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    <title language="deu">Anforderungen an Behälter für die Endlagerung hochradioaktiver Abfälle in Steinsalz, Tonstein und Kristallingestein</title>
    <abstract language="deu">Bei der Auswahl eines Standortes für ein Endlager für hochradioaktive Abfälle (Wärme entwickelnde radioaktive Abfälle und ausgediente Brennelemente) in Deutschland werden auf Grundlage des Standortauswahlgesetzes von 2017 die drei potenziellen Wirtsgesteine Steinsalz, Tonstein und Kristallingestein in Betracht gezogen. Die Auswahl eines konkreten Endlagerstandortes steht dabei in engem Zusammenhang mit den für die jeweiligen Wirtsgesteine geeignet erscheinender Endlagersystemen. Zentraler Bestandteil dieser Endlagersysteme sind die Endlagerbehälter, deren Gestaltung und Auslegung maßgeblich die Randbedingungen für die Transport- und Einlagerungstechnik vorgibt und zudem die Nachweise zur Betriebs- und Langzeitsicherheit entscheidend prägt. Daher ist es für die Behälterentwicklung erforderlich, die an Endlagerbehälter zu stellenden Anforderungen systematisch herzuleiten. Auf dieser Grundlage können anforderungsgerechte Endlagerbehälter zielgerichtet für die jeweils zu untersuchenden Endlagerstandorte in unterschiedlichen Wirtsgesteinen entwickelt werden.&#13;
Dieser Beitrag fasst die wesentlichen Ergebnisse des von BAM und BGE TECHNOLOGY GmbH im Zeitraum 2017 bis 2020 bearbeiteten und vom Bundesministerium für Wirtschaft und Energie (BMWi) geförderten Forschungsvorhabens KoBrA zusammen, die in einem Abschlussbericht und vier zugehörigen Teilberichten umfassend dokumentiert sind.</abstract>
    <parentTitle language="deu">Proceedings Tage der Standortauswahl 2021</parentTitle>
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    <author>S. Prignitz</author>
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      <value>Endlager</value>
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      <value>hochradioaktive Abfälle</value>
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    <title language="deu">Nationaler und Internationaler Stand zu bereits existierenden Anforderungen und Konzepten für Endlagerbehälter und Zusammenstellung sicherheitsrelevanter Behältereigenschaften; Bericht zum Arbeitspaket 1 des FuE-Verbundvorhabens KoBrA</title>
    <abstract language="deu">Im hier vorliegenden Bericht wurde im Rahmen einer umfassenden Literaturrecherche der nationale und internationale Stand von Wissenschaft und Technik hinsichtlich Behälterkonzepten und Behälteranforderungen erfasst. Dabei wurde eine umfangreiche Dokumentensammlung zusammengestellt und sortiert, die als Quellenbasis für alle weiteren Arbeiten zur Verfügung steht. Die Auswertung der gesammelten Informationen resultiert in einem Überblick über internationale Behälterentwicklungen sowie einer detaillierten Übersicht über die Behälterkonzepte und die ihnen zugrundeliegenden Anforderungskataloge aus elf fortgeschrittenen Endlagerprogrammen.</abstract>
    <identifier type="doi">10.2314/KXP:1759195804</identifier>
    <note>Auftraggeber: Bundesministerium für Wirtschaft und Energie (BMWi), Förderkennzeichen: 02E11537.</note>
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    <title language="deu">Erarbeitung von Vorschlägen für mögliche Behälterkonzepte in den drei potenziellen Wirtsgesteinen Steinsalz, Tonstein und Kristallingestein; Bericht zum Arbeitspaket 4 des FuE Verbundvorhabens KoBrA</title>
    <abstract language="deu">Dieser Bericht untersucht die im ersten Arbeitspaket ermittelten vorhandenen bzw. entwickelten Behälterkonzepte dahingehend, inwieweit die jeweiligen Behälterfunktionen unter den im zweiten und dritten Arbeitspaket ermittelten Randbedingungen und Einwirkungen den im dritten Arbeitspaket ermittelten Anforderungen an endlagerfähige Behälter in einem deutschen Endlager genügen. Zum anderen sollen, basierend auf den im zweiten Arbeitspaket ermittelten Randbedingungen und den im dritten Arbeitspaket hergeleiteten und zusammengestellten Anforderungen an die Endlagerbehälter, Vorschläge für mögliche generische Endlagerbehälter in den drei potenziellen Wirtsgesteinen Steinsalz, Tonstein und Kristallingestein erarbeitet werden. Die im ersten Arbeitspaket recherchierten Behälterkonzepte, deren Entwicklungslinien und zugrundeliegende Behälteranforderungen bilden hier den Ausgangspunkt für weitergehende Überlegungen hinsichtlich ihrer potenziellen Eignung für ein zukünftiges deutsches Endlager und zur Skizzierung generischer Konzepte für zukünftige Endlagerbehälter.</abstract>
    <identifier type="doi">10.2314/KXP:1759194123</identifier>
    <note>Auftraggeber: Bundesministerium für Wirtschaft und Energie (BMWi), Förderkennzeichen: 02E11537.</note>
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    <title language="deu">Herleitung und Zusammenstellung der Anforderungen an Endlagerbehälter für ein HAW-Endlager in den drei  potenziellen Wirtsgesteinen Steinsalz, Tonstein und  Kristallingestein; Bericht zum Arbeitspaket 3 des FuE Verbundvorhabens KoBrA</title>
    <abstract language="deu">Der Bericht zum Arbeitspaket 3 baut auf den Ergebnissen der internationalen Recherche (AP1) sowie der Zusammenstellung der Randbedingungen und Beanspruchungsgrößen für die Endlagerbehälter (AP2) auf. Die Anforderungen an die Behälter – regulatorische, betriebliche sowie solche aus der Standortgeologie und den Einwirkungen und Prozessen, denen die Behälter ausgesetzt sind – werden hergeleitet und systematisch dargestellt. &#13;
Die für das Endlagersystem zu betrachtenden Nutzungsphasen werden aus den regulatorischen Anforderungen hergeleitet und charakterisiert. Die Einwirkungen auf die Behälter in den drei potenziellen Wirtsgesteinen sowie die sich für die Erfüllung der Sicherheitsfunktionen des Behälters als Teil des Endlagersystems ergebenden Behälterfunktionen werden ebenfalls wirtsgesteins- und zeitphasenabhängig betrachtet. Schließlich werden aus den Einwirkungen auf die Behälter und den Anforderungen an die Behälterfunktionen auch quantifizierbare Behälterfunktionen für alle drei potenziellen Wirtsgesteine abgeleitet.</abstract>
    <identifier type="url">https://www.bge-technology.de/fileadmin/user_upload/MEDIATHEK/f_e_berichte/KoBrA/2020-KoBrA_Bericht_AP3.pdf</identifier>
    <note>Auftraggeber: Bundesministerium für Wirtschaft und Energie (BMWi), Förderkennzeichen: 02E11527 und 02E11537.</note>
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    <title language="deu">Abschlussbericht zum FuE-Verbundvorhaben KoBrA: Anforderungen und Konzepte für Behälter zur Endlagerung von Wärme entwickelnden radioaktiven Abfällen und ausgedienten Brennelementen in Steinsalz, Tonstein und Kristallingestein</title>
    <abstract language="deu">Im Forschungsvorhaben KoBrA werden Anforderungen an Endlagerbehälter für hochradioaktive Abfälle erstmals systematisch und unter Berücksichtigung des internationalen Standes von Wissenschaft und Technik hergeleitet. Parallel werden die behälterrelevanten Randbedingungen und Beanspruchungsgrößen für Endlagerbehälter in den drei potenziellen Wirtsgesteinen Steinsalz, Tonstein und Kristallingestein ermittelt. Darauf aufbauend werden die zur Erfüllung der Anforderungen unter den gegebenen Einwirkungen und Beanspruchungen notwendigen Behälterfunktionen bestimmt und erste Konzeptideen für zukünftige Endlagerbehälter diskutiert bzw. entwickelt.</abstract>
    <identifier type="doi">10.2314/KXP:1750909669</identifier>
    <note>Auftraggeber: Bundesministerium für Wirtschaft und Energie (BMWi), Förderkennzeichen: 02E11527 und 02E11537.</note>
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    <title language="eng">Latest developments in Germany concerning extended interim storage</title>
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    <enrichment key="eventPlace">Jeju, Korea</enrichment>
    <enrichment key="eventStart">15.09.2017</enrichment>
    <enrichment key="eventEnd">15.09.2017</enrichment>
    <enrichment key="InvitedTalks">0</enrichment>
    <author>Holger Völzke</author>
    <author>Teresa Orellana Pérez</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Nuclear waste management</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Long term storage</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Spent fuel</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
  </doc>
  <doc>
    <id>43795</id>
    <completedYear/>
    <publishedYear>2017</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst/>
    <pageLast/>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>lecture</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Perspectives on demonstrating fuel cladding integrity for extended dry interim storage in Germany</title>
    <abstract language="eng">The presentation highlights recent investigations by BAM on how to address fuel cladding integrity under long term dry storage conditions. National and European initiatives and research programs related to radioactive waste management and disposal are explained.</abstract>
    <enrichment key="eventName">EPRI Extended Storage Collaboration Program (ESCP) Winter Meeting 2017</enrichment>
    <enrichment key="eventPlace">Charlotte, NC, USA</enrichment>
    <enrichment key="eventStart">14.11.2017</enrichment>
    <enrichment key="eventEnd">16.11.2017</enrichment>
    <enrichment key="InvitedTalks">0</enrichment>
    <author>Teresa Orellana Pérez</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Fuel cladding integrity</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Extended interim storage</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Spent fuel</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
  </doc>
  <doc>
    <id>45329</id>
    <completedYear/>
    <publishedYear>2018</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst/>
    <pageLast/>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>lecture</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">R&amp;D initiatives at BAM concerning spent nuclear fuel integrity during long term storage</title>
    <abstract language="eng">The presentation provides an overview about the understanding of fuel cladding failure mechanisms dominated by hydride embrittlement during long term dry storage. A currently launched research project focuses on the development of a fracture mechanics approach to describe brittle failure of fuel cladding during long term interim storage (BRUZL)“. Finally, the BAM contribution to the current European Joint Program (EJP) on radioactive waste management is illustrated.</abstract>
    <enrichment key="eventName">2nd GRS Workshop on Safety of Extended Dry Storage of Spent Nuclear Fuel</enrichment>
    <enrichment key="eventPlace">Munich, Germany</enrichment>
    <enrichment key="eventStart">06.06.2018</enrichment>
    <enrichment key="eventEnd">08.06.2018</enrichment>
    <enrichment key="InvitedTalks">0</enrichment>
    <author>Teresa Orellana Pérez</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Spent fuel</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Extended interim storage</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Hydride precipitation</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Fuel cladding integrity</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
  </doc>
  <doc>
    <id>44749</id>
    <completedYear/>
    <publishedYear>2017</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>1</pageFirst>
    <pageLast>8</pageLast>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>conferenceobject</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Relevance of cladding failure mechanisms due to zirconium hydride precipitation under extended dry storage conditions in Germany</title>
    <abstract language="eng">The German nuclear waste management strategy consists of dry interim storage of spent fuel inside dual purpose casks and its subsequent direct final disposal in a deep geological repository. Interim storage is limited to 40 years so far, but will have to be extended until repository site selection and operation is concluded, potentially up to 100 years. In this context, research on the long term performance of safety relevant cask components and fuel rod integrity during such extended periods of time is of outmost importance. The barrier function of the fuel cladding depends on its integrity under operational and accidental conditions along with storage and subsequent transportation and is mainly affected over time by altering of the cladding microstructure and by thermo-mechanical conditions during reactor operation and subsequent wet and dry storage. &#13;
This paper focuses on failure mechanisms regarding cladding embrittlement caused by physical phenomena concerning hydrogen dissolution and precipitation of hydrides in the zirconium matrix. Within this context, potential cladding integrity issues under extended interim storage conditions followed by transportation are emphasized.  &#13;
Delayed hydride cracking (DHC) is a well-known time-dependent temperature-activated phenomenon failure mechanism of the fuel cladding during reactor operation. The phenomenon consists of hydrogen diffusion and hydride precipitation at the tip of an initial crack and the propagation of the crack to an approximate distance equal to the length of the hydride. This failure mechanism is temperature-activated phenomenon and enhances along with thermal cycling of the fuel cladding, e. g. during reactor shutdowns. DHC shows limited relevance under quasi static storage conditions with continuously lowering temperatures. However, the literature points that DHC may occur when the temperature during storage decreases to a certain level after some decades and in combination with stress concentrations in the cladding material.&#13;
When spent fuel is transferred to dry storage by vacuum drying, the cladding temperature raises up to peak temperatures of ~370°C. Under these conditions, hydrides dissolute into the zirconium matrix up to the solubility limit defined by the peak temperature and this amount of hydrogen can precipitate in a radial re-oriented fashion due to the temperature decrease during storage. Cladding materials with radially precipitated hydrides show significant embrittlement. Radially oriented hydrides are perpendicularly oriented to hoop stresses representing the most critical configuration. Brittle failure of the cladding then occurs by crack propagation through radially oriented hydrides and finally through the zirconium matrix. The susceptibility to radial hydride precipitation depends on cladding material type and microstructure, hydrogen content, pre-drying hydride distribution, irradiation conditions, and temperature and stress histories during drying and storage operations.&#13;
This paper addresses major considerations concerning spent fuel cladding embrittlement due to hydride precipitation with regard to the boundary conditions of dry spent fuel storage in Germany. Analytical, numerical, and experimental approaches are to be discussed by BAM in order to identify the specific needs for future R&amp;D work in that area with the purpose to provide the necessary data base for proper safety demonstration and evaluation along with future extended storage licensing procedures.</abstract>
    <parentTitle language="eng">Proceedings of the 2017 Water Reactor Fuel Performance Meeting</parentTitle>
    <enrichment key="eventName">2017 Water Reactor Fuel Performance Meeting</enrichment>
    <enrichment key="eventPlace">Jeju, Korea</enrichment>
    <enrichment key="eventStart">10.09.2017</enrichment>
    <enrichment key="eventEnd">14.09.2017</enrichment>
    <author>Teresa Orellana Pérez</author>
    <author>Holger Völzke</author>
    <author>Dietmar Wolff</author>
    <author>Uwe Zencker</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Cladding</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Hydride precipitation</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Spent fuel</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Graue Literatur</collection>
  </doc>
  <doc>
    <id>43792</id>
    <completedYear/>
    <publishedYear>2017</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst/>
    <pageLast/>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>lecture</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Relevance of cladding failure mechanisms due to zirconium hydride precipitation under extended dry storage conditions in Germany</title>
    <abstract language="eng">The German nuclear waste management strategy consists of dry interim storage of spent fuel inside dual purpose casks and its subsequent direct final disposal in a deep geological repository. Interim storage is limited to 40 years so far, but will have to be extended until repository site selection and operation is concluded, potentially up to 100 years. In this context, research on the long term performance of safety relevant cask components and fuel rod integrity during such extended periods of time is of outmost importance. The barrier function of the fuel cladding depends on its integrity under operational and accidental conditions along with storage and subsequent transportation and is mainly affected over time by altering of the cladding microstructure and by thermo-mechanical conditions during reactor operation and subsequent wet and dry storage. &#13;
This paper focuses on failure mechanisms regarding cladding embrittlement caused by physical phenomena concerning hydrogen dissolution and precipitation of hydrides in the zirconium matrix. Within this context, potential cladding integrity issues under extended interim storage conditions followed by transportation are emphasized.  &#13;
Delayed hydride cracking (DHC) is a well-known time-dependent temperature-activated phenomenon failure mechanism of the fuel cladding during reactor operation. The phenomenon consists of hydrogen diffusion and hydride precipitation at the tip of an initial crack and the propagation of the crack to an approximate distance equal to the length of the hydride. This failure mechanism is temperature-activated phenomenon and enhances along with thermal cycling of the fuel cladding, e. g. during reactor shutdowns. DHC shows limited relevance under quasi static storage conditions with continuously lowering temperatures. However, the literature points that DHC may occur when the temperature during storage decreases to a certain level after some decades and in combination with stress concentrations in the cladding material.&#13;
When spent fuel is transferred to dry storage by vacuum drying, the cladding temperature raises up to peak temperatures of ~370°C. Under these conditions, hydrides dissolute into the zirconium matrix up to the solubility limit defined by the peak temperature and this amount of hydrogen can precipitate in a radial re-oriented fashion due to the temperature decrease during storage. Cladding materials with radially precipitated hydrides show significant embrittlement. Radially oriented hydrides are perpendicularly oriented to hoop stresses representing the most critical configuration. Brittle failure of the cladding then occurs by crack propagation through radially oriented hydrides and finally through the zirconium matrix. The susceptibility to radial hydride precipitation depends on cladding material type and microstructure, hydrogen content, pre-drying hydride distribution, irradiation conditions, and temperature and stress histories during drying and storage operations.&#13;
This paper addresses major considerations concerning spent fuel cladding embrittlement due to hydride precipitation with regard to the boundary conditions of dry spent fuel storage in Germany. Analytical, numerical, and experimental approaches are to be discussed by BAM in order to identify the specific needs for future R&amp;D work in that area with the purpose to provide the necessary data base for proper safety demonstration and evaluation along with future extended storage licensing procedures.</abstract>
    <enrichment key="eventName">2017 Water Reactor Fuel Performance Meeting (WRFPM 2017)</enrichment>
    <enrichment key="eventPlace">Jeju, Korea</enrichment>
    <enrichment key="eventStart">10.09.2017</enrichment>
    <enrichment key="eventEnd">14.09.2017</enrichment>
    <enrichment key="InvitedTalks">0</enrichment>
    <author>Teresa Orellana Pérez</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Spent fuel</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Cladding</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Hydride precipitation</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
  </doc>
  <doc>
    <id>45459</id>
    <completedYear/>
    <publishedYear>2018</publishedYear>
    <thesisYearAccepted/>
    <language>deu</language>
    <pageFirst/>
    <pageLast/>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>poster</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="deu">Verbundvorhaben KoBrA - Arbeitspaket 1 (a)</title>
    <abstract language="deu">Im Vorhaben "KoBrA" sollen aus bestehenden Anforderungen für endlagerfähige Behälter und aus internationalen Erfahrungen ein aktueller Stand auf dem Gebiet der Behälterforschung für HLW/SF-Behälter ermittelt und generische Vorschläge für HLW/BE-Endlagerbehälterkonzepte in den drei potentiellen Wirtsgesteinen (Kristallin, Ton oder Salz) erarbeitet werden.</abstract>
    <abstract language="eng">Within Project "KoBrA" we want to establish the international state of the art in final disposal containers for HLW/SF, and, based on boundary conditions and national legislation, to propose generic final disposal canister concepts for all three potential host rocks (crystalline rock, clay and salt) for the German high-level waste.</abstract>
    <enrichment key="eventName">Fachinformationsgespräch zum FuE-Vorhaben "KoBrA"</enrichment>
    <enrichment key="eventPlace">Berlin, Germany</enrichment>
    <enrichment key="eventStart">28.05.2018</enrichment>
    <enrichment key="eventEnd">28.05.2018</enrichment>
    <author>Christian Herold</author>
    <author>Holger Völzke</author>
    <author>Teresa Orellana Pérez</author>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Endlagerbehälter</value>
    </subject>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Hochaktive wärmeentwickelnde Abfälle</value>
    </subject>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Internationale Recherche</value>
    </subject>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Arbeitsflussdiagramm</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
  </doc>
  <doc>
    <id>45460</id>
    <completedYear/>
    <publishedYear>2018</publishedYear>
    <thesisYearAccepted/>
    <language>deu</language>
    <pageFirst/>
    <pageLast/>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>poster</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="deu">Verbundvorhaben "KoBrA" - Arbeitspaket 1 (b)</title>
    <abstract language="deu">Im Vorhaben "KoBrA" sollen aus bestehenden Anforderungen für endlagerfähige Behälter und aus internationalen Erfahrungen ein aktueller Stand auf dem Gebiet der Behälterforschung für HLW/SF-Behälter ermittelt und generische Vorschläge für einen deutschen HLW/BE-Endlagerbehälter in den drei potentiellen Wirtsgesteinen (Kristallin, Ton oder Salz) erarbeitet werden. Im Arbeitspaket 1 wird dafür eine umfassende Literaturrecherche zu internationalen Behälterkonzepten durchgeführt, deren erste Ergebnisse hier präsentiert werden.</abstract>
    <abstract language="eng">Within Project "KoBrA" we want to establish the international state of the art in design and concepts for HLW/SF final disposal Containers. Working package 1, encompassing an extensive literature research on this topic, yielded some preliminary results - promising container concepts - which are presented here.</abstract>
    <enrichment key="eventName">Fachinformationsgespräch zum FuE-Vorhaben "KoBrA"</enrichment>
    <enrichment key="eventPlace">Berlin, Germany</enrichment>
    <enrichment key="eventStart">28.05.2018</enrichment>
    <enrichment key="eventEnd">28.05.2018</enrichment>
    <author>Christian Herold</author>
    <author>Holger Völzke</author>
    <author>Teresa Orellana Pérez</author>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Endlagerbehälter</value>
    </subject>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Internationale Endlagerkonzepte</value>
    </subject>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Hochaktive wärmeentwickelnde Abfälle</value>
    </subject>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Final disposal cask</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
  </doc>
  <doc>
    <id>45466</id>
    <completedYear/>
    <publishedYear>2018</publishedYear>
    <thesisYearAccepted/>
    <language>deu</language>
    <pageFirst/>
    <pageLast/>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>poster</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="deu">Verbundvorhaben "KoBrA"</title>
    <abstract language="deu">Im Verbundvorhaben "KoBrA" sollen systematisch Randbedingungen, Anforderungen und Konzepte für BE/HLW-Endlagerbehälter in den potentiellen Wirtsgesteinen Kristallin, Ton und Salz gesammelt, zusammengetragen und ausgewertet werden. Am Ende sollen generische Behälteranforderungen und -Konzepte für mögliche endlagerfähige Behälter in Deutschland erarbeitet werden. Hier wird ein Überblick über das gemeinsam mit unseren Partnern von der DBE TEC (jetzt BGE TEC) bearbeitete Gesamtvorhaben mit allen Arbeitspaketen gegeben.</abstract>
    <abstract language="eng">Within Project "KoBrA" we will compile and analyse requirements, demands and concepts for HLW/SF final disposal containers for the potential host rock formations crystalline, clay and salt, and thereby establish proposals for generic final disposal canisters. This poster presentation offers an overview of all work packages we share with our Partners from DBE TEC (now BGE TEC).</abstract>
    <enrichment key="eventName">Fachinformationsgespräch zum FuE-Vorhaben "KoBrA"</enrichment>
    <enrichment key="eventPlace">Berlin, Germany</enrichment>
    <enrichment key="eventStart">28.05.2018</enrichment>
    <enrichment key="eventEnd">28.05.2018</enrichment>
    <author>Christian Herold</author>
    <author>Holger Völzke</author>
    <author>Teresa Orellana Pérez</author>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Projektvorhaben</value>
    </subject>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Endlagerbehälter</value>
    </subject>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>BGE TECHNOLOGY</value>
    </subject>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Literaturrecherche</value>
    </subject>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Endlageranforderungen</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
  </doc>
  <doc>
    <id>40412</id>
    <completedYear/>
    <publishedYear>2017</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>718</pageFirst>
    <pageLast>725</pageLast>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>conferenceobject</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation>American Nuclear Society, Inc.</creatingCorporation>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Cladding considerations at BAM regarding extended storage  spent fuel</title>
    <abstract language="eng">With the clear expectation of the need for extending spent fuel storage in Germany beyond the initial license period of maximum 40 years additional material data and knowledge about the long term performance and integrity of casks and internals like fuel rods will be required to meet major safety goals and regulatory requirements.&#13;
Based on a broad knowledge base about fuel cladding behavior, degradation mechanisms and related potential failure mechanisms, e. g. induced by reoriented Hydride precipitation, as illustrated in this paper, a specific gap analyses for the German situation regarding fuel conditions and cladding materials should identify the specific knowledge gaps to be addressed and closed in the near future. This is of specific interest as all spent fuel assemblies are going to be transferred to dry cask storage with the next decade and as a consequence of the German nuclear phase-out decision.&#13;
Within several decades, BAM as a Federal materials research institute gathered a broad range of expertise in the safety evaluation of materials, components and casks under operational and accidental thermal and mechanical conditions. This paper elucidates selected Basic considerations regarding technical and scientific knowledge about the long term aging performance and potential failure mechanisms of fuel cladding materials.&#13;
Under consideration of the national R&amp;D funding policy which has been adapted to the extended interim storage or pre-disposal needs and the competences of BAM, its future R&amp;D strategy is explained and some R&amp;D objectives have already been identified. BAM will continue and expand ist engagement in the area of investigating fuel cladding material behavior in the long term and developing validated simulation and analyses tools in collaboration with national and international partners. R&amp;D outcomes shall improve the knowledge-base to close identified knowledge gaps in the area of demonstrating fuel cladding integrity and to provide crucial information with regard to future safety assessments for the extended interim spent fuel storage.</abstract>
    <parentTitle language="eng">Proceedings of the 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017)</parentTitle>
    <enrichment key="eventName">16th International High -Level Radioactive Waste Management Conference  (IHLRWM  2017)</enrichment>
    <enrichment key="eventPlace">Charlotte, NC, USA</enrichment>
    <enrichment key="eventStart">09.04.2017</enrichment>
    <enrichment key="eventEnd">13.04.2017</enrichment>
    <author>Teresa Orellana Pérez</author>
    <author>Holger Völzke</author>
    <author>Dietmar Wolff</author>
    <author>Uwe Zencker</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Spent fuel</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Storage</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Fuel cladding</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Graue Literatur</collection>
  </doc>
  <doc>
    <id>40305</id>
    <completedYear/>
    <publishedYear>2017</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst/>
    <pageLast/>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>lecture</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
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    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Cladding considerations at BAM regarding extended storage of spent fuel</title>
    <abstract language="eng">The current German waste management strategy consists of dry interim storage of spent fuel inside dual purpose casks at various sites and its subsequent direct final disposal in a deep geological repository. Interim facilities are licensed for up to 40 years of operation but this storing period will have to be extended until repository site selection and operation is concluded, potentially up to 100 years. In this context, research on long term mechanical behavior of fuel cladding and cask components during extended interim storage and transportation to a final repository are of outmost importance. &#13;
Barrier properties of the fuel cladding depend on its integrity which is affected over time by thermo-mechanical loads and by microstructure altering including potential embrittlement caused by re-oriented hydride precipitation. Experimental and numerical investigations have been performed by the international research community in order to predict the degree of cladding embrittlement against storage time. Results have shown that embrittlement of cladding materials is governed by the concentration, orientation and size of precipitated hydrides. Nevertheless, the existing variety of fuel materials and assemblies available on the market and the many parameters effecting hydride precipitation do not allow sufficient reliable safety predictions in the long term without further investigation. &#13;
Thus, knowledge on cladding integrity over storage time and during subsequent transportation is to be gained taking into consideration the relevant fuel and cladding material types as well as cladding temperatures along with peak values during cask drying and cooling rates during storage periods. Expected research results will increase the accuracy of cladding safety analysis. This paper summarizes the current German status regarding extended interim storage and how BAM is going to identify and address potential cladding integrity issues in the long term.</abstract>
    <enrichment key="eventName">ANS Conference International High-Level Radioactive Waste Management (IHLRWM) 2017</enrichment>
    <enrichment key="eventPlace">Charlotte, NC, USA</enrichment>
    <enrichment key="eventStart">09.04.2017</enrichment>
    <enrichment key="eventEnd">13.04.2017</enrichment>
    <enrichment key="InvitedTalks">0</enrichment>
    <author>Teresa Orellana Pérez</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Spent Fuel Cladding</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Hydrides</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Storage</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
  </doc>
  <doc>
    <id>41061</id>
    <completedYear/>
    <publishedYear>2016</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst/>
    <pageLast/>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>lecture</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Design testing of containers for the Konrad repository</title>
    <abstract language="eng">The presentation explains the requirements, process and challenges of the container design testing procedures for the Konrad repository, where low and intermediate level radioactive waste is planned to be disposed of beginnung end of 2022. BAM performs container design testing for more than 30 years whether analytically or experimentally. The challenges of the complex Konrad requirements concerning their proper interpretation and application is discussed in this presentation.</abstract>
    <enrichment key="eventName">Joint Meeting between CSN-ENRESA-ENUSA and BAM</enrichment>
    <enrichment key="eventPlace">Madrid, Spain</enrichment>
    <enrichment key="eventStart">29.06.2016</enrichment>
    <enrichment key="eventEnd">29.06.2016</enrichment>
    <enrichment key="InvitedTalks">0</enrichment>
    <author>Teresa Orellana Pérez</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Radioactive waste</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Container</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Konrad repository</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Safety requirements</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
  </doc>
  <doc>
    <id>41062</id>
    <completedYear/>
    <publishedYear>2016</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst/>
    <pageLast/>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>lecture</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Technical Requirements for High Level Waste Disposal Containers with regard to their Retrievability during Operation and Recovery after Repository Closure</title>
    <abstract language="eng">The Bundesanstalt für Materialforschung und -prüfung (BAM) in Germany has gathered extensive expertise over decades in the fields of design testing and safety assessment of transport and storage containers for radioactive materials. On behalf of the German commission for the disposal of highly radioactive waste, BAM had been assigned the elucidation of requirements for high level waste disposal containers specifically in terms of their retrievability from deep geological formations during repository operation and recovery after its closure over a period of time between 500 to 1000 years. The output of the initial assessment is presented taking into account the frame of the current German repository site selection procedure together with the definition of repository conditions corresponding to the potential deep geological formations to be considered for disposal.&#13;
This presentation addresses the spectrum of relevant stress factors for disposal containers and reflects their relevance and consequences during the repository operation phase including the emplacement and their potential retrieval. In addition, further aspects and consequences for container recovery after repository closure are discussed taking into consideration potential repository conditions of different geological formations. &#13;
Finally, potential disposal container concepts are briefly addressed comparing the consequences of an improvement of existing dual purpose casks versus completely new disposal canister designs adjusted to the specific geological conditions of the host rock formation. Pros and cons of these two concepts are depicted in order to address major challenges. However, precise container design concepts cannot be consolidated before repository conditions and derived specific container requirements are designated.</abstract>
    <enrichment key="eventName">7th IGD-TP Exchange Forum</enrichment>
    <enrichment key="eventPlace">Cordoba, Spain</enrichment>
    <enrichment key="eventStart">25.10.2016</enrichment>
    <enrichment key="eventEnd">26.10.2016</enrichment>
    <enrichment key="InvitedTalks">0</enrichment>
    <author>Teresa Orellana Pérez</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Radioactive waste</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Disposal</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Container</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Safety requirements</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
  </doc>
  <doc>
    <id>59295</id>
    <completedYear/>
    <publishedYear>2022</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst/>
    <pageLast/>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>lecture</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">European policy framework regulations codes and standards for safe hydrogen technologies</title>
    <abstract language="eng">This lecture describes the history of hydrogen from the first scientific discoveries in the 18th century to the current technological and political developments for the market ramp-up of hydrogen technologies. The European policy framework for safe hydrogen technologies is explained comprehending the European Green Deal, European Climate Law, European Hydrogen Strategy, Clean Hydrogen Partnership, etc. Safety in hydrogen technologies is governed by international and European regulations and standards. An overview on regulatory bodies, technical committees, regulations, directives, standards, and technical guidelines with special attention on the BAM-GGR 021 is given in this lecture.</abstract>
    <enrichment key="eventName">Joint European Summer School 2022, Hydrogen Safety</enrichment>
    <enrichment key="eventPlace">Athens, Greece</enrichment>
    <enrichment key="eventStart">18.09.2022</enrichment>
    <enrichment key="eventEnd">24.09.2022</enrichment>
    <enrichment key="opus.source">publish</enrichment>
    <enrichment key="InvitedTalks">1</enrichment>
    <author>Teresa Orellana Pérez</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Hydrogen</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Safety</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Regulations</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Standards</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="institutes" number="">3 Gefahrgutumschließungen; Energiespeicher</collection>
    <collection role="themenfelder" number="">Energie</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
    <collection role="institutes" number="">3.5 Sicherheit von Gasspeichern und Gefahrguttanks</collection>
    <collection role="themenfelder" number="">Wasserstoff</collection>
  </doc>
  <doc>
    <id>59296</id>
    <completedYear/>
    <publishedYear>2022</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst/>
    <pageLast/>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>lecture</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Guest lecture: European policy framework regulations codes and standards for safe hydrogen technologies</title>
    <abstract language="eng">This lecture describes the history of hydrogen from the first scientific discoveries in the 18th century to the current technological and political developments for the market ramp-up of hydrogen technologies. The European policy framework for safe hydrogen technologies is explained comprehending the European Green Deal, European Climate Law, European Hydrogen Strategy, Clean Hydrogen Partnership, etc. Safety in hydrogen technologies is governed by international and European regulations and standards. An overview on regulatory bodies, technical committees, regulations, directives, standards, and technical guidelines with special attention on the BAM-GGR 021 is given in this lecture.</abstract>
    <enrichment key="eventName">MSc Fuel Cells and Hydrogen Technologies at the University of Birmingham (LM Hydrogen Safety, MSc FCHT module C7B)</enrichment>
    <enrichment key="eventPlace">Birmingham, UK</enrichment>
    <enrichment key="opus.source">publish</enrichment>
    <enrichment key="eventStart">21.10.2022</enrichment>
    <enrichment key="InvitedTalks">1</enrichment>
    <author>Teresa Orellana Pérez</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Hydrogen</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Safety</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Regulations</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Standards</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="institutes" number="">3 Gefahrgutumschließungen; Energiespeicher</collection>
    <collection role="themenfelder" number="">Energie</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
    <collection role="institutes" number="">3.5 Sicherheit von Gasspeichern und Gefahrguttanks</collection>
    <collection role="themenfelder" number="">Wasserstoff</collection>
  </doc>
</export-example>
