PB - Bundesanstalt für Materialforschung und -prüfung CY - Berlin AN - OPUS4-19024 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Schön, W. A1 - Droste, Bernhard T1 - Investigations of water spraying systems for LPG storage tanks by full scale fire tests PY - 1988 SN - 0304-3894 VL - 20 SP - 73 EP - 82 PB - Elsevier CY - Amsterdam AN - OPUS4-19025 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Schön, W. T1 - Full scale fire tests with unprotected and thermal insulated LPG storage tanks PY - 1988 SN - 0304-3894 VL - 20 SP - 41 EP - 53 PB - Elsevier CY - Amsterdam AN - OPUS4-19026 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Schön, W. A1 - Droste, Bernhard T1 - Brandschutz bei Flüssiggas-Lagertanks. Die Wasserberieselung von Flüssiggas-Lagertanks im Vergleich zu anderen Brandschutzmaßnahmen PY - 1988 SN - 1434-9728 SN - 1436-4948 SN - 0372-2457 SN - 0376-1185 VL - 29 IS - 4 SP - 115 EP - 119 PB - Springer-VDI-Verl. CY - Düsseldorf AN - OPUS4-19027 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Blümel, Peter T1 - Amtliche Bekanntmachungen. Die Verträglichkeit von Füllgut und Wandungswerkstoff - eine wesentliche Vorraussetzung der Genehmigung von Lager- und Transportbehältern für gefährliche Stoffe - Teil 1 PY - 1981 SN - 0340-7551 VL - 11 IS - 1 SP - 31 EP - 44 PB - Bundesanstalt für Materialforschung und -prüfung CY - Berlin AN - OPUS4-19030 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Blümel, Peter T1 - Amtliche Bekanntmachungen. Die Verträglichkeit von Füllgut und Wandungswerkstoff - eine wesentliche Vorraussetzung der Genehmigung von Lager- und Transportbehältern für gefährliche Stoffe - Teil 2 PY - 1981 SN - 0340-7551 VL - 11 IS - 3 SP - 235 EP - 240 PB - Bundesanstalt für Materialforschung und -prüfung CY - Berlin AN - OPUS4-19031 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Hübner, Heinz W. A1 - Wieser, Karol E. T1 - Quality assurance measures for RAM-Packagings in the Federal Republic of Germany T2 - PATRAM ´80 - 6th International symposium on the packaging and transportation of radioactive materials CY - Berlin, Germany DA - 1980-11-10 PY - 1981 VL - 1 SP - 708 EP - 713 PB - Bundesanstalt für Materialprüfung CY - Springfield, Va. AN - OPUS4-19032 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schön, W. A1 - Probst, Ulrich A1 - Droste, Bernhard T1 - Experimental investigations of fire protection measures for LPG storage tanks T2 - 6th international symposium on loss prevention and safety promotion in the process industries CY - Oslo, Norway DA - 1989-06-19 PY - 1989 VL - 4 SP - 51/1 EP - 51/17 PB - European Federation of Chemical Engineering CY - Oslo AN - OPUS4-19876 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Mallon, Michael T1 - A statistical review of the reasons leading to LPG accidents T2 - 6th international symposium on loss prevention and safety promotion in the process industries CY - Oslo, Norway DA - 1989-06-19 PY - 1989 VL - 2 SP - 79/1 EP - 79/25 PB - European Federation of Chemical Engineering CY - Oslo AN - OPUS4-19879 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Droste, Bernhard A1 - Wieser, Karol E. ED - Warnecke, E. ED - Giller, H. T1 - Behälter zur Endlagerung radioaktiver Abfälle - Vorgehen bei der Bauartprüfung - T2 - 85. PTB-Seminar CY - Braunschweig, Deutschland DA - 1989-07-17 PY - 1989 SN - 3-88314-942-X SN - 0721-0892 N1 - Serientitel: PTB-Bericht – Series title: PTB-Bericht IS - SE-25 SP - 133 EP - 150 PB - Wirtschaftsverl. CY - Bremerhaven AN - OPUS4-19884 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Völzke, Holger A1 - Droste, Bernhard T1 - Entwicklung von Beurteilungsmethoden für Transport- und Lagerbehälter mit erhöhten metallischen Reststoffanteilen - Weiterführende Untersuchungen (EBER II) T2 - VI. Stilllegungskolloquium Hannover und 5. Statusbericht "Stilllegung und Rückbau kerntechnischer Anlagen" CY - Hannover, Deutschland DA - 2000-04-13 PY - 2000 SP - 315 EP - 326 AN - OPUS4-21591 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Prüfungen im verkehrsrechtlichen Zulassungsverfahren von Transportbehältern T2 - 1. Symposium - Beförderung radioaktiver Stoffe CY - Hannover, Deutschland DA - 1999-11-18 PY - 1999 SP - 1 EP - 16(?) CY - Hannover AN - OPUS4-21592 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Droste, Bernhard ED - Schulz-Forberg, Bernd ED - Hübner, W. T1 - Die Untersuchung extremer Unfalleinwirkungen auf Transportbehälter für radioaktive Stoffe PY - 1999 SN - 3-89701-299-5 SN - 0938-5533 SP - 7 EP - 10 PB - Wirtschaftsverlag NW CY - Bremerhaven AN - OPUS4-21593 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Völzke, Holger T1 - Prüfungen an Zwischenlagerbehältern zur Belastbarkeit bei Einwirkungen von innen und aussen T2 - Zwischenlager-Workshop CY - Jülich, Deutschland DA - 2001-01-23 PY - 2001 SP - 177 EP - 221 CY - Jülich AN - OPUS4-21569 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Quercetti, Thomas A1 - Wieser, Günter A1 - Völzke, Holger A1 - Droste, Bernhard ED - Droste, B. ED - Kowalewsky, H. T1 - Mechanical impact assessment of cubic waste containers depending on target construction T2 - PATRAM 98 - 12th International conference on the packaging and transportation of radioactive materials CY - Paris, France DA - 1998-05-10 PY - 1998 VL - 3 SP - 1152 EP - 1159 PB - Nuclear Technology Publishing CY - Paris, France AN - OPUS4-21556 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zeisler, Peter A1 - Droste, Bernhard A1 - Rehmer, Birgit A1 - Rödel, R. ED - Droste, B. ED - Kowalewsky, H. T1 - A new fracture mechanics assessment method for ferritic steel components of type B packages T2 - PATRAM 98 - 12th International conference on the packaging and transportation of radioactive materials CY - Paris, France DA - 1998-05-10 PY - 1998 VL - 1 SP - 309 EP - 316 PB - Nuclear Technology Publishing CY - Paris, France AN - OPUS4-21558 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Droste, Bernhard T1 - Bauartprüfung, Qualitätssicherung und Sonderversuche mit CASTOR-Behältern T2 - Fachtagung "Standortnahe Zwischenlager" CY - Bonn, Deutschland DA - 2001-03-14 PY - 2001 SN - 3-926956-43-7 SP - 141 EP - 194 PB - INFORUM-Verl. CY - Bonn AN - OPUS4-21559 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wieser, Günter A1 - Droste, Bernhard A1 - Martens, B.-R. A1 - Probst, Ulrich A1 - Schreiber, D. A1 - Völzke, Holger ED - Droste, B. ED - Kowalewsky, H. T1 - Thermal test of a cubic ductile cast iron container filled with an ion exchanger resin T2 - PATRAM 98 - 12th International conference on the packaging and transportation of radioactive materials CY - Paris, France DA - 1998-05-10 PY - 1998 VL - 1 SP - 429 EP - 435 PB - Nuclear Technology Publishing CY - Paris, France AN - OPUS4-21560 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard T1 - Wie Verpackungen unfallsicher werden - Brennelementbehälter auf dem Prüfstand PY - 1999 SN - 0949-0663 VL - 13 SP - 28 EP - 35 PB - GSF-Forschungszentrum für Umwelt und Gesundheit CY - Neuherberg AN - OPUS4-21554 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Probst, Ulrich A1 - Heller, Winfried T1 - Impact of an exploding LPG rail tank car onto a CASTOR spent fuel cask PY - 1999 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 10 IS - 4 SP - 231 EP - 240 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-21555 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Neumeyer, Tino A1 - Kowalewsky, Helmut T1 - Hoch- und Tieftemperatureignung von Elastomerdichtringen für Transport- und Lagerbehälter radioaktiver Stoffe T2 - Jahrestagung Kerntechnik `99 CY - Karlsruhe, Deutschland DA - 1999-05-18 PY - 1999 SN - 0720-9207 SP - 313 EP - 316 PB - Inforum AN - OPUS4-21598 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Kowalewsky, Helmut A1 - Droste, Bernhard A1 - Neumeyer, Tino A1 - Burnay, S.G. A1 - Ball, M. H. A1 - Morton, D.A.V. A1 - Smith, P.N. A1 - Tuson, A.T. ED - Droste, B. ED - Kowalewsky, H. T1 - Safety assessment of leaktightness criteria for radioactive materials transport packages T2 - PATRAM 98 - 12th International conference on the packaging and transportation of radioactive materials CY - Paris, France DA - 1998-05-10 PY - 1998 VL - 2 SP - 543 EP - 550 PB - Nuclear Technology Publishing CY - Paris, France AN - OPUS4-21599 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Gogolin, B. A1 - Droste, Bernhard ED - Droste, B. ED - Kowalewsky, H. T1 - Casks for transportation and storage of radioactive materials as multi mass systems - additional stresses caused by kinematic effects T2 - PATRAM 98 - 12th International conference on the packaging and transportation of radioactive materials CY - Paris, France DA - 1998-05-10 PY - 1998 VL - 3 SP - 1137 EP - 1143 PB - Nuclear Technology Publishing CY - Paris, France AN - OPUS4-21601 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard T1 - Geprüfte Sicherheit (I.) PY - 1998 SN - 0016-5808 VL - 9 SP - 33 EP - 35 PB - Storck CY - Hamburg AN - OPUS4-21603 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard T1 - Geprüfte Sicherheit (II.) PY - 1998 SN - 0016-5808 VL - 10 SP - 31 EP - 33 PB - Storck CY - Hamburg AN - OPUS4-21605 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Zencker, Uwe A1 - Weber, Mike A1 - Qiao, Linan A1 - Menzel, Martin A1 - Droste, Bernhard T1 - Beurteilungsmethoden für Transport- und Lagerbehälter mit erhöhten metallischen Reststoffanteilen - Behälterbruchsicherheitsuntersuchungen und Entwicklung eines KONRAD-Referenzprüfstandfundamentes T2 - 9. Internationales Symposium "Konditionierung radioaktiver Betriebs- und Stilllegungsabfälle" (KONTEC 2009) CY - Dresden DA - 2009-04-15 KW - Duktiles Gusseisen KW - Behälterdesign KW - Sicherheitstechnische Bewertung KW - Bruchmechanik KW - Dynamische Belastungsbedingungen KW - KONRAD KW - Referenzprüfstandfundament PY - 2009 SP - 646 EP - 652 PB - KONTEC CY - Hamburg AN - OPUS4-19396 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Müller, Karsten A1 - Quercetti, Thomas A1 - Melnik, Nauka A1 - Droste, Bernhard T1 - Impact target characterisation of BAM drop test facility N2 - BAM safety related research of containers for radioactive material focuses on advanced mechanical safety assessment methods for verification of the structural integrity and leak tightness under normal conditions of transport and hypothetical accident conditions during transport and storage. An essentially unyielding target with a rigid surface is required for impact tests performed for package approval according to IAEA regulations. In addition to specification of a target, e.g. with a combined mass more than 10 times that of the specimen for drop tests, unyielding target characteristics have been investigated with various package designs and different impact tests. The unyielding target of the BAM drop test facility, a reinforced concrete block together with an embedded and anchored mild steel plate, provides relatively large mass and stiffness with respect to the packages being tested. For monitoring reasons accelerometers and strain gauges are embedded in the concrete block of the foundation at several positions. Additionally, dynamic impact responses like vibrations and rigid body motion can be measured by seismic accelerometers. The mechanical characterisation of the target's rigidity is based on experimental results from various drop tests. Test containers with weights of 181 000 kg, 127 000 kg and 8010 kg hit the target with velocities up to 13·5 m s-1 in the horizontal and vertical drop positions. The rigidity of the impact target can be demonstrated with experimental results confirmed by analytical approaches. Some conclusions can be drawn about experimental testing as well as analytical calculations in order to compare impact effects. KW - Target KW - Unyielding KW - Impact KW - Drop test PY - 2009 U6 - https://doi.org/10.1179/174651008X344449 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 19 IS - 4 SP - 217 EP - 221 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-20136 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Droste, Bernhard A1 - Müller, Karsten A1 - Zencker, Uwe T1 - Recent experiences in mechanical design assessment of spent fuel and HLW casks by competent authority in Germany - 10093 T2 - WM2010 Conference CY - Phoenix, Arizona, USA DA - 2010-03-07 KW - Design testing KW - Transport packages KW - Numerical analysis PY - 2010 SP - 1 EP - 10 AN - OPUS4-21106 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Interaction of Package Design Development and Package Design Safety Assessment - Development and Assessment of Packages for Transport and Storage of Radioactive Materials within Decommissioning Activities - T2 - 16th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 2010 CY - London, England DA - 2010-10-03 PY - 2010 AN - OPUS4-21950 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Quercetti, Thomas A1 - Nakagami, M. A1 - Komatsuki, S. A1 - Musolff, André A1 - Müller, Karsten A1 - Droste, Bernhard A1 - Fujisawa, K. T1 - Disposal container safety assessment - drop tests with 'Yoyushindo-disposal' waste container onto concrete target N2 - This paper presents technical details of the drop test performance as well as some experimental results of tests carried out with the Japanese 'Yoyushindo-Disposal' waste container for intermediate depth disposal. The drop test program comprised three single 8 m drop tests at the specimen's corner edge orientation onto a concrete slab. The slab was connected to the unyielding IAEA target of the BAM's 200 t drop test facility. The three tested specimens had masses between 20 000 and 28 000 kg depending on their content mass. The tests were accompanied by various metrology, such as strain and deceleration measurements, optical three-dimensional deformation methods, leak tightness testing and test installation for potential particle release measurements to collect a set of data for establishing a basis for safety assessment. KW - Drop test KW - Disposal container KW - Safety PY - 2010 U6 - https://doi.org/10.1179/174650910X12681251630291 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 21 IS - 3 SP - 132 EP - 141 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-22613 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Droste, Bernhard T1 - Mechanical safety analysis for high burn-up spent fuel assemblies under accident transport conditions KW - Fuel rods KW - High burn-up KW - Accident conditions KW - Mechanical analysis KW - Failure KW - Accident transport conditions PY - 2010 U6 - https://doi.org/10.1179/174650910X12913756439836 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 21 IS - 4 SP - 212 EP - 217 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-23051 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Wille, Frank A1 - Droste, Bernhard A1 - Müller, Karsten A1 - Zencker, Uwe T1 - Mechanical design assessment approaches of actual spent fuel and HLW transport package designs KW - Package design KW - Spent fuel KW - High level waste KW - Design computations KW - Testing KW - Design testing KW - Transport packages KW - Numerical analysis KW - Mechanical analysis PY - 2010 U6 - https://doi.org/10.1179/174650910X12913738452796 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 21 IS - 4 SP - 203 EP - 207 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-23052 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Nehrig, Marko A1 - Wille, Frank A1 - Quercetti, Thomas A1 - Masslowski, Jörg-Peter A1 - Droste, Bernhard A1 - Pope, R. T1 - Historical view and experiences with the crush test for light weight packages T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Crush test KW - IAEA regulations KW - Type-B PY - 2010 SP - 1 EP - 8(?) AN - OPUS4-23303 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Ulrich, Armin A1 - Borch, Jörg-Peter T1 - Brandnew fire test facilities at 'BAM test site technical safety' N2 - Fire testing is an essential part of the hypothetical, cumulative mechanical and thermal accident test conditions that shall guarantee package safety in severe accidents. Not only for radioactive material transport packages but also for other containments of dangerous goods international standards require specific thermal load specifications. Following the guideline 'Safety in tech-nology and chemistry' BAM as a scientific and technical German federal government institute operates a 12 km² large open air test facility for experimental investigations of dangerous goods and their containments. On an area besides the well-known 200-ton drop test facility we put into operation new fire test facilities. This facility area provides two fire test stands that are utilized with liquid Propane as fuel from a central earth-covered 60 m³ LPG storage tank. From that stor-age the Propane is pumped via pipelines to the test stands where the gas is released from nozzles, and ignited by ignition burners. The fire exposed test facility areas are 12 m x 8 m. Fire test facil-ity B (with gas release nozzles below water-covered ground) is designed for fire testing of con-tainers that may burst during the test. Fire test facility A (with ring burner systems) is designed for heavy test objects up to 200 tons, e.g. for full-scale spent fuel casks. The paper will present a detailed description of the facility, insight into first test performances, and results of calorimeter fire tests, using containers of various sizes, to verify the absorbed heat fluxes, demonstrating that regulatory fire test conditions are met, and that the Propane fire can be compared with a kerosene or heating oil pool fire. T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Transport und Lagerung radioaktiver Stoffe KW - Gefahrgutrechtliche Bauartprüfung KW - Brandversuche PY - 2010 SP - 1 EP - 8 (Wednesday/Poster Session/218) AN - OPUS4-23900 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard T1 - Gestaffelte Anforderungen N2 - Klasse 7 - Design, Prüfung und Zulassung von Versandstücken zur Beförderung radioaktiver Stoffe orientieren sich am stofflichen Gefährdungspotenzial und administrativen Kontrollen durch die zuständigen Behörden. KW - Gefahrgutklasse 7 KW - Versandstücke KW - Beförderung radioaktiver Stoffe PY - 2011 SN - 0944-6117 VL - 4 SP - 46 EP - 48 PB - Vogel CY - München AN - OPUS4-23901 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Wolff, Dietmar A1 - Droste, Bernhard A1 - Völzke, Holger T1 - Requirements for transport packages after interim storage N2 - In Germany the concept of dry interim storage of spent fuel and vitrified high active waste in dual purpose metal casks is implemented (currently for periods of up to 40 years). The casks being used have an approved package design in accordance with the international transport regulations. The license for dry storage is granted on the German Atomic Energy Act with respect to the guidelines of the German Reactor Safety Commission for dry interim storage of spent fuel. Currently part of the assessment process of the cask design for transport on public routes is to evaluate the suitability of the used materials with respect to their properties and their compatibility for possible transport periods. For transport on public routes during or after long term interim storage periods, it has to be ensured that the transport and storage casks fulfill the specifications of the transport approval or other sufficient properties which satisfy the proofs for the compliance of the safety objectives at that time. This paper describes the state-of-the-art technology in Germany and points out arising prospective challenges and which related questions have to be answered in future. Present research and knowledge concerning the long term behavior of transport and storage cask components (such as gaskets and shielding components) have to be consulted as well as experiences from interim cask storage operations. Challenges in the safety assessment are therefore i.e. the behavior of aged metal and elastomeric gaskets under IAEA test conditions to ensure that the results of drop tests can be transferred to the compliance of the safety objectives at the time of transport after the interim storage period (aged package). Assessment methods for the material compatibility, the behavior of fuel assemblies and the aging behavior of shielding parts (e. g. influence of radiation) are further issues as well. T2 - 52nd INMM Annual meeting CY - Palm Desert, CA, USA DA - 17.07.2011 KW - Transport package design KW - Interim storage KW - Inspections KW - Log term behavior KW - Dual purpose casks PY - 2011 SP - 1 EP - 9 AN - OPUS4-24172 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Wille, Frank T1 - Transport of large nuclear power plant components - experiences in mechanical design assessment T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Mechanische Bewertung KW - Radioaktives Material KW - Numerische Analyse PY - 2010 SP - 1 EP - 8(?) AN - OPUS4-23383 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Neumann, Martin A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Weber, Mike A1 - Qiao, Linan A1 - Droste, Bernhard T1 - Mechanical assessment within type B packages approval - the application of static and dynamic calculation approaches T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Mechanische Bewertung KW - Radioaktives Material KW - Numerische Analyse PY - 2010 SP - 1 EP - 8(?) AN - OPUS4-23384 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rolle, Annette A1 - Neumeyer, Tino A1 - Droste, Bernhard T1 - Testing of sealed radioactive sources at BAM N2 - Requirements and test programs for sealed radioactive sources are specified in international standards for safety in transport and in use. Sealed sources which are approved as special form radioactive material according to the Transport Regulations, IAEA Safety Standards TS-R-1, must be able to withstand mechanical (9 m drop, percussion and bending) and thermal (800°C heat) tests without loss of radioactive content. The International Standard ISO 2919 provides a set of tests which classifies the sources for their safety in use. Performance tests specified in this standard are temperature (high and low), external pressure, impact, vibration and puncture tests. Each test can be applied at different levels of intensity depending on typical usage. As a criterion of pass or fail, leakage testing has to be done after each test. The poster gives an overview of BAM s comprehensive test equipment and experience in testing sealed radioactive sources. T2 - 3rd European IRPA Congress CY - Helsinki, Finland DA - 2010-06-14 KW - Radioactive KW - Sealed sources KW - Testing PY - 2010 SN - 978-952-478-551-8 IS - P18-07 SP - 2749 EP - 2754 CY - Helsinki AN - OPUS4-23420 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Droste, Bernhard A1 - Müller, Karsten A1 - Zencker, Uwe T1 - Mechanical design assessment approaches of actual spent fuel and HLW transport package designs T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Design testing KW - Transport packages KW - Numerical analysis PY - 2010 SP - 1 EP - 8(?) AN - OPUS4-23590 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Musolff, André A1 - Müller, Karsten A1 - Neumann, Martin A1 - Kadji, Arsène Brice A1 - Droste, Bernhard T1 - Results of full scale CONSTOR® V/TC prototype 9 m horizontal drop test KW - Drop testing KW - Impact limiter KW - Finite element method KW - Full scale cast PY - 2008 U6 - https://doi.org/10.1179/174651008X382951 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 19 IS - 4 SP - 228 EP - 232 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-18625 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Experiences in the safety evaluation of dry spent fuel storage casks in the Federal Republic of Germany T2 - Technical committee meeting on methods used in design of wet and dry spent fuel storage facilities CY - Otaniemi, Espoo, Finland DA - 1985-09-30 PY - 1985 SP - 1 EP - 12 PB - Internat. Atomic Energy Agency AN - OPUS4-19108 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Experiences and perspectives of package testing under hypothetical accident conditions T2 - PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials CY - Miami, Florida, USA DA - 2007-10-21 PY - 2007 SP - 1 EP - 8(?) PB - Institute of Nuclear Materials Management AN - OPUS4-19091 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Schön, W. A1 - Droste, Bernhard T1 - Brandschutzausrüstung von Flüssiggaslagertanks PY - 1987 SP - 1 EP - 16 AN - OPUS4-19142 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Droste, Bernhard ED - Mischke, J. T1 - Überblick über die behälterspezifischen Gesichtspunkte der Zwischenlagerung abgebrannter Kernbrennstoffe N2 - Es wird ausgeführt, dass die Wiederaufbereitung ausgedienter Brennelemente aus Druck- bzw. Siedewasserreaktor-Kernkraftwerken "schadlos durchführbar und wirtschaftlich vertretbar" ist und damit Vorrang hat vor einer Entsorgung ohne Wiederaufbereitung. In der Wiederaufbereitungsanlage Wackersdorf sind alle notwendigen Entsorgungsschritte von der Eingangslagerung bis zur endlagergerechten Behandlung von radioaktiven Abfällen zusammengefasst. PY - 1986 SN - 3-88314-521-1 SP - 30 EP - 38 PB - Wirtschaftsverl. CY - Bremerhaven AN - OPUS4-19116 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Probst, Ulrich A1 - Mallon, Michael A1 - Schön, W. T1 - Flüssiggastanks im Unfallfeuer PY - 1986 SN - 0936-5370 IS - 5 SP - 8 EP - 9 PB - VVA Kommunikation GmbH CY - Essen AN - OPUS4-19117 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Licensing approach used in the F. R. G. to qualify dual purpose casks T2 - Third international spent fuel storage technology symposium/workshop CY - Seattle, WA, USA DA - 1986-04-08 PY - 1986 SP - 341 EP - 344 AN - OPUS4-19122 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Röder, R. A1 - Droste, Bernhard T1 - Qualitätssichernde Maßnahmen für Brennelement-Transport- und Lagerbehälter T2 - Seminar der Bundesanstalt für Materialforschung und -prüfung CY - Berlin, Deutschland DA - 1987-06-09 PY - 1987 VL - 13 SP - 107 EP - 120 PB - Bundesanstalt für Materialforschung und -prüfung CY - Berlin AN - OPUS4-19123 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Kowalewsky, Helmut T1 - Sicherheit bei der Gefahrgutlagerung - die sicherheitstechnische Begutachtung von Transportbehältern zur trockenen Zwischenlagerung abgebrannter Brennelemente PY - 1987 SN - 1434-9728 SN - 1436-4948 SN - 0372-2457 SN - 0376-1185 VL - 28 IS - 4 SP - 167 EP - 172 PB - Springer-VDI-Verl. CY - Düsseldorf AN - OPUS4-19125 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Mallon, Michael A1 - Probst, Ulrich A1 - Schön, W. T1 - Flüssiggasanlagen - Brandschutz-Wärmedämmung kann die Sicherheit für die Umgebung verbessern PY - 1985 SN - 0017-7296 VL - 41 IS - 26 SP - 1 EP - 2(?) PB - Verl.-Gruppe Handelsblatt CY - Düsseldorf AN - OPUS4-19103 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Hübner, Heinz W. T1 - Brandversuche mit Flüssiggas-Lagertanks - Versuche der Fachgruppe 1.5 in Lehre PY - 1985 SN - 0178-5214 VL - 35 IS - 4 SP - 102 EP - 106 PB - Jamelle CY - Bochum AN - OPUS4-19104 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Technische Maßnahmen des vorbeugenden Brandschutzes oberirdischer Flüssiggas-Behälter PY - 1987 SP - 1 EP - 14 PB - Engler-Bunte-Institut CY - Karlsruhe AN - OPUS4-19128 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Müller, Karsten A1 - Musolff, André A1 - Ulrich, Armin T1 - BAM Test Site Technical Safety - The installations for mechanical and thermal Package testing - T2 - Radioactive Materials Transport 2009 (RAMTRANSPORT 09) CY - Manchester, England DA - 2009-05-12 PY - 2009 AN - OPUS4-19513 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Ballheimer, Viktor T1 - Structural Performance and Release Behavior of high-burnup nuclear Fuel under mechanical Accident Loads T2 - ORNL/BAM Meeting CY - Oak Ridge, TN, USA DA - 2008-07-21 PY - 2008 AN - OPUS4-20315 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Drop and Fire Testing of RAM Packages at BAM Test Site Technical Safety T2 - INMM 49th Annual Meeting CY - Nashville, TN, USA DA - 2008-07-15 PY - 2008 AN - OPUS4-20316 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Droste, Bernhard A1 - Wille, Frank T1 - Transport of large nuclear power plant components - experiences in mechanical design assessment T2 - Ramtransport 09 - 8th International Conference on radioactive materials transport 2009 CY - Manchester, Great Britain DA - 2009-05-12 KW - Rückbau KW - Kerntechnische Anlagen KW - Großkomponenten KW - Transport KW - Mechanik PY - 2009 IS - Session 5 / PAP 12 SP - 1 EP - 8 AN - OPUS4-20557 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Wille, Frank T1 - Zur Bauartprüfung der Behälterbauart CASTOR HAW 28M durch die BAM im verkehrsrechtlichen Zulassungsverfahren T2 - Öffentliche Sitzung des "Ausschusses für Atomanlagen und öffentliche Sicherheit" des Landkreises Lüchow-Dannenberg CY - Lüchow, Germany DA - 2009-11-05 PY - 2009 AN - OPUS4-20540 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard ED - Kussmaul, K.F. T1 - Evaluation of accidental impacts on shipping and storage casks for radioactive materials T2 - Transactions of the 12th International conference on structural mechanics in reactor technology CY - Stuttgart, Germany DA - 1993-08-15 PY - 1993 SN - 0-444-81515-5 VL - N IS - N01/2 SP - 297 EP - 302 PB - Elsevier Science Publ. CY - Amsterdam AN - OPUS4-21736 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - RPRT A1 - Probst, Ulrich A1 - Droste, Bernhard T1 - Untersuchung von Brandschutzmassnahmen - Instrumentierte Brandversuche an 4850 l-Flüssiggas-Lagertanks mit Wärmeschutz-Isolierung und zwei Sicherheitsventilen im Heizölfeuer PY - 1988 VL - Fachband 5.2 IS - Bericht 01501 SP - 1 EP - 92 CY - Berlin AN - OPUS4-21738 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Feller, H.G. T1 - Beeinflussen der Nickelabscheidung mit organischen Additiven PY - 1977 SN - 0025-4509 SN - 0341-5775 VL - 83 IS - 64 SP - 1225 EP - 1227 PB - Vogel Business Media CY - Würzburg AN - OPUS4-21706 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Feller, H.G. T1 - Untersuchung der Nickelabscheidung aus Watts'schen Bädern mit Hilfe dynamischer Impedanz- und Stromdichte-Potential-Messungen PY - 1977 SN - 0026-0797 SN - 0043-2792 VL - 31 IS - 1 SP - 1 EP - 48 PB - IGT, Informationsges. Technik CY - München AN - OPUS4-21707 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard ED - Feller, ED - Frohberg, ED - Osterwald, ED - Thomas, T1 - Abscheidungsbedingungen und Eigenschaften galvanisch abgeschiedener Metalle T2 - Fachseminar "Verhalten und Eigenschaften von metallischen Oberflächen" CY - Berlin, Deutschland PY - 1976 SP - 122 EP - 138 CY - Berlin AN - OPUS4-21708 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Dreisvogt, H. A1 - Droste, Bernhard A1 - Völzke, Holger A1 - Probst, Ulrich T1 - Dry interim spent fuel storage casks - Licensing, evaluation and operational experience T2 - International symposium on safety and engineering aspects of spent fuel storage CY - Vienna, Austria DA - 1994-10-10 PY - 1995 IS - IAEA-SM-335/35 SP - 355 EP - 368 CY - Vienna, Austria AN - OPUS4-21728 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Kowalewsky, Helmut A1 - Rödel, Roland ED - Brauns, J. ED - Eigenwillig, G.G. T1 - Szenarien für die Sicherheitsanalysen zum Transport radioaktiver Stoffe und Ableitung von Vorschriften T2 - 27. Jahrestagung "Entsorgung: Wiederverwertung-Beseitigung" CY - Wolfenbüttel, Deutschland DA - 1995-09-25 PY - 1995 SN - 1013-4506 N1 - Serientitel: Fortschritte im Strahlenschutz – Series title: Fortschritte im Strahlenschutz VL - I IS - FS-95-77-T SP - 1 EP - 13 AN - OPUS4-21729 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Droste, Bernhard ED - Slate, S. ED - Feizollahi, F. ED - Creer, J. T1 - Safety assessment of HLW and spent fuel transport and storage casks T2 - 5th International conference on radioactive waste management and environmental remediation - ICEM ´95 CY - Berlin, Germany DA - 1995-09-03 PY - 1995 SN - 0-7918-1219-7 VL - 1 SP - 243 EP - 248 AN - OPUS4-21730 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Völzke, Holger A1 - Rödel, Roland A1 - Zeisler, Peter A1 - Droste, Bernhard T1 - Considerations of the competent authority concerning the assessment of a brittle fracture safe ductile cast iron (DCI) cask design PY - 1995 SN - 0957-476X VL - 6 IS - 2/3 SP - 121 EP - 126 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21731 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Gogolin, Bernd A1 - Völzke, Holger A1 - Quercetti, Thomas A1 - Günther, Burkhard T1 - Extended drop tests of DCI casks with artificial flaws demonstrating the existing safety margins PY - 1995 SN - 0957-476X VL - 6 IS - 2/3 SP - 177 EP - 182 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21732 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Masslowski, Jörg-Peter T1 - Accident with packages for RAM on a German autobahn PY - 1995 SN - 0957-476X VL - 6 IS - 4 SP - 271 EP - 272 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21733 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Völzke, Holger A1 - Rödel, Roland A1 - Droste, Bernhard T1 - A fracture mechanics safety concept to assess the impact behavior of ductile cast iron containers for shipping and storage of radioactive materials PY - 1994 SN - 0029-5493 SN - 1872-759X VL - 150 SP - 357 EP - 366 PB - North-Holland Publ. Co. CY - Amsterdam AN - OPUS4-21734 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Zeisler, Peter A1 - Völzke, Holger A1 - Rödel, Roland T1 - Development and evaluation of containers for radioactive waste disposal PY - 1994 SN - 0957-476X VL - 5 IS - 1 SP - 27 EP - 32 PB - Nuclear Technology Publ. CY - Ashford, Kent AN - OPUS4-21735 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - Die Beurteilung der Sicherheit von Behältern für die trockene Zwischenlagerung abgebrannter Brennelemente T2 - Deutsch-Sowjetisches Seminar zum thema "Erfahrung auf dem Gebiet der Lagerung und des Transportes von abgebrannten Kernbrennstoffen; zukunftsträchtige Verfahren auf diesem Gebiet" CY - Berlin/Gorleben/Essen, Deutschland DA - 1990-12-13 PY - 1990 SP - 58 EP - 90 AN - OPUS4-21696 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - THES A1 - Droste, Bernhard T1 - Über den Einfluss organischer Badzusätze auf die elektrolytische Nickelabscheidung PY - 1981 SP - 1 EP - 146 CY - Berlin AN - OPUS4-21697 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Martens, B.-R. A1 - Droste, Bernhard A1 - Wieser, Karol E. T1 - Tests for packagings for the disposal of radioactive wastes PY - 1990 SN - 0937-4469 VL - 1 SP - 291 EP - 303 PB - BfS CY - Salzgitter AN - OPUS4-21698 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Mallon, Michael A1 - Probst, Ulrich T1 - Neuartige Brandschutzbeschichtungen für Flüssiggas-Lagertanks PY - 1990 SN - 1434-9728 SN - 1436-4948 SN - 0372-2457 SN - 0376-1185 VL - 31 IS - 5 SP - 219 EP - 224 PB - Springer-VDI-Verl. CY - Düsseldorf AN - OPUS4-21699 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard T1 - Sprühen mit Wasser hilft nur auf der gesamten Tankoberfläche PY - 1990 SN - 0017-7296 IS - 116 SP - 27 PB - Verl.-Gruppe Handelsblatt CY - Düsseldorf AN - OPUS4-21701 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - RPRT A1 - Schrödter, Wolfgang A1 - Droste, Bernhard A1 - Behrend, Eberhard A1 - Wilde, Hans T1 - Mustersicherheitsanalyse eines Flüssiggastanklagers bei einer Gross-Kfz-Tankstelle (UBA-FB 86-007) PY - 1986 IS - 22 SP - 1 EP - 104 PB - Umweltbundesamt CY - Dessau-Roßlau AN - OPUS4-21703 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Aurich, Dietmar A1 - Droste, Bernhard A1 - Helms, Rolf A1 - Ziebs, Josef T1 - Mechanical requirements for materials of accident proof packagings of radioactive materials T2 - PATRAM ´83 - 7th International Symposium on packaging and transportation of radioactive materials CY - New Orleans, Lousiana, USA DA - 1983-05-15 PY - 1983 VL - I IS - Paper 087 SP - 110 EP - 115 AN - OPUS4-21704 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Feller, H.G. ED - Frankenthal, R.P. ED - Kruger, J. T1 - The passivity of nickel and nickel alloys T2 - 4th International Symposium on Passivity - Passivity of Metals CY - Princeton, NJ, USA PY - 1978 SP - 802 EP - 826 CY - Princeton, New Jersey, USA AN - OPUS4-21705 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Neumann, Martin A1 - Herter, Jürgen A1 - Droste, Bernhard A1 - Hartwig, S. T1 - Compressive behaviour of axially loaded spruce wood under large deformations at different strain rates N2 - Impact limiting components of packages for the transport of radioactivematerials are often designed as wood filled steel constructions. Wood absorbs major part of the impact energy in order to minimise the impact load acting upon the containment. Dynamic impact experiments with wood filled impact limiters showed different crushing mechanisms for axially loaded wood depending on their lateral constraint. Tests on spruce wood samples (Picea abies) were performed in order to clarify the influence of strain rate from static to 30 s-1 on a) compression strength, b) stress at a global strain level of 50%, and c) energy absorption capacity at 50% deformation, including statistical evaluation of the results. Results were as follows: strain rate increase led to significantly higher compression strength, stress and strain energy at a strain level of 50%. Lateral strain restriction had no effect on compression strength; it had a significant effect on stress and strain energy at strain level of 50%. Therefore, the definition of a general yield curve for wood under large deformations is not possible, the yield curve has to be chosen taking into account lateral constraints. KW - Compression KW - Wood KW - Spruce KW - Picea abies KW - Impact PY - 2011 U6 - https://doi.org/10.1007/s00107-010-0442-x SN - 0018-3768 VL - 69 IS - 3 SP - 345 EP - 357 PB - Springer CY - Berlin ; Heidelberg AN - OPUS4-22980 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Ballheimer, Viktor A1 - Wille, Frank A1 - Droste, Bernhard T1 - Mechanical safety analysis for high burn-up spent fuel assemblies under accident transport conditions T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Accident transport conditions KW - Fuel rods KW - High burn-up KW - Failure PY - 2010 SP - 1 EP - 8(?) AN - OPUS4-23760 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin A1 - Wille, Frank A1 - Droste, Bernhard T1 - Introduction of BAM safety assessment experience feedback list N2 - BAM as competent authority regarding assessment of mechanical and thermal design, activity release and quality assurance aspects of SNF and HLW transport packages developed a thesaurus of experience feedback topics from recent approval procedures. The list is structured according to the European PDSR guide. It involves issues, which from BAM point of view, needed clarification during last package design assessment procedures. The list contains issues from operation (e.g. deactivation of handling lugs not intended for package handling), maintenance (e.g. leak tightness of impact limiting devices) to technical assessment (e.g. formation of hydrogen by radiolysis and its impact on pressure and ignitability, consideration of ageing mechanisms, thermo-mechanical assessment, impact of gaps between content and flask, spent fuel behaviour) as well as to general and specific safety analysis report requirements (e.g. report structure and required data). T2 - PATRAM 2016 CY - Kobe, Japan DA - 18.09.2016 KW - Experience feedback list KW - Radioactive material KW - Transport PY - 2016 UR - http://www.patram2016.org/ SP - Paper 4002, 1 AN - OPUS4-37850 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Wille, Frank A1 - Droste, Bernhard T1 - Gap analysis by periodical reviews of transport package design safety reports of German SNF/HLW dual purpose casks N2 - Storage of spent nuclear fuel and high-level waste in dual purpose casks (DPC) is related with the challenge of maintaining safety for transportation over several decades of storage. Beside consideration of aging mechanisms by appropriate design, material selection and operational controls to assure technical reliability by aging management measures, an essential issue is the continuous control and update of the DPC safety case. Not only the technical objects are subject of aging but also the safety demonstration basis is subject of “aging” due to possible changes of regulations, standards and scientific/technical knowledge. The basic document, defining the transport safety conditions, is the package design safety report (PDSR) for the transport version of the DPC. To ensure a safe transport in future to a destination which is not known yet (because of not yet existing repository sites) periodical reviews of the PDSR, in connection with periodic renewals of package design approval certificates, have to be carried out. The main reviewing tool is a gap analysis. A gap analysis for a PDSR is the assessment of the state of technical knowledge, standards and regulations regarding safety functions of structures, systems and components. T2 - 18th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM2016 CY - Kobe, Japan DA - 18.09.2016 KW - Radioactive material KW - Gap analysis KW - Periodical review KW - Approved packages PY - 2016 SP - Paper 5004, 1 EP - 9 AN - OPUS4-37641 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Linnemann, Konrad A1 - Ballheimer, Viktor A1 - Müller, Lars A1 - Rolle, Annette A1 - Wille, Frank A1 - Droste, Bernhard T1 - Aspects of spent fuel behavior assessment for transport packages N2 - Transport packages for spent nuclear fuel have to be assessed with respect to specific transport conditions which are defined in the safety regulations of the International Atomic Energy Agency. In general, gastight fuel rods constitute the first barrier of the containment system. The physical state of the spent fuel and the fuel rod cladding as well as the geometric configuration of the fuel assemblies are important inputs for the evaluation of the package safety under transport conditions. The objective of this paper is to discuss the methodologies accepted by BAM for the authority assessment of spent fuel behavior within the package design approval procedure of German package designs. In particular, cracks or failures in the fuel rod cladding can occur under regulatory transport conditions. These defects can cause the release of gas, volatiles, fuel particles or fragments into the package cavity and have to be considered properly in the safety analysis. Another issue is the transport of defective fuel rods. One concept is to use special canisters which can be handled like fuel assemblies. This concept requires additional assessment concerning drying, sealing and the mechanical and thermal design of such canisters. The package as a mechanical system is characterized by a complex set of interactions, e.g. between the fuel rods within the assembly as well as between the fuel assemblies, the basket, and the cask containment. This complexity together with the limited knowledge about the material properties and the variation of the fuel assemblies regarding cladding material, burn-up and the operation history makes an exact mechanical analysis of the fuel rods nearly impossible. The simplified approaches to consider conservatively spent fuel behavior currently accepted by BAM are presented here. T2 - International Conference on Management of Spent Fuel from Nuclear Power Reactors - An Integrated Approach to the Back-End of the Fuel Cycle CY - Wien, Austria DA - 15.06.2015 KW - Transport packages KW - Spent fuel assessment PY - 2015 SP - 1 AN - OPUS4-38102 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Musolff, André A1 - Quercetti, Thomas A1 - Müller, Karsten A1 - Droste, Bernhard A1 - Gründer, Klaus-Peter T1 - Experimental testing of impact limiters for RAM packages under drop test conditions N2 - In context with new cask designs and their approval procedure, the experimental testing of impact limiters under drop test conditions becomes more and more important in order to assess the damage mechanics behaviour and safety margins for validation reasons. In recent years, various designs of impact limiters have been tested by the Federal Institute for Materials Research and Testing within specific component testing and particularly with regard to type B package design approval procedures. The paper focuses on the experimental realisation of impact limiter tests and presents implemented measurement techniques to determine the amount of deformation and to explain the impact behaviour by means of photogrammetric metrology and three-dimensional fringe projection method, high speed motion analysis and adjusted deceleration measurements. KW - Experimental KW - Drop test KW - Impact limiter KW - Close range photogrammetry PY - 2014 U6 - https://doi.org/10.1179/1746510915Y.0000000003 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 25 IS - 3-4 SP - 133 EP - 138 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-33776 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rolle, Annette A1 - Droste, Bernhard A1 - Schubert, Sven A1 - Probst, Ulrich A1 - Wille, Frank T1 - Verification of activity release compliance with regulatory limits within spent fuel transport casks T2 - PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials CY - London, UK DA - 2010-10-03 KW - Radioactive material KW - Safety assessment KW - Leakage mechanism KW - Leakage rate KW - Sealing behavior PY - 2010 SP - 1 EP - 8(?) AN - OPUS4-32193 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Komann, Steffen A1 - Wille, Frank A1 - Rolle, Annette A1 - Probst, Ulrich A1 - Schubert, Sven T1 - Consideration of aging mechanism influence on transport safety of dual purpose casks for spent nuclear fuel of HLW N2 - 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'. KW - Transport KW - Storage KW - Spent fuel KW - High-level waste KW - Aging KW - Metal seals KW - Transport and storage casks KW - Spent nuclear fuel KW - Aging mechanisms KW - Corrosion KW - Safety assessment PY - 2014 U6 - https://doi.org/10.1179/1746510914Y.0000000070 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 25 IS - 3-4 SP - 105 EP - 112 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-33428 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Neumann, Martin A1 - Wille, Frank A1 - Droste, Bernhard T1 - Experience feedback from BAM safety assessment of transport packages N2 - BAM as competent authority regarding assessment of mechanical and thermal design, activity release and quality assurance measures of Type-B(U) transport packages developed a thesaurus of experience feedback topics from recent assessment procedures. The list is structured according to the European PDSR guide. It involves issues, which from BAM's point of view, needed clarification during the last package design assessment procedures. The list contains issues from Operation (e.g. deactivation of handling lugs not intended for package handling), maintenance (e.g. leak tightness of impact limiting devices) to technical assessment (e.g. formation of hydrogen by radiolysis and its impact on pressure and ignitability, consideration of ageing mechanisms, thermo-mechanical assessment, impact of gaps between content and flask) as well as to general and specific safety analysis report requirements (e.g. report structure and required data). T2 - RAMTRANS 2015 - 10th International conference on radioactive materials transport and storage CY - Oxford, UK DA - 19.05.2015 KW - Transport KW - RAM KW - Radioactive material KW - Cask KW - Flask KW - Nuclear fuel PY - 2015 SP - 1 EP - 7 AN - OPUS4-33420 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CHAP A1 - Droste, Bernhard ED - Sorenson, K.B. T1 - Packaging, transport, and storage of high-, intermediate-, and low-level radioactive wastes N2 - Radioactive wastes are generated by research and medicine (e.g., the use of radioisotopes), industrial use of radioisotopes (e.g., for nondestructive materials testing), different activities related to nuclear power plant (NPP) operations (e.g., mining of uranium and thorium ores, manufacturing of fuel assemblies, operational waste generation during NPP Operation), reprocessing of spent nuclear fuel, and dismantling of nuclear installations. KW - Packaging KW - Transport KW - Storage KW - Radioactive waste KW - Safety assessment PY - 2015 SN - 978-1-78242-309-6 SN - 978-1-78242-322-5 N1 - Serientitel: Woodhead publishing series in energy – Series title: Woodhead publishing series in energy IS - 78 SP - Chapter 15, 231 EP - 270 PB - Woodhead Publ. AN - OPUS4-33991 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Wille, Frank A1 - Ballheimer, Viktor A1 - Rolle, Annette A1 - Droste, Bernhard T1 - Mechanical behaviour of high burn-up SNF under normal and accident transport conditions - present approaches and perspectives - T2 - PSAM 11 ESREL 2012 - 11th International probabilistic safety assessment and management conference & The annual european safety and reliability conference CY - Helsinki, Finland DA - 2012-06-25 KW - Spent fuel KW - High burn-up KW - Transport conditions KW - Mechanical analysis PY - 2012 SP - 1 EP - 9(?) AN - OPUS4-33850 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Wille, Frank A1 - Komann, Steffen T1 - Aging Mechanisms Influence on Transport Safety of Dual Purpose Casks for Spent Nuclear Fuel T2 - International Conference on the Management of Spent Fuel from Nuclear Power Rectors: An Integrated Approach to the Back-End of the Fuel Cycle (CN-226) CY - IAEA, Vienna, Austria DA - 2015-05-19 PY - 2015 AN - OPUS4-33569 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Wille, Frank T1 - Safety Aspects of Dual and Multi-Purpose Casks for Radioactive Materials T2 - RAMTRANS 2015, 10th International Conference on Radioactive Materials Transport and Storage CY - Oxford, UK DA - 2015-05-19 PY - 2015 AN - OPUS4-33570 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard A1 - Komann, Steffen A1 - Wille, Frank A1 - Rolle, Annette A1 - Probst, Ulrich A1 - Schubert, Sven T1 - Considerations of aging mechanisms influence on transport safety and reliability of dual purpose casks for spent nuclear fuel or HLW N2 - 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'. T2 - PSAM 12 - Probabilistic safety assessment and management CY - Honolulu, Hawaii, USA DA - 22.06.2014 KW - Transport and storage casks for spent nuclear fuel or high level waste KW - Aging mechanisms KW - Corrosion KW - Safety assessment KW - Metal seals KW - Closure system KW - Spent fuel/high-level waste KW - Dual purpose casks KW - Metal seals reliability KW - Cesium corrosion PY - 2014 UR - http://psam12.org/proceedings/paper/paper_180_1.pdf SP - 1 EP - 10 AN - OPUS4-32518 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - A survey on the history of relations between BAM and Sandia NL T2 - BAM/SNL Collaborative Workshop CY - Albuquerque, NM, USA DA - 2014-10-06 PY - 2014 AN - OPUS4-32788 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Droste, Bernhard T1 - SNF/HLW dual purpose cask issues T2 - BAM/SNL Collaborative Workshop CY - Albuquerque, NM, USA DA - 2014-10-06 PY - 2014 AN - OPUS4-32789 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Wille, Frank A1 - Wolff, Dietmar A1 - Droste, Bernhard A1 - Völzke, Holger A1 - Baden, M. T1 - German approach and feedback on experience of transportability of SNF packages after interim storage N2 - In Germany, the concept of dry interim storage of spent fuel in dual purpose metal casks is implemented, currently for periods of up to 40 years. The casks being used have an approved package design in accordance with the international transport regulations. The license for dry storage is granted on the German Atomic Energy Act with respect to the recently revised 'Guidelines for dry interim storage of irradiated fuel assemblies and heat-generating radioactive waste in casks' by the German Waste management Commission. For transport on public routes between or after long term interim storage periods, it has to be ensured that the transport and storage casks fulfil the specifications of the transport approval or other sufficient properties, which satisfy the proofs for the compliance of the safety objectives at that time. In recent years, the validation period of transport approval certificates for manufactured, loaded and stored packages were discussed among authorities and applicants. A case dependent system of 3, 5 and 10 years was established. There are consequences for the safety cases in the Package Design Safety Report, including evaluation of long term behaviour of components and specific operating procedures of the package. The present research and knowledge concerning the long term behaviour of transport and storage cask components have to be consulted as well as experiences from interim cask storage operations. Challenges in the safety assessment are e.g. the behaviour of aged metal and elastomeric gaskets under IAEA test conditions to ensure that the results of drop tests can be transferred to the compliance of the safety objectives at the time of transport after the interim storage period. Assessment methods for the material compatibility, the behaviour of fuel assemblies and the aging behaviour of shielding parts are issues as well. This paper describes the state of the art technology in Germany, explains recent experience on transport preparation after interim storage and points out arising prospective challenges. KW - Radioactive material storage KW - Dry storage KW - Interim storage KW - Cask design KW - Radioactive material transport KW - Regulation KW - Operating procedures KW - Package KW - Safety KW - Storage KW - Transport KW - Lagerung KW - Spent fuel PY - 2014 U6 - https://doi.org/10.1179/1746510914Y.0000000064 SN - 1746-5095 SN - 1746-5109 SN - 0957-476X VL - 25 IS - 2 SP - 55 EP - 59 PB - Ramtrans Publ. CY - Ashford AN - OPUS4-33834 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Komann, Steffen A1 - Wille, Frank A1 - Droste, Bernhard T1 - Transport von Großkomponenten aus der Stilllegung kerntechnischer Anlagen in Deutschland-Erfahrungen bei der mechanischen Integritätsbewertung N2 - Im Zuge des Rückbaus kerntechnischer Anlagen in Deutschland müssen u. a. Großkomponenten (Dampferzeuger, Reaktordruckbehälter) über öffentliche Verkehrswege in Zwischenlager transportiert werden, in denen sie zerlegt bzw. zwischengelagert werden. Für diese Versandstücke ist eine mechanische Integritätsbewertung, nach den Vorschriften der Internationalen Atomenergie-Organisation (IAEO), notwendig, die in der Regel unter dem Einsatz einer komplexen numerischen Berechnung erfolgt. ---------------------------------------------------------- In the course of decommissioning of power plants in Germany large nuclear components (steam generator, reactor pressure vessel) must be transported over public traffic routes to interim storage facilities, where they are dismantled or stored temporarily. For these packages a safety evaluation considering the International Atomic Energy Agency (IAEA) transport regulations is necessary, preferably by a complex numerical analysis. KW - Radioaktive Stoffe KW - Transport KW - Mechanik KW - Numerische Analyse PY - 2016 SN - 0005-6650 VL - 91 IS - 5 SP - 188 EP - 192 PB - Springer VDI Verlag CY - Düsseldorf AN - OPUS4-36016 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Droste, Bernhard A1 - Blümel, Peter ED - Busch, H. J. T1 - Die Verträglichkeit von Füllgut und Wandungswerkstoff - Eine wesentliche Voraussetzung der Genehmigung von Lager- und Transportbehältern für gefährliche Stoffe - Teil 1 PY - 1981 SP - B 58 a EP - B 58 l PB - Bundesanzeiger Verl.ges. CY - Köln AN - OPUS4-36017 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - GEN A1 - Droste, Bernhard A1 - Blümel, Peter ED - Busch, H. J. T1 - Die Verträglichkeit von Füllgut und Wandungswerkstoff - Eine wesentliche Voraussetzung der Genehmigung von Lager- und Transportbehältern für gefährliche Stoffe - Teil 2 PY - 1981 SP - B 58 p EP - B 58 w PB - Bundesanzeiger Verl.ges. CY - Köln AN - OPUS4-36018 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - RPRT A1 - Droste, Bernhard A1 - Schulz, Ina T1 - Gewässerschutz bei der Beförderung wassergefährdender Stoffe auf Binnenschiffen T1 - Water protection in transportation of dangerous goods by vessels on inland waterways N2 - Die Studie gibt einen Überblick über den Umfang und die Struktur der Gefahrgutbeförderung auf Binnenschiffen und stellt die maßgeblichen sicherheitstechnischen Vorschriften dar. Aus dem Unfallgeschehen läßt sich entnehmen, daß in West-Deutschland jährlich ca. 1200 Binnenschiffsunfälle mit größenordnungsmäßig insgesamt 100 bis 300 m³ Ladungsaustritt verbunden sind, wozu fast ausschließlich Mineralölprodukte gehören, und zumeist ein oder zwei Unfälle den größten Beitrag liefern. Während nach Unfällen häufig mit Erfolg Ölsperren zur Begrenzung von Gewässerverunreinigungen eingesetzt werden können, führen ungeklärte Entsorgungsprobleme zu wesentlich kritischer einzuschätzenden, verdeckten Verunreinigungen der Gewässer. Insbesondere die Entsorgung von Ladungsresten bedarf in technischer, administrativer und wirtschaftlicher Hinsicht einer zufriedenstellenden Klärung wie sie z. B. bei der Bilgenwasserentsorgung existiert. N2 - The study gives a survey on the structure and amount of dangerous goods carriage on inland waterway vessels. The technical safety requirements are presented. The accident statistics of West-Germany show that appr. 1200 incidents per year lead to loss of loading of a total amount of 100 to 300 m³. The lost goods are nearly in every case inflammable liquids, and usually only one or two incidents p. a. cause major losses. After accidents often mobile oil barriers can stop water pollution. Unsolved problems in vessel decommissioning serve much more critical situations with respect to water pollution. Primarily the decommissioning of remaining parts of the hazardous cargo inside vessels needs to be clarified with respect to technical, administrative and commercial reasons. KW - Gefahrgutbeförderung KW - Binnenschiffe KW - Gewässerschutz KW - Tankschiffsunfälle KW - Entsorgungsprobleme von Binnenschiffen PY - 1993 VL - Forschungsbericht 102 03 439 SP - 1 EP - 93 PB - Umweltbundesamt CY - Berlin AN - OPUS4-51134 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Komann, Steffen A1 - Wille, Frank A1 - Droste, Bernhard T1 - Gap analysis examples from periodical reviews of transport package design safety reports of SNF/HLW dual purpose casks N2 - Storage of spent nuclear fuel and high-level waste in dual purpose casks (DPC) is related with the challenge of maintaining safety for transportation over several decades of storage. Beside consideration of aging mechanisms by appropriate design, material selection and operational controls to assure technical reliability by aging management measures, an essential issue is the continuous control and update of the DPC safety case. Not only the technical objects are subject of aging but also the safety demonstration basis is subject of "aging" due to possible changes of regulations, standards and scientific/technical knowledge. The basic document, defining the transport safety conditions, is the package design safety report (PDSR) for the transport version of the DPC. To ensure a safe transport in future to a destination which is not known yet (because of not yet existing repository sites) periodical reviews of the PDSR, in connection with periodic renewals of package design approval certificates, have to be carried out. The main reviewing tool is a gap analysis. A gap analysis for a PDSR is the assessment of the state of technical knowledge, standards and regulations regarding safety functions of structures, systems and components. T2 - PSAM 12 - Probabilistic safety assessment and management CY - Honolulu, Hawaii, USA DA - 22.06.2014 KW - Dual Purpose Casks KW - Aging KW - Transportation KW - Periodical Review PY - 2014 UR - http://psam12.org/proceedings/paper/paper_259_1.pdf SP - Paper 259, 1 EP - 9 AN - OPUS4-32574 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Scheidemann, Robert A1 - Qiao, Linan A1 - Müller, Karsten A1 - Droste, Bernhard T1 - Determination of material parameters of damping concrete under dynamic loading N2 - The safety and integrity of casks for radioactive waste in accidental scenarios is analysed by BAM Federal institute tor Materials Research and Testing. An accidental scenario in German interim storage facilities is the drop from a crane during the handling operation. To reduce the mechanical loads to the cask a shock absorbing footing with high energy absorption capability is used in these areas. In order to analyse and evaluate such impact scenarios of casks, numerical simulations are performed. For a comprehensive simulation of an accidental scenario the behaviour of the damping concrete footing has to be taken into account as well and therefor a material model is needed. Material parameters under different loading conditions are the basis for a numerical model. For that reason a government funded research project (Kasparek, 2012) was conducted to characterise damping concrete under quasi-static as well as highly dynamic impact loading conditions. The performed tests include compression tests with and without lateral constraint small-scale and midscale penetration tests with different indenters, and finally a full-scale drop test onto a damping concrete footing. T2 - RAMTRANS 2015 - 10th International conference on radioactive materials transport and storage CY - Oxford, UK DA - 19.05.2015 KW - Drop test KW - Damping concrete KW - Material characterisation PY - 2015 SP - 1 EP - 9 AN - OPUS4-33492 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - JOUR A1 - Droste, Bernhard A1 - Hübner, Heinz W. T1 - Brandversuche mit Flüssiggas-Lagertanks - Versuche der Fachgruppe 1.5 in Lehre PY - 1985 SN - 0178-5214 IS - 4 SP - 102 EP - 106 PB - Jamelle CY - Bochum AN - OPUS4-33930 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Müller, Lars A1 - Komann, Steffen A1 - Wille, Frank A1 - Droste, Bernhard T1 - Sicherheitstechnische Begutachtung der strukturmechanischen Auslegung von Castor-Behältern N2 - Die Sicherheitsanforderungen, die an Behälter für den Transport radioaktiver Stoffe auf öffentlichen Verkehrswegen gestellt werden, orientieren sich an dem Gefährdungspotenzial des radioaktiven Inhalts. So müssen für den Transport abgebrannter Brennelemente oder hochradioaktiver Abfalle aus nuklearen Anlagen Behälter eingesetzt werden, die auch schweren Unfällen standhalten. Zu ihnen gehören z. B. die CASTOR®-Behälter (Cask for Storage and Transport of Radioactive Material). T2 - BTU Stahlbau-Symposium 2014 CY - Cottbus, Germany DA - 23.05.2014 PY - 2014 SN - 1611-5023 N1 - Serientitel: Schriftenreihe Stahlbau – Series title: Schriftenreihe Stahlbau IS - 8 SP - 33 EP - 40 AN - OPUS4-31148 LA - deu AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CHAP A1 - Droste, Bernhard A1 - Wolff, Dietmar A1 - Bevilacqua, A. A1 - Reiche, I. A1 - Harvey, J. A1 - Hirose, M. A1 - Kumano, Y. A1 - McConnell, P. A1 - Saegusa, T. A1 - Einziger, R. ED - González-Espartero, A. T1 - Methodology for a Safety Case of a Dual Purpose Cask for Storage and Transport of Spent Fuel N2 - Spent nuclear fuel which is generated in the operation of nuclear reactors needs to be safely managed following its removal from the reactor core. On-site power reactor storage pools were designed on the assumption that after a short period of time spent nuclear fuel would be removed for reprocessing and disposal or further storage elsewhere. The amount of highly radioactive spent fuel that needs to be stored over longer periods of time is growing and additional storage capacity is required. One of the widely used options for additional storage capacity is the use of casks for dry storage of spent fuel. Among various existing dry storage concepts, several Member States are utilizing a concept of dual purpose casks (DPCs). This publication provides practical advice on the structure and contents of a DPC integrated safety case with reference to existing IAEA requirements relevant to the licensing and use of transport and storage casks for spent fuel. KW - Dual Purpose Cask KW - Spent Fuel KW - Storage KW - Transport PY - 2020 UR - https://www.iaea.org/publications/10966/methodology-for-a-safety-case-of-a-dual-purpose-cask-for-storage-and-transport-of-spent-fuel SN - 978-92-0-131620-2 SN - 1011–4289 SP - 1 EP - 109 PB - IAEA Publishing Section CY - Vienna, Austria AN - OPUS4-51962 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER - TY - CONF A1 - Rolle, Annette A1 - Neumeyer, Tino A1 - Droste, Bernhard T1 - Design Approval of Special Form Radioactive Material- Important Aspects N2 - The design of a special form radioactive material has to resist a severe transport accident without undue loss or dispersal of radioactive material. Safety assessment by authorities competent for design approval has to include besides the required test program (impact, percussion, bending and heat test) also the evaluation of the quality management system for design, manufacture, testing, documentation, use, maintenance and inspection. These quality assurance measures have to assure that every specimen of the approved design is produced in the same verified quality and every specimen must be able to survive the severe mechanical and thermal tests without undue loss or dispersal of radioactive material at any time of its working life. All important aspects in the design approval procedure by BAM as the competent authority for approvals of special form radioactive material in Germany are summarized in a guideline published in 2014. This paper will give additional explanations to some aspects in safety assessment, e.g.: the applicability of leak test methods and the need to consider ageing aspects. T2 - PATRAM 2016 CY - Kobe, Japan DA - 18.09.2016 KW - Transport KW - Radioactive material KW - Safety PY - 2016 SP - Paper 4004-22 AN - OPUS4-39912 LA - eng AD - Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin, Germany ER -